Sessions and abstracts are subject to change. Abstracts are arranged in the order the presentation is scheduled for the session.
- Tuesday 4 Jun 2024
- Wednesday 5 Jun 2024
- Thursday 6 Jun 2024
Tuesday 4 Jun 2024
8:15 am - 9:00 am Keynote
An IAEA update on NORM: ISEMIR-N platform and Intercomparison Exercise on NORM analysis
H. Burçin Okyar | International Atomic Energy AgencyEnoch ABC Ballroom
The IAEA is the one of the leading international organisations in establishing and maintaining the information exchange platforms, such as Information System on Occupational Exposure in Medicine, Industry and Research (ISEMIR), which is a tool to improve implementation of optimization of occupational radiation protection for interventional cardiology facilities (ISEMIR-IC) and for non-destructive testing companies carrying out industrial radiograph (ISEMIR-IR).
With the experience gained from the operation of ISEMIR modules, UMEX and others and demand from Member States to strengthen their capabilities for the realistic assessment of radiological impacts of NORM, a new web-based module (so-called ISEMIR-N) has been developed to improve the optimization of occupational radiation protection in different industrial processes involving Naturally Occurring Radioactive Material (NORM) through regular collection and maintenance of data on occupational exposure. The ISEMIR-N covers all NORM industrial processes and offers a model for dose assessment, but not in character of a dose registry and aims to enhance the worker protection through strengthening and harmonizing the radiation protection programmes for different NORM involving industrial operations and processes.
Design has been completed by March 2019 and IT development has been initiated by June 2021. The initial design characteristics were evaluated with an IAEA Technical Meeting that was organized in November 2021 attended by 69 official participants from 41 Member States.
The ISEMIR-N platform is in use with 54 users from 51 organisations.
The module with its conceptual background, organizational characteristics, technical content and interfaces will be described.
9:00 am - 10:15 am Session A - Safety Culture
Moderator: Leah Suparski-Miller
Compliance: a goal, a tool or a weapon of mass persuasion?
Stéphane Jean-François | Radioprotection Inc.Enoch ABC Ballroom
Let me be clear: this presentation is not really about compliance, but it is all about a strong safety culture! How can we make sure that our radiation protection program (RPP) is working properly, even when the Radiation Safety Officer (RSO) is enjoying a well-deserved Pina Colada on the beach?
Using key highlights from the applied experience of a RSO that had worked in many fields for the past 25 years, we present how an agile RPP can contribute to a desirable safety culture. We discuss the impact of existing and nonexistent regulations on medical, industrial or research radiation protection, for nuclear substances and X-ray applications. We will also discuss important aspects of a high quality, high performance RPP, as a master safety symphony:
- Playing the RSO’s important role as a maestro: develop your musical ear.
- Practicing and playing our safety symphony: communication and training
- Dealing with the entire orchestras: Holistic approach of risk management to present a coherent message to workers.
For this presentation, we present reference tools, available for everyone, to test, practice and enforce, your radiation safety culture.
Practical Considerations of Radiation Protection in Field Work
Alan Tung | Ontario Power GenerationEnoch ABC Ballroom
This presentation is an overview of a typical, though non-routine, task at Pickering Nuclear Generating Station from a field technician point of view. In this task, a 45gal D2O drum with elevated dose rates needs to be moved to a storage location. Due to the size and weight, moving the drum cannot be accomplished without specialized equipment and procedures that preclude the use of shielding on the drum. Radiological qualifications, typical instruments used, radiation personal protective equipment, and some procedures will be discussed. There are also challenges of an industrial nature that are unique to nuclear generating stations that will be discussed. One lesson that was learned is the importance of understanding the conditions and limitations of what can be done by field personnel. This is accomplished by inspecting the surroundings and equipment and getting input from people knowledgeable in this type of work.
Progressing Safety Culture – A Shared Responsibility
Jeff Fleming | Canadian Nuclear Safety CommissionEnoch ABC Ballroom
Nuclear Substance and Radiation Device (NSRD) licensees have no formal equirements under RegDoc 2.1.2 – Safety Culture but that doesn’t mean there isn’t a place for formal safety culture.
A great safety culture is vital to running a great radiation safety program!
This presentation will highlight some unique challenges and successes seen in NSRD licensees by Inspectors and give attendees an open forum to bring up their highlights and concerns in progressing their safety culture and how the Canadian Nuclear Safety Commission can help.
As a licensee, whether big or small, complex or simple, in management or not, everyone can all benefit from growing their safety culture – even if you aren't an NSRD licence.
Bridging Frameworks: A Comparison of Occupational Health and Safety's Hierarchy of Controls and the International System of Radiation Protection
T. Lynn MacDonald | Radiation Safety Institute of CanadaEnoch ABC Ballroom
Those responsible for radiation protection in the workplace come to the role through many different pathways. Experience training Radiation Safety Officers and X-Ray Safety Officers has revealed that while many will have previous radiation protection training, it is very common for those moving into these roles to come from Occupational Health and Safety or Industrial Hygiene.
Humans use mental models, or schema, to understand the world. They assimilate new information based on their existing schema. Those formally trained in radiation protection are well versed in the International System of Radiation Protection (ISRP), based on the fundamental principles of justification, optimization, and limitation as described in ICRP Publication 103. Those with training in Occupational Health and Safety or Industrial Hygiene in Canada or the United States work with a framework called the Hierarchy of Controls (HoC).
This presentation will compare these safety frameworks with consideration of how the schema of these two groups of radiation protection personnel may differ and look for obvious areas on which to build a common understanding of radiation protection in the workplace. Hopefully, consideration of this topic will lead to improved communication and help safety professionals avoid misconceptions which might arise due to differences in foundational knowledge.
10:45 am - 12:00 pm Session B - Radiation Protection
Moderator: Tara Hargreaves
Neutron standards and calibration services at the National Research Council Canada
Dr. John Paul Archambault | National Research Council CanadaEnoch ABC Ballroom
Neutron radiation is present in many laboratories and workplaces throughout Canada, such as nuclear power stations or radiation therapy clinics. Because radiation safety is of utmost importance to all users of these facilities, the National Research Council of Canada (NRC) offers a service to calibrate neutron survey meters. Neutron survey meters measure the ambient equivalent dose due to neutron radiation fields and are typically composed of a thermal neutron detector surrounded by a polyethylene shell. The shell is designed to moderate the neutron field, slowing down fast neutrons for detection in the thermal neutron counter. Neutron survey meters are calibrated at the NRC in a low-scatter laboratory using a well-characterised americium-beryllium (AmBe) neutron source. The large laboratory minimizes the effects of air-and room-scattered neutrons and enables the determination of a calibration coefficient which is independent of the facility characteristics. The presentation will cover the production of neutron radiation by an AmBe source and how the NRC determines the output of its neutron sources used in the survey meter calibrations. The unique, low-scatter neutron facility will also be described. This will be followed by a summary of how typical neutron survey meters are designed to work and an outline of the strategies and procedures the NRC uses during calibrations. Finally, the information typically found in a calibration report will be provided. The NRC calibration procedures adhere to ISO-8529: Neutron Reference Radiations Fields, the documents which guide the strategies for calibrating neutron survey meters and throughout the presentation, particular sections of the ISO-8529 documents will be highlighted by subject for easy reference.
Radiation Shielding Considerations for Cyclotron Operation (Part 1 of 2)
Dr. John Wilson | University of AlbertaEnoch ABC Ballroom
The cyclotron is a type of charged particle accelerator which produces a continuous stream of high energy protons. Targets comprised of stable elemental isotopes are bombarded by these protons to generate medical radioisotopes used for molecular imaging. When the proton beam interacts with the target material, a nuclear reaction occurs, and there is an emission of secondary particles and gamma rays which must have adequate radiation shielding for personnel protection. Neutrons are an emission product that are particularly hazardous as they are highly mutagenic. Considerations in cyclotron vault design and the necessary thickness and composition of shielding material and strategies to reduce the neutron flux during irradiation will be presented. Self shielded cyclotrons which do not require vault are also possible with the advantage of a much smaller space requirement for the cyclotron. Some of the draw-backs and issues with the self-shielded option will also be presented.
Shielding for Activated Components Produced during Cyclotron Irradiation (Part 2 of 2)
Dr. John Wilson | University of AlbertaEnoch ABC Ballroom
Neutron production ceases when beam is stopped however there are many secondary radionuclidic byproducts that result from interaction with the proton beam and from the generated neutron flux. Cyclotron targets can be in the gas phase (e.g.14N(p,α)11C), liquid phase (18O(p,n)18F) or solid phase (e.g.205Tl(p,3n)203Pb) and must be able to dissipate the tremendous heat caused by the beam on target. Gas and liquid targets operate at high-pressure and are sealed with a HAVAR metal foil through which the proton beam passes. HAVAR is exceptionally strong and flexible however is very prone to proton activation, generating long lived radionuclides byproducts. The interior of the cyclotron must have high electrical conductivity and is typically copper. Spurious protons from the beam on the copper result in secondary radionuclide formation and radiation field from the main tank at end of beam. The energy of the beam is degraded as it passes through target material and gas and liquid target are ‘thick’ targets as the entire beam is stopped in the target. Solid targets are used for elements of higher molecular number which can have multiple stable isotopes or can undergo various nuclear transformations depending on the beam energy. These are typically ‘thin’ targets as itis advantageous to stop only the desired energy fraction of the beam within the target material to reduce undesired radionuclide contaminants. Avoidance of cooling water activation from the lower energy exiting beam is important when irradiating thin targets. Neutrons emitted during irradiation have a high propensity to activate many materials in the vault. Moderation of the overall neutron field in the vault during irradiation is important to reduce activation of copper pipes, 63Cu(n,γ)64Cu, steel components, 58Fe(n,γ)59Fe and metal contaminants in the concrete.
Uranium content, distribution, and biokinetics in human body: USTUR studies
Dr. Maia Avtandilashvili | United States Transuranium and Uranium Registries, Washington State UniversityEnoch Ballroom ABC
Since 1968, the United States Transuranium and Uranium Registries (USTUR) has followed up occupationally-exposed individuals (volunteer tissue donors) by studying biokinetic and dosimetry of actinide elements. The USTUR currently holds data and tissue samples from six whole- and 38 partial-body donors with occupational uranium intakes. In this study, uranium tissue concentrations, body distribution, and biokinetics were compared between a group of individuals (two males and one female) with occupational exposure to uranium and a group with chronic environmental-only intakes (three males).
Of three occupationally-exposed individuals, one had chronic inhalation intake of uranium oxide with natural composition, another had acute inhalation of slightly enriched UF6, and the third (female) had both chronic and acute inhalation of highly enriched U3O8. For all six individuals, the skeleton was a major deposition site where 55 ± 17% of systemic uranium was retained at the time of death. The geometric mean concentration in the skeleton was 4.1 µg·kg-1 with a geometric standard deviation of 1.7. Systemic uranium was equally distributed between the skeleton and soft tissues. For five male cases, uranium content in systemic organs followed the pattern: skeleton >> spleen ≈ kidneys > liver ≈ brain > heart ≈ thyroid. For a single female case, the pattern was: skeleton >> brain ≈ kidneys > heart ≈ liver > thyroid ≈ spleen. For U3O8 inhalation, approximately 40% of occupational uranium was still retained in the skeleton, followed by the kidneys (~30%), and the brain and liver (~10%) 31 years after exposure. For UF6 inhalation, 65 years post-intake, approximately 40% of occupational uranium was retained in the brain, followed by the liver (~26%), and the skeleton (~21%) and kidneys (~7%).
10:45 am - 12:00 pm Session C - Radon 1
Moderator: Megan McDonald
Thoron Distribution profile of RRI thoron calibration chamber based on CFD simulation and its validation with measurement results
Dr. Mohammademad Adelikhah | Institute of Radiochemistry and Radioecology, University of PannoniaRiver Cree Ballroom 1
CFD is an inexpensive visualization tool that has been applied widely to solve health-related issues, such as predicting the activity concentrations of radon and thoron gas inside confined areas. Thoron gas is increasingly recognized as a potential source of radiation exposure in dwellings, so various organizations recommend assessing the long-term levels of indoor exposure (passive measurements). Obtaining accurate measurements requires determining the calibration factors for SSNTDs in order to predict the exact distribution of the thoron concentration inside a calibration chamber. Precise measurements are necessary to accurately assess radon and thoron dose exposure. Therefore, in the present study, the distribution of the thoron concentration was simulated and predicted inside the calibration chamber at RRI using different configurations for the inlet and outlet under various flow rates. The facilities at RRI were suitable for producing and sustaining the required homogeneous concentrations of thoron. Initially, the results showed that the transmission factor (Cout/Cin) increased after increasing the flow rate under all five chamber configurations tested in this study. The positions of the inlet and outlet, and the flowrate were also identified as key factors that determined the distribution of the thoron concentration within a closed volume, thereby affecting the transmission factor for thoron. The simulation results were also compared with the predictions obtained using the mixing model by defining the transmission factor (Cout/Cin), which can be used as a suitable indicator for checking the uniformity in terms of the distribution of the thoron concentration inside the chamber. Inconclusion, our results clearly demonstrate that the thoron calibration chamber at RRI is suitable for calibrating SSNTDs. Moreover, the CFD-based predictions agreed well with the experimental and analytical results according to the relative deviations and close agreement between the corresponding transmission factors in at higher flow rates.
AN EARLY LOOK INTO THE 2024 CROSS CANADA RADON REPORT: A symmetric, balanced understanding of Canadian residential housing radioactive radon gas exposure
Dr. Aaron A. Goodarzi | Robson DNA Science Centre, University of CalgaryRiver Cree Ballroom 1
Over the past five years, and in collaboration with multiple partner teams, the Evict Radon National Study teams from across Canada have integrated almost100,000 long term residential radon gas readings with housing, regional community, and population information from the 2021Canada Census to establish a clear, symmetric understanding of Canadian radon exposure within the residential built environment. With essential funding from the Canadian Institutes of Health Research Healthy Cities program, our teams have integrated pan-Canadian cohort of long-term residential radon test outcomes to detailed property and human demographic data. Using this, we have normalized all findings to the key administrative human and housing statistics assembled by Statistics Canada in the most recent (2021) census to produce an appropriately weighted understanding of radon exposure across Canada. The resulting Canadian residential radon data are now “symmetric” (meaning that they are fully balanced to the reality of Canada in the 2020s)by region, diverse communities (urban to rural),and residential building design types. We have used this data to derive population-attributable risk of lung cancer from radon (by region and other factors), as well as to understand and build tools to assess the impact of the built environment, behaviour, and demographics on personalized risk alpha radiation exposure (to the lungs) from radon. The outcome(s)of this work forms the basis of the once-per-decade Cross Canada Radon Report being produced in close collaboration with Health Canada and other public health agencies. The report will help inform physical, social and policy interventions required to mitigate lung cancer risks attributable to radon inhalation in Canada. During my talk, I will provide the Canadian radiological protection community an early look into the content of this report, which is slated for release in Fall 2024, outlining how it will be presented for the general public with anticipated timelines.
The population-level impact of residential radon exposure on lung cancer across Canada
John Danforth | Robson DNA Science Centre, University of CalgaryRiver Cree Ballroom 1
Lung cancer is the leading cause of cancer-related death in Canada, of which 40% of cases are now attributable to non-tobacco environmental toxicant exposures such as inhalation of radioactive radon (222Rn) gas and its decay products. Buildings can contain radioactive radon gas to harmful levels, exposing occupants repetitively to alpha particle radiation emissions that modify lung cancer risk, with a 16% increase in relative lifetime risk of lung cancer per 100 Bq/m3 long term exposure to alpha radiation from radon. Through the Evict Radon National Study, we have generated a detailed, up-to-date, and (relative to the current state of Canadian communities, buildings, and people) statistically representative dataset of residential radon concentrations. Using information from nearly 100,000 Canadian participants, we have combined household Bq/m3 indoor air radon levels with the activity pattern information (i.e. time spent at home, outside, or in any other indoor air environment) of individuals to determine an equivalent alpha radiation dose from radon to the lungs, in millisieverts (mSv) per time spent in the home. To do this, we employed the International Commission on Radiological Protection (ICRP) standardized formula for converting radon level to personalized estimations for radiation doses from radon. Using this and estimates for relative risk of lung cancer from residential radon gas exposure, we derived population attributable risk (PAR) estimates. These values represent the relative proportion of Canadian lung cancer cases attributable to residential radon exposure in the context of both measured radon concentrations as well as doses in mSv/year. We then expressed all outcomes relative to recent Canadian census information on regionality, housing type, and community type to generate a well-rounded perspective of lung cancer risk from radon-related radiation exposure across diverse Canadian groups.
Radon and Energy Efficiency a Collaborative Steps Forward
Dr. Anne Marie Nicol and Pam Warkentin | BC CDC and CARST/C-NRPPRiver Cree Ballroom 1
Retrofitting existing homes and buildings is a necessary step for Canadian governments wanting to meet climate goals. However, renovations can significantly impact indoor air contaminants including radon. After providing a summary of current research, this presentation will talk about the collaborative efforts that are needed to begin to address this issue.
1:30 pm - 2:45 pm Session D- Radon 2
Moderator: Cody Cuthill
Design and Development of a Canadian Radon Calibration Chamber
Athena Wang | Radiation Safety Institute of CanadaEnoch ABC Ballroom
The Radiation Safety Institute of Canada has operated a radon chamber for more than 30 years at its National Laboratories, in Saskatoon, Saskatchewan, Canada. The chamber has and continues to be used for quality control, performance testing, and research and development for the Institute’s personal alpha dosimeters under its federally licensed Personal Alpha Dosimetry Service for radon progeny and long-lived radioactive dust. In 2017 the Institute, in collaboration with Health Canada, enhanced the radon calibration chamber to also service radon measurement professionals in Canada. The chamber is currently the only AARST-NRPP accredited secondary radon calibration chamber in Canada. In addition to supporting the Institute’s PAD Service, the chamber is used to provide quality control, calibration, and testing for other radon measurement devices, as well as conducting applied research in controlled atmospheric environments. Within the 12 m3 walk-in chamber, radon concentrations can be varied and controlled between 150 Bq/m3 and 500 kBq/m3 utilizing gas-flow-through sources and computer-controlled air management systems. Radon progeny concentrations can be varied and controlled using an aerosol injection system. The chamber includes multiple reference measurement. The chamber has a comprehensive quality assurance program which includes routine chamber intercomparisons with the Bowser-Morner facility in Dayton, Ohio, USA to ensure traceability. Since certification in 2017, the Institute has tested over 600 instruments. In this presentation I will share the design and commissioning work conducted by the Institute and lessons learned to certify the Radon Calibration Laboratory.
International InterComparison of Radon 222 Activity Concentration Calibration Facilities
Pam Warkentin | CARST/C-NRPPEnoch ABC Ballroom
The Coalition of International Radon Associations (COIRA) organized an inter-comparison of Rn-222 (radon) activity concentrations reported by calibration laboratories. A set of three AlphaGUARDs were used as transfer reference instruments against which to compare reported Rn-222 activity concentrations. Rn-222 activity concentration calibration facilities (sometimes termed chambers) from seven countries (Australia, US, Czech, Spain, England, Sweden, Canada), and 3 continents participated in this project. The objective of the study was to provide information useful to calibration chamber operators and public health officials in the improvement of measurement and control systems, the maintenance of performance standards for measurements, and regulatory requirements for calibrations.
The human behavioural, built environmental and socio-demographic variables of residential alpha particle radiation doses to the lungs
Dr. Dustin Pearson | University of CalgaryEnoch ABC Ballroom
Our goal is to understand alpha particle radiation doses to the lungs from the inhalation of residential radon gas (and its progeny) within the Canadian population, as radon is a leading cause of lung cancer. To do this, we have analyzed multiple the variables that alter exposure, such as the building characteristics (i.e. property size, insulation levels, window glazing, year of construction, etc.) and how radon levels within indoor air dynamically fluctuate in real time (i.e. radon’s indoor air dynamics). As part of this work, the Evict Radon National Study team collected and analyzed hourly real time radon levels in a case study of 50 residential properties located in the Canadian Prairies over one or more years. I will describe radiation exposure outcomes and knowledge derived from >0.6 million continuous hourly radon readings expressed as a function of building, geographic, and seasonal variability. I will also contextualize these case study findings using the ~100,000 nation-wide residential radon readings that form the basis of the upcoming 2024 Cross Canada Radon Report. Using both datasets, I will present a detailed perspective on the how the indoor air dynamics of radon is modified by both residential property characteristics, seasonal weather fluctuations, and human behaviour to define personalized and population radiation doses to the lungs from radon. Finally, I will demonstrate predictive models that describe the building characteristics most often associated with radon doses across the health-impacting range, highlighting the correlative and causative factors underlying Canada’s substantial and worsening radon gas exposure problem.
1:30 pm - 2:45 pm Session E - X-Ray
Evaluation of the Entrance Surface Doses (ESD) for common diagnostic X-ray examinations
Dr. Nada Alomairy | Diagnostic Radiography Department, Jazan UniversityRiver Cree Ballroom 1
Objective: The purpose of this study was to assess the Entrance Skin Dose (ESD) in patients undergoing multiple types of radiographic examinations across three hospitals in Saudi Arabia.
Methods: The patient ESD was estimated directly using optically stimulated luminesces (OSL) and indirectly using a survey meter and calculations for 100 adult patients undergoing common diagnostic X-ray examinations, including a posterior anterior chest, posterior anterior hand, anterior posterior foot, and anterior posterior knee examinations, in three hospitals in Saudi Arabia. Comparative analysis with national and international reference values was conducted.
Results: Our analyses revealed considerable heterogeneity in X-ray exposure parameters among the hospitals. The mean ESD values for the chest examination were 0.28 ± 0.13 mGy for the direct method and 0.19 ± 0.11 mGy for the indirect method. Hand examination using the direct method resulted in a mean ESD of 0.42 ± 0.15 mGy, while the indirect method yielded 0.23 ± 0.06 mGy.
Remarkably, the ESD values in most cases exceeded national and international guidelines, with the knee examination ESD using the direct and indirect methods showing an alarming value of 1.54 ± 0.31 mGy and 1.18 ± 0.21 mGy, respectively. The correlation between direct ESD, indirect ESD showed a strong positive correlation exists between direct ESD and Indirect ESD (r = 0.8, p <0.001).
Conclusion: The study highlights the urgent need for standardized protocols and quality control measures across radiographic facilities in Saudi Arabia. The elevated ESD values signify a critical issue that requires immediate attention to minimize patient radiation exposure while maintaining diagnostic image quality. Quality control tests and adjustments in examination parameters are strongly advised.
Challenges of Implementing a New Radiation Protection Program In Dentistry in Québec
Manon Rouleau | Radioprotection Inc.River Cree Ballroom 1
In 2022, following a consultation with all stakeholders, Health Canada amended its guidelines on radiation protection in dentistry with the publication of a new standard entitled " Radiation Protection in Dental Practice: Safety Procedures for the Installation, Use and Control of Dental X-ray Equipment - Safety Code 30 (2022 ) ". The previous standards dated from 1999.
The objective of the 2022 standard is to update and standardize radiation protection practices across the country. It takes into account the new technologies available in dentistry, such as portable equipment, cone-beam computed tomography (CBCT) and digital sensors. It also includes the most recent international radiation protection standards and the latest Canadian legislative changes (2018) concerning design, construction and operating criteria for dental X-ray equipment.
There are more than 2000 dental clinics in Quebec (including academic clinics and hospital clinics). Nearly 10 000 dental X-ray machines are in use throughout the province, including more than 500 CBCT. Radiation protection regulations for dentistry are from 1981, and no upgrades have been announced.
Although several elements of these new guidelines reinforce radiation protection practices, others are in opposition with Quebec regulations. In this context, medical organizations, professional orders and associations have taken an individual interest in the implementation, in whole or in part, of this new standard, targeting, for example, use of portable equipment (banned in Quebec’s private clinics), or quality control conducted by radiation protection experts. We present the case of the Ordre des hygiénistes dentaires du Québec, which has opted for a holistic approach that will both better equip its members and train the next generation in radiation protection. We will discuss these initiatives from the perspective of ALADA and the latest UNSCEAR data on population doses from medical procedures.
3:15 pm - 4:30 pm Session F - Medical
A Treatment That Keeps Giving
Jeff Dovyak | Shared HealthEnoch Ballroom ABC
With increasing interest/use of theranostics, there may well be situations where radionuclide therapy (RNT) patients are encountered in hospital who weren’t actually treated by that hospital. Is there a requirement for RSOs in the non-treating hospital to get involved?
A pediatric patient living in Winnipeg required I-131 MIBG RNT for a neuroendocrine tumor. He was treated at a specialty hospital in another province and came back to Winnipeg after a brief radiation isolation. His condition required an unexpected hospitalization in Winnipeg which no-one was prepared for. “Hot” diapers started showing up at the local landfill and Manitoba Environment was bringing back bags & bags of “hot” diapers that really didn’t pose a radiological hazard (none of our landfills can accept radioactive material).
A local protocol was created with input from the pediatric oncologist, the manager of the pediatric ward that had this patient and radiation safety professionals involved with this case, so that ad hoc approaches can be minimized with future RNT patients treated elsewhere who come to one of our hospitals. The final protocol was shared with the pediatric oncologist, the oncology clinic nurse, the pediatric ward that would expect to see future patients such as this, as well as the pediatric Intensive Care and Emergency Room departments and relevant RSOs. This oral presentation will address the situation and actions taken by Radiation Safety staff.
Experiences from a High Dose I-131 Trial at University Health Network
Matthew Bernacci | University Health NetworkEnoch ABC Ballroom
As the largest health research organization in Canada, the University Health Network has attracted many clinical trials in the promising field of targeted Theranostics. One such trial is presented here, highlighting the unique challenges of a high dose I-131 therapy study where administration and inpatient stay occurred in a hospital ward without intended radioisotope design considerations. The study involving an I-131 radiopharmaceutical (mean therapy activity of 600 mCi), required multidisciplinary collaborations between oncologists, nurses, nuclear medicine, radiation safety, trial sponsors, and various other support staff. Due to the administered activity amounts and lack of a dedicated shielded inpatient room, portable lead shields of 1/4” and 1” thickness were implemented. Dose and contamination considerations to caregivers, staff, and other members of the public were evaluated. An inpatient stay of several days was required for medical monitoring, and radioactive isolation to minimize exposures to others. Contamination and access controls were established, and exposures to surrounding areas assessed. Doses received by staff directly involved in patient care were tracked to verify they remained below applicable dose limits. Several training sessions were offered to a large pool of hospital staff, the majority having limited experience with radioactive patients. In addition to licensing the patient room, a small research lab was commissioned as a nuclear medicine hot lab. This presentation will describe the process from licensing of new locations, training of staff, room preparation, administration, patient stay, waste management, and final release/clearance.
Lessons Learned: A Thyroid Uptake of over 100%
Sarah Ternan | The Ottawa HospitalEnoch ABC Ballroom
A discussion about the lessons learned following a case in the Nuclear Medicine Department where a patient had a thyroid uptake of over 100%. A patient travelled from Iqaluit to Ottawa for a thyroid uptake and scan in Nuclear Medicine prior to an Iodine 131 Hyperthyroid Therapy. Their 24hpd thyroid uptake unexpectedly demonstrated a value exceeding 100%. Will discuss the investigation into the situation, the parties involved including the radiation safety department’s role, and the resolution, which ultimately lead to an award-winning publication in the Journal of Nuclear Medicine
Imaging and quantifying radioactive contamination with gamma cameras in Nuclear Medicine departments
Dr. Marjorie Gonzalez | Interior HealthEnoch ABC Ballroom
Nuclear medicine departments are equipped with gamma cameras with NaI scintillation detectors that are optimized to detect photons with energies ranging from around 20 keV to 400 keV. The cameras have lead collimators to narrow down the direction of the incoming photons and they allow for the creation of images with spatial resolutions ranging from around 0.6 cm to 1.5 cm. In addition, when these cameras are properly calibrated, the counts collected can be used to estimate the amount of activity that is being imaged.
Several years ago, we started to use these gamma cameras to image and quantify radioactive contamination on staff who have been accidentally contaminated during the course of their clinical work. This has proven to be a very useful technique, as it can help to locate the body areas that are contaminated, the extent of the contamination, and the amounts of activity involved. The information collected has helped to guide the management of these incidents. In this talk, I will review the use of gamma cameras to image and quantify radioactive contamination on persons. I will review the imaging and calibration parameters that have been used and show examples of contamination incidents where imaging has been performed. I will also discuss some of the advantages and disadvantages we have encountered with this technique.
3:15 pm - 4:30 pm Session G - NORM
NORM in the Oil and Gas Industry
Cody Cuthill | Normtek Radiation Services Ltd.River Cree Ballroom 1
As awareness to human exposure to Naturally Occurring Radioactive Materials (NORM) grows, radiation protection and NORM waste management guidance is necessary to protect workers, the public and the environment from the hazards presented by radionuclides of natural origin. Radon Gas was first identified in the Canadian Oil and Gas Industry in 1904 during research on petroleum reserves and its uses at the time. However, it wasn’t until 1988 that NORM came under regulatory oversite when Lionhead Engineering and Consulting Ltd. identified NORM impacted tubing during a routine well abandonment in Alberta. Jurisdiction over control of exposures of NORM to workers and members of the public and NORM management authorizations rests with each Canadian Province or Territory. Industries seeking advice on the management of NORM would seek this advice from the relevant Occupational Health and Safety Regulators or Environmental Protection Regulators. This advice has traditionally been given on an ad hoc basis as regulations surrounding NORM have not been developed. Canada has adopted the recommendations of the International Atomic Energy Agencies (IAEA) and developed Canadian NORM Guidelines. However, the principles and practices have not been well understood and have been difficult for non-radiation professionals to understand without the development of formal regulations. This has resulted in inconsistent handling practices within different industry sectors and between provinces. This paper outlines how NORM waste is formed, managed and disposed, within the Oil and Gas Industry to meet the recommendations of the IAEA and Canadian NORM Guidelines.
NORM Characterization
Jenna Smith-Windsor | Saskatchewan Research CouncilRiver Cree Ballroom 1
The Canadian Guidelines for Naturally Occurring Radioactive Material (NORM) set out principles and procedures for the detection, classification, handling, and material management of NORM in Canada. NORM which includes radioactive elements found in the environment including long-lived elements of uranium, thorium, and potassium, and any of their radioactive decay products, such as radium and radon. Although the concentrations of NORM in most natural substances is low, higher concentrations may arise as the result of human activities. Disposal of NORM sources also requires consideration of the effects of dilution, possible reconcentration of the material in the environment, and the manner in which the material may deliver radiation doses to the public.
To assist in NORM material management, Derived Release Limits (DRLs) have been determined from the annual radiation dose limits. The DRLs provide an estimate for public dose from measured releases of NORM. A Radiation Assessment or characterization of the radiological properties may compare measurement results to DRLs. DRLs for the amount and concentration of NORM materials that meet this criteria have been calculated and are presented in the Guidelines as Unconditional Derived Release Limits (UDRLs).
The Saskatchewan Research Council (SRC) Environmental Analytical Laboratories role in the NORM material management is to provide a radiation assessment or characterization of the NORM material to help industry assess if these waste materials meet the release limits outlined in the Guidelines. This presentation will discuss the recommended sampling procedures to ensure a homogenous sample representation for NORM analysis; SRC’s NORM analysis packages; and how the radionuclide analysis relates to the UDRLs and NORM transportation Guidelines.
Derivation and Comparison of the Canadian Guidelines for the Management of Naturally Occurring Radioactive Materials’ Unrestricted Derived Release Limits
Dr. Kenneth Moats | Health CanadaRiver Cree Ballroom 1
Health Canada, in support to the Federal Provincial Territorial Radiation Protection Committee (FPTRPC), is currently updating the Canadian Guidelines for the Management of Naturally Occurring Radioactive Materials (NORM). The guidelines will support the various regulatory authorities across the provinces and territories and are intended to help harmonize protection of the public and workers within Canada. The updated guidelines will be comprised of 3 volumes: the first on radiation protection as it applies to NORM, the second on radon, and the third on NORM transportation. The third volume has been recently published and is being updated based on feedback from users and the Canadian Nuclear Safety Commission (CNSC). The two other volumes are being completed and will clarify the scope of the guidelines, as well as recommendations related to worker protection strategies and, in particular the Unrestricted Derived Release Limits (UDRLs). This presentation will cover the current methodology used for the determination of the UDRLs for diffuse solid, liquid, and airborne releases. The UDRLs will be compared to the CNSC exemption and clearance levels, and the methodology will be compared to that used by the International Atomic Energy Agency (IAEA) in their recommendations for NORM release criteria. We will compare the differences and possible implications of the implementation of each method. In addition, an overview of some of the proposed updates to the guidelines will be given.
4:30 pm - 5:30 pm Anthony J. MacKay Student Paper Contest – Finalist’s Presentations
Ionizing radiation exposure effects across multiple generations in non-human biota
Shayenthiran (Shayen) Sreetharan | McMaster UniversityEnoch ABC Ballroom
The potential for radiation-induced deleterious effects in progeny, and thus, in next generations is a major concern for parents exposed to ionizing radiation from occupational, medical or environmental sources. To date, the systems of radiological protection do not quantify or consider the possibility for effects that may manifest in subsequent generations following the initial exposure. A Task Group (TG121) of the International Commission on Radiological Protection (ICRP) Committee 1 was launched in 2021 to study the effects of ionizing radiation in offspring and next generations. One goal of TG121 was to review the literature on both multi-generational (in which the exposure continues across multiple generations) and trans-generational (in which later generations are not exposed during a recovery period) effects in non-human biota. With shorter generation times in these non-human species, they offer a unique tool to monitor and study generational effects following radiation exposure, although the underlying biological and physiological differences amongst these species must be carefully considered.
Methods: A review of multiple online databases (Google Scholar, PubMed, Scopus) was completed in 2022 by performing keyword searches related to the topics of multi- and trans-generational effects of ionizing radiation in non-human species. Both laboratory-controlled experiments and field studies were considered, with the latter typically containing ecological studies from either the Chernobyl Exclusion Zone or the Fukushima-Daiichi prefecture. In addition to studies identified from online databases, we also considered published reviews, conference proceedings and expert reports within our review.
Results: Studies were grouped into categories based on the model organism used, which includes species of bacteria, nematodes and annelids (largely Caenorhabditis elegans), crustaceans (largely Daphnia magna), insects, amphibians, birds, fish, mammals and plants. Details regarding exposure schedule (multi-generational, trans-generational or environmental exposure), generation numbers studied, endpoints monitored and results were summarized into a table. Effects on altered reproductive parameters were reported in offspring, with this observation present in different study models. In some studies, decreased survival in offspring was also observed, however these studies typically involved chronic, persistent exposure of numerous generations to a radiation field or following very large acute doses in trans-generational studies. There was also a number of studies in different study species that reported changes in genetic and epigenetic endpoints, with transmission of epigenetic changes into subsequent generations previously described as a possible mechanism for multi- and trans-generational irradiation effects. Changes in genome methylation, histone modifications, chromosomal aberrations and other mutations were reported in plants (Arabidopsis thaliana and flax), nematodes (Caenorhabditis elegans), insects (Drosophila melanogaster) and amphibian (Japanese tree frogs and Eastern tree frogs) species. Overall, the diversity of available non-human biota data brings complexities regarding the application of any reported results into the systems of radiological protection. We propose that differences in radiation sensitivity between species, transferability of data between different species, the presence of adaptation and adaptive responses, and dose reconstruction across subsequent generations and finally extending knowledge to humans represent key knowledge gaps within this field.
Conclusion: The goal of this paper was to perform a literature review of studies that investigated multi- and trans-generational effects in non-human biota, and to consider the incorporation of this evidence into the systems of radiological protection. The reported effects in altered reproduction represent an area of potential concern, due to the importance of population and ecosystem structure within ecological radiation protection. This is in contrast to human radiation protection, which considers effects at an individual level. Future work of ICRP Task Group 121 will continue to review this literature, with a final ICRP Publication that will be published for the radiation protection community.
RDS-112 Cyclotron Facility Decommissioning
Meghan Sanderson | McMaster UniversityEnoch ABC Ballroom
The RDS-112 cyclotron facility, consisting of an 11 MeV self-shielded cyclotron, was located in the McMaster University Medical Centre in Hamilton, ON. This facility was operated from 1990-2018, producing radioisotopes for medical imaging and research; primarily F-18 along with C-11, N-13 and O-15. The McMaster University Health Physics Department provided radiation safety support throughout the lifetime of the facility. By 2018, when all operations ceased, the cyclotron was owned by the Centre for Probe Development and Commercialization. All sealed and unsealed radioactive material was removed and it was determined that the facility would be decommissioned. However, the problem at hand was determining the process, as the option to remove the cyclotron as a whole was expensive and not feasible. The final decision was to dismantle the cyclotron and its related components, with the work being planned and led by McMaster Health Physics.
Methods: Samples and measurements of the internal components and the surrounding concrete shielding were taken to characterize and estimate the extent of activation. From this data, the decommissioning plan was created. In April 2023, researchers at King’s College London (KCL) identified 82 components of the RDS cyclotron which they could use for their own cyclotron. These components were removed, surveyed and cleared for release for shipment. All 82 components showed activation below exemption quantities or below minimum detection limits. In June 2023, an opening was created in the exterior wall of the building and the demolition commenced. Air sample measurements were taken during the demolition of the concrete shields to determine if this generated any airborne contamination. Daily contamination surveys were performed to ensure that no loose contamination was generated. The demolition began with the 6 surrounding concrete shields which contained majority of the total material, working towards the central components of the cyclotron. The shields were demolished in sections from which representative samples were taken and analyzed. All samples were surveyed for both loose and fixed contamination using contamination and dose rate meters prior to being removed from the building. Further analysis was performed using low-energy gamma spectroscopy along with liquid scintillation to characterize and quantize what, if any, activation products were present.
Results: The pre-demolition samples showed that the activation was mostly localized to the metal components around the ion source, extraction ports and target stations. The inner six inches of the concrete shields also showed low levels of activation. As demolition proceeded, the analysis confirmed that the activity levels of majority of the material were well below the exempt and unconditional clearance limits and was able to be unconditionally released. The lead shielding surrounding the targets also showed no activity above the minimum detectable limits. Approximately 56,600 kg of material was exempt or unconditionally cleared, and approximately 5,700 kg is considered to be potentially radioactive. The activated components not able to be unconditionally released were found to be parts of the more centralized components, consisting of a small section of the North and bottom steel shields surrounding the magnet, two floor tracks, I-beams and a localized portion of the upper and lower magnets near the targets. These remaining materials will be kept under McMaster’s consolidated licence until a plan for conditional release or radioactive waste disposal is finalized.
Conclusion: This project was the first of its kind in Canada completed under a Canadian Nuclear Safety Commission (CNSC) licence to decommission an isotope production accelerator facility. The decision to dismantle the cyclotron resulted in majority of materials being unconditionally released, in addition to many of the parts being reused in the RDS cyclotron at King’s College. This proves to be a viable alternative to the expensive option of removing the cyclotron as a whole.
Estimation of Effects of Filtration and Ventilation on Worker Inhalation Dose from Aerosols During Nuclear Dismantlement
Nicholas Somer | Ontario Tech UniversityEnoch ABC Ballroom
During the decommissioning of nuclear power plants, radioactive contaminants may be released into the work environment in the form of aerosols, which can expose workers through inhalation, ingestion, and submersion pathways. Workers often perform dismantlement work in confined spaces and sealed-off environments. Typical engineering controls to reduce concentrations include air exchange as well as air filtration, which captures aerosols at their source. The dose reduction from these engineering controls is generally not well understood. Given that there exist a variety of filtration methods of varying efficiencies and throughputs, a method of estimating dose reduction for a variety of work scenarios is desirable.
Methods: This work presents a model of radioactive aerosol concentration. It is used to estimate worker committed effective dose. The model considers dismantlement work parameters such as work time, aerosol source rate, air exchange along with air filtration and air filtration efficiency. The concentration over time is compared to a worst-case aerosol buildup based on no filtration nor air exchange.
The committed effective dose (CED) due to inhalation from the aerosols is calculated applying the approach of ICRP 119: the dose is proportional to the inhaled activity [1]. The rate of activity inhalation is proportional to the concentration of aerosols in the air. By integrating the concentration over time for an entire shift, the dose to a worker can be estimated. These calculations involve integrations of elementary functions, which allows for scalability of the model and calculations that are easily done on spreadsheets.
Results:Aerosol concentration over time is not dictated exclusively by the filter flow rate, the filter’s capture efficiency, and the air exchange rate of the room. Instead, it is dictated by a combination of all these factors, referred to as the cleaning period 𝜏. The cleaning period identifies the trade-offs that can be made between air exchange and filtration. Further, this is an engineering parameter which applies to any workspace size.
By comparing to the worst-case of no ventilation or filtration, the reduction of worker dose over a 10-hour shift can be determined. The dose reduction is exclusively a function of the cleaning period 𝜏 and dismantlement shift structure, i.e., when work is and is not being performed. The dose reduction is independent of scenario-specific parameters such as workspace volume, aerosol source rate, PPE, etc. and so can be used to model aerosol dose reduction in different dismantlement scenarios.
This paper produces two useful charts for filter selection. The first chart outlines the required cleaning period 𝜏 for a desired dose reduction for the modelled 10-hour worker shift. The second chart outlines the necessary combination of filter efficiency and flow rate for a single filter to achieve the cleaning period for such a space. These types of charts are a tool for engineers and health physicists to consider when building work packages, selecting engineering controls for dismantlement work, and so on.
Conclusion: This paper presents a mathematical model of the evolution of aerosol concentrations over time during dismantlement work using various dismantlement work parameters, such as aerosol source rates, workspace size, air exchange and filtration, and so on.
The engineering parameter referred to as a cleaning period 𝜏, which emerges from the model, determines the growth or reduction in aerosol concentrations over time, and ultimately the worker dose.
For a desired dose reduction, charts to select for cleaning period and associated filtration parameters can be generated for work package design. The models suggest that filtration systems, which often tout their capture efficiencies, should also have their specified flow rates considered.
Wednesday 5 Jun 2024
9:00 am - 10:15 am Session H - Academic
Safely developing an 18F-Labeling Maltose Dendrimer Radiotracer for Positron Emission Tomography (PET) Imaging of Heparanase
Yinglan Pu | University of AlbertaEnoch ABC Ballroom
Background: Heparanase, the only mammalian enzyme capable of degrading heparan sulfate (HS), plays a crucial role in various cellular processes including angiogenesis, inflammation, and cancer cell metastasis. Its overexpression in cancer cells makes it an attractive target for anti-cancer therapies. However, the development of heparanase-targeting radiotracers for positron emission tomography (PET) diagnostic imaging or for cancer treatments has been limited. In this study, we utilized a dendrimer HS glycomimetic heparanase inhibitor as a precursor to develop a Fluorine-18 labeled PET imaging agent.
Methods and Results: Our radiotracer was crafted by replacing one arm of the dendrimer with a fragment containing a silicon-fluoride acceptor (SiFA) moiety. Assessment of the radiotracer’s binding to heparanase was conduct using a colorimetric affinity assay based on Ferro’s method, yielding a reasonable 200 nM IC50. Fluorine-18 was effectively introduced to the SiFA group using an improved isotopic exchange reaction, resuting in a radiochemical yield of 93 % ± 0.5%. This is followed by a brief 15-minute chemistry step to form the radiotracer. Subsequent HPLC purification and solvent removal were performed, yielding a sample ready for animal injection.
Conclusion: We have developed a novel F-18 labeled heparanase inhibitor for oncological PET imaging. Future steps involve in vitro and in vivo analysis in various breast cancer models. The precautions for radiation protection have been outlined, ensuring safety during the labeling process.
The Value of Offering an Introductory Radiopharmacy Course at Canadian Universities
Lexi Gower-Fry | University of AlbertaEnoch ABC Ballroom
The use of radionuclides in nuclear imaging, as well as radiotherapy of cancer and other diseases, is a rapidly growing area in the medical field. Therefore, it is beneficial to offer a course that covers the fundamentals of radiopharmaceutical sciences which includes training and education on the safe-handling and application of radioactive materials. The Fundamentals of Radiopharmaceutical Science course offering is an intensive 2-week course with lectures in the morning and hands-on lab sessions in the afternoon, with a final exam at the end of the course. Radiation safety principles and procedures, as well as nuclear chemistry basics are established before the course progresses into practical work. Subsequently, students learn about radiation measurement techniques and their limitations to gain an understanding of radiation detection, another important aspect of radiation safety. They also learn about classic nuclear chemistry principles including radioactive half-lives, decay modes and differences between radioactive emissions (i.e., alpha, beta, gamma, and Auger electrons). Also, students prepare a radio-fluorinated compound using Silicon-Fluoride Acceptor (SiFA) methodology, the same principle currently used in the clinic to prepare [18F]SiTATE for PET imaging of neuroendocrine tumors. Students also perform a kit-labeling of 99mTc-MDP (Medronate), a skeletal imaging agent, and determine the radiochemical purity. Students also gain practical experience through using standard radiolabeling protocols to coordinate a radiometal, 68Ga, to various chelators. Upon completion of this intensive course, students will have gained valuable experience in an active radiochemistry laboratory where they partake in radiation safety procedures, handling radioactivity, and the synthesis of some established radiopharmaceutical compounds using various methodologies. This foundation and training provide the skills for students to effectively work in a radiopharmacy or radiochemistry-focused research laboratory where they can continue to deepen their knowledge as well as contribute to the fields of nuclear chemistry and medicine.
The Utility of a Medical Cyclotron for Neutron Activation in Research, Teaching and Service.
Dr. John M. Duke | University of AlbertaEnoch ABC Ballroom
Over the past 30 years, Canada has witnessed a significant reduction in the number of its operational research nuclear reactors, dwindling from 10 to 3 due to the decommissioning or permanent shutdown of such facilities. This decline has led to a loss of neutron activation analysis (NAA) and radionuclide production capabilities, as well as diminished research, teaching, training, and outreach opportunities. In contrast, the last 10-15 years have seen a notable surge in the commissioning of cyclotrons, especially medical cyclotrons in the 10-25 MeV energy range, both within Canada and worldwide. For instance, the University of Alberta (UofA) decommissioned its SLOWPOKE reactor in 2017 but established a TR-24 cyclotron in 2013.
The primary purpose of the UofA TR-24 cyclotron is to produce radionuclides for medical use via (p,xn) nuclear reactions. While the neutrons generated in such reactions are typically considered problematic from a radiation safety and, in the longer term, from a facility decommissioning perspective, they can also serve as a potential neutron source for NAA. Using the UofA TR-24 cyclotron, I have been actively exploring, evaluating, and applying the use of these 'by-product' neutrons for the elemental analysis of samples by instrumental NAA (INAA). In this presentation, the utility and limitations of the TR-24 as a neutron source for INAA will be demonstrated through examples of the analysis of archeological, biological, and geological materials. As the number of cyclotrons affiliated with universities and hospitals continue to rise, it is expected that their utilization for NAA, and the production of small quantities of neutron-rich radionuclides for research and teaching purposes, will also likely increase. As a result, this is a topic of potential interest to radiation safety officers at such facilities, especially those who are unfamiliar with NAA.
9:00 am - 10:15 am Session I - Non-Ionizing
Energy-Based Home Use Devices (HUDs) - An Overview
Dr. Godfrey Town | Dermatology Department, Aalborg University HospitalRiver Cree Ballroom 1
In recent years, there has been a proliferation of home-use light-based treatments for various cosmetic and therapeutic purposes.
Review: Since 2003, consumers have embraced HUDs for hair removal and skin rejuvenation available both in physical stores and online. Notable brands in the hair removal category include SpectraGenics Tria, Philips SatinLux, iPulse Smooth Skin Bare, Braun Glow, Remington iLight Pro, and Home Skinovations Silk’n with FDA clearance for over-the-counter sales.
In the consumer anti-aging sector, radiofrequency (RF) and massage HUDs like Tripollar Stop, Trinity NuFACE, and Clarisonic Smart Profile Uplift are prevalent. Laser devices and microdermabrasion also play a growing role. However, HUD non-ablative fractional laser technology has faced challenges, with discomfort and side effects leading to the withdrawal of some major brands.
Thermally mediated, non-ablative fractional laser technology is relatively new, and limited published clinical data exist due to consumer discomfort and side effects. LED arrays, masks, and hand-held applicators for anti-aging treatments, such as Omnilux Contour and Lustre Skin Renew, are gaining popularity.
HUD LED devices extend to male-pattern hair loss treatment, with FDA-cleared products introduced since 2007. Lack of standardization in evaluating these devices has been criticized by some researchers.
Blue light LED devices for acne treatment, like Lustre Pure Light and Quasar MD are available online or recommended by dermatologists. These devices leverage photobiological interactions, particularly with 400-495 nm blue light, to target tissues and produce reactive oxygen species, proposing a bactericidal effect in the treatment of mild to moderate acne vulgaris. Despite their widespread availability, the clinical evaluation of these devices lacks standardized criteria, prompting scrutiny from researchers.
Summary: HUDs have been adopted by consumers for personal use, and by dermatologists and cosmetic doctors for medical and cosmetic purposes as companion products to professional treatments.
Laser /IPL Physics & Safety: Example Online Training
Dr. Godfrey Town | Dermatology Department, Aalborg University HospitalRiver Cree Ballroom 1
Distance learning offers more choices and gives the learner more control to work at their own pace and in their own time. Modern courses are secure and protected by fraud algorithms. Workbooks are provided and training videos (which can be played-back multiple times), can be viewed on a desk-top computer, laptop, tablet, or iPhone/Android before taking a series of multiple-choice competency tests at the end of each lesson. Additional resources include video PPT presentations of the course. This course is approved by the US Board of Laser Safety (BLS) and awarded 1 BLS Certification Maintenance (CM) point (10 hours).
Online learning is particularly suitable for laser and IPL practitioners in private clinics and salons where laser and light-based therapy is now in everyday use.
The topics covered include:
- Light generation & characteristics
- How lasers work and intense light sources work
- Laser Beam and intense light delivery systems
- Working safely: Non-beam hazards
- Beam related hazards
- Safety policies and procedures
- Light interaction with tissue & thermal damage from lasers and intense light sources
- Treatment bandwidths using Lasers and Intense Light Sources
- Treatment related side effects and injury potential
- Relevant national laser & IPL safety legislation, regulations, standards and guidelines.
Summary: This short review of extracts from a current BLS/BMLA independently approved, 10-lesson online course will provide an overview of how safety and applications training for laser users in the independent sector is achieved.
Industrial Laser Incident-Accident Report Forms
Randolph Paura, P. Eng., CLSO, B11 LMSS | Dynamic Laser Solutions, Inc.River Cree Ballroom 1
This paper and presentation discuss the importance of Incident/Accident report forms in the context of a written laser safety program. It emphasizes the need, as identified by ANSI Z136.1 “Safe Use of Lasers”, for addressing actual or suspected laser radiation over-exposures and conducting incident investigations. It is noted that while other agencies or healthcare providers may have the requisite report forms, these may not always be sufficient for effective root cause determination. Where a diligent Laser Safety Officer (LSO) or Environmental Health and Safety (EH&S) committee would conduct simulated laser incidents, an element often overlooked is including the creation of an injury report form in response to the hypothetical event. In cases where such forms are not readily available, this paper provides two suggested report forms (ocular and body), along with a review of an actual suspected injury to demonstrate their utility. Complementary to this is a suggested incident investigation report form for those facilities that do not have an established document for such. This comprehensive approach ensures a robust written laser safety program, facilitating effective incident response and prevention in the workplace. By following the guidance provided, users can ensure they are achieving Light Applied, Safely, Efficiently, and Reliably (a play on the L.A.S.E.R. acronym attributed by this author to Dr. David Sliney, Ph.D.).
Industrial Laser Risk Assessment
Randolph Paura, P. Eng., CLSO, B11 LMSS | Dynamic Laser Solutions, Inc.River Cree Ballroom 1
This paper and presentation address the critical aspect of industrial laser risk assessment, emphasizing its importance at the onset of projects to ensure success in terms of budget, quality, productivity, safety, and compliance. A common misconception that Tables 12 and 13 alone from ANSI Z136.1-2022 “Safe Use of Lasers” are sufficient for a risk assessment speaks to the need for understanding what is meant for a risk assessment and what is required.
Content reviews first the foundational document IEC/ISO Guide 51 “Safety Aspects – Guidelines for their Inclusion in Standards”, which provides practical guidance to drafters of standards to assist them in including safety aspects in standards (ANSI, IEC, ISO, and others). The underlying principles of this Guide can also be used wherever safety aspects require consideration, and as a useful reference for other stakeholders such as designers, manufacturers, service providers, policy-makers and regulators. It then reviews how general equipment recommendations from ISO 12100 or ANSI B11.0 can be incorporated into a format or template specifically designed for industrial laser systems, particularly those used in the manufacturing sector. Additional recommendations are identified from Occupational Safety and Health organizations globally. The aim is to provide a comprehensive approach to risk assessment that goes beyond existing standards, as no one set format or template currently exists, but there is a trend! It underscores the need for a thorough and well-structured risk assessment process to ensure safety and compliance in the use of industrial laser systems. By following the guidance provided, users can ensure they are achieving Light Applied, Safely, Efficiently, and Reliably (a play on the L.A.S.E.R. acronym attributed by this author to Dr. David Sliney, Ph.D.).
10:45 am - 12:00 pm Session J - Dosimetry
Defining Human Receptors for Assessing Safety of Canada’s Deep Geological Repository for Used Nuclear Fuel
Chantal Medri | Nuclear Waste Management OrganizationEnoch ABC Ballroom
The Nuclear Waste Management Organization (NWMO) is responsible for the implementation of Adaptive Phased Management. Under this plan, used nuclear fuel will ultimately be placed within a deep geological repository in a suitable host rock formation. The NWMO is currently in the siting process, working towards site selection at the end of 2024. Two areas remain in the site selection process: the Wabigoon Lake Ojibway Nation-Ignace area in north-western Ontario and the Saugeen Ojibway Nation-South Bruce area in southern Ontario. The NWMO has been developing preliminary post-closure safety analysis to support site selection.
A primary endpoint of a safety analysis is an estimate of potential doses that someone living in the area — a receptor — could receive in various scenarios. To measure repository performance and demonstrate safety, hypothetical doses for the receptors during that facility’s operation (pre-closure) and after closure (post-closure) are compared to set dose benchmarks. The dose received largely depends on a person’s lifestyle, specifically, their relationship with their environment. The NWMO’s site-specific safety analyses consider two different types of lifestyles: a most-exposed group and illustrative local lifestyles. The most-exposed group is a receptor designed to maximise potential dose and demonstrate that present regulatory limits would be met, independent of the potential landscape and social evolutions. The illustrative local lifestyles demonstrate repository’s safety as it relates to local communities’ current and past practices. Illustrative local lifestyles include various Indigenous, town resident, and rural lifestyles. This presentation describes the methodology for defining receptors during the pre-closure and post-closure phases, giving examples of receptors currently selected for safety analyses, the characteristics of each lifestyle, and exposure pathways relevant to each lifestyle.
Best practices for mitigating extremity exposures with PET unidose pigs
Justin Symons | Isologic Innovative RadiopharmaceuticalsEnoch ABC Ballroom
The main objective of a radiation protection program is to protect workers, the public, and the environment by ensuring that radiation doses are kept As Low As Reasonably Achievable (ALARA). In order to meet this objective, licensees may establish action levels that serve as an early warning before regulatory dose limits are reached and serve as a trigger for the investigation and implementation of corrective actions.
This presentation goes over the investigation into extremity exposures following an exceedance of action levels at Isologic Innovative Radiopharmaceuticals. It includes the analysis of the inciting event, a study of the dose rate profiles surrounding unidose pigs, and the resulting corrective actions. Lastly, some best practices that can be used to reduce extremity exposures in radiopharmacies shall be discussed.
Lessons learned from monitoring prolonged fluoroscopic procedures
Dr. Alexander L.C. Kwan | University of Alberta / Alberta Health ServicesEnoch ABC Ballroom
Due to the concern that high radiation exposure to the patient’s skin during prolonged fluoroscopic procedures may result in severe skin reaction that requires additional medical intervention, the AHS Edmonton Zone DI QC team has been assisting with the monitoring of the radiation exposure from fluoroscopic examinations performed in the Edmonton area. This monitoring program was initiated at selected departments back in 2017 but has since been expanded to most fluoroscopic procedures in the last couple of years. The current data suggests that while the number of cases that have reached or exceeded the monitoring threshold dropped at the beginning of the program, it has since leveled off in recent months. In this presentation, an overview of the monitoring program in its current form will be presented, and lessons learned from the program will be explored.
Objectives of this presentation:
1. To provide an overview of the monitoring program.
2. To examine the metric needed for proper monitoring.
3. To review the results of the monitoring program.
4. To explore possible improvements to the program.
10:45 am - 12:00 pm Session K - Commissioning
Lessons Learned from Commissioning a High Activity Gamma Cabinet Irradiator at Ontario Tech University
Dr. Edward Waller | Ontario Tech UniversityRiver Cree Ballroom 1
A cabinet irradiator is a device in which the source of radiation and exposure receptors are contained within a shielded cabinet such that the dose rates external to the cabinet, even under irradiation, are minimal. There are numerous steps that are required for commissioning this type of equipment including:
(i) procurement,
(ii) facilities management,
(iii) security,
(iv) regulatory application and approval,
(v) cabinet manufacture, delivery and install,
(vi) source production, delivery and install, and
(vii) final calibration and site acceptance.
A Hopewell Design Industries model BX3-BR was ordered in late 2019. Unfortunately, the pandemic created a cascade of problems and issues related to the timely delivery and installation of this unit. This talk will discuss the steps taken to acquire this irradiator, the pitfalls encountered along the way, and numerous lessons learned.
How Many RSOs Does it Take to change a Light Bulb? (Part 1 of 2)
Karen Ann Johnson | ElektaRiver Cree Ballroom 1
This will be:
- A simple overview as to what GK is and why we use it,.
- General machine information, including # of sources, and configuration. (With a short video).
- Nordion’ s RSO contribution-RS training for Nordion staff and trucking company staff/drivers (TDG).
- Planning time for a project.
- # of CNSC licenses needed (total 4)-Nordion, AOS, Elekta, facility.
- Game day-source arrival! Facility RSO duties/Elekta RSO duties/Nordion RSO-security/drivers
- Overview of exchange procedure
- Ship out -Facility RSO duties/Elekta RSO duties/Nordion RSO-security/drivers
How Many RSOs Does It Take To Change A Light Bulb? (Part 2 of 2)
Bryan McIntosh | CancerCare ManitobaRiver Cree Ballroom 1
Gamma Knife radiation therapy systems use a large array of precisely collimated Co-60 sources that are to treat brain tumours and perform some neurosurgeries without requiring major brain surgery. These Co-60 sources require replacement every five years to ensure that patients are treated in a reasonable time and to minimize changes in radiobiological effects due to a lower dose rate. Scheduling a source exchange is a complex affair, and can take up to two years to arrange depending on the location of the specialized loading equipment needed to transfer sources with total activities in the hundreds of terabecquerels.
CancerCare Manitoba has had several source exchanges since installing our first Gamma Knife system in 2003, and this presentation will detail what we have learned from these four procedures over the years. On the user side a source exchange involves a great deal of work from petitioning senior management to fund the exchange, coordinating schedules with Elekta and the rigging team for delivery of the new source and removal of the old source to ensure that their staff are available, and ensuring that security will be present in case any security systems are disabled during the exchange. Beyond those physical concerns we will also discuss how we coordinate schedules between Neurology, Oncology, and Physics to ensure that all departments are aware of when the system will be unavailable and when Physics will need to schedule their staff for commissioning. Throughout the source delivery and removal process there is also a great deal of communication required with the CNSC when receiving and shipping sources with high activities, well beyond what most modern radiation therapy departments deal with on a regular basis.
1:30 pm - 2:45 pm Session L - Decommissioning
Dismantling of the Canadian Light Source Linear Accelerator
Darin Street | Canadian Light SourceEnoch ABC Ballroom
The Canadian Light Source (CLS) is Canada’s national synchrotron research facility. CLS uses a 2.9 GeV electron beam to produce high energy photons (synchrotron light) for experimental use on its 22 beamlines. The electrons circulate in a 170m storage ring after being generated by a six section, 250 MeV linear accelerator (linac) that has been in use since the 1980s. The existing linac is due to be replaced in 2024. This presentation will discuss the linac replacement project with focus on the radiological hazards and processes/procedures relating to the dismantling work. The process by which activated material will be surveyed for residual radioactivity and analyzed for potential release from the facility, as well as the plan for commissioning the replacement linac in time for operations to resume in late 2024 will be presented.
An Overview and Pictorial Account of the Decommissioning of the University of Alberta SLOWPOKE-2 Reactor Facility – Parts I and II
Dr. John M. Duke | University of AlbertaEnoch ABC Ballroom
The SLOWPOKE-2 nuclear reactor is a 20 kW (thermal), sealed-container, in-pool type research reactor designed by the Atomic Energy of Canada Ltd. (AECL). It was designed for use in universities, hospitals, and research institutes to serve as a safe, reliable, low-cost source of neutrons for elemental analysis, radionuclide production, and for teaching and training purposes. The original SLOWPOKE design utilised HEU fuel (93% 235U-enrichment). In the early 1980s, AECL redesigned the reactor fuel to use LEU for use when commissioning new SLOWPOKE reactors and, when necessary, for refueling existing SLOWPOKE reactors.
The University of Alberta (UofA) SLOWPOKE-2 reactor (HEU fuelled) was installed in the Dentistry-Pharmacy Building on campus in April 1977 and operated, trouble-free, for over 40 years before being decommissioned in the summer of 2017. Under the Canadian Nuclear Safety Control Act (NSCA) SLOWPOKE is classified as a Class 1A nuclear facility. The decommissioning of Class IA and Class II nuclear facilities share many features in common. However, certain aspects central to decommissioning a Class IA nuclear facility do not apply to Class II facilities.
This presentation consists of two parts:
Part I provides an overview of the regulatory requirements covering the decommissioning of the University of Alberta SLOWPOKE Facility. Emphasis is placed on the unique considerations involved in decommissioning a Class IA nuclear facility, such as reactor defueling, transportation of used HEU fuel, International Safeguards and IAEA involvement.
Part II of the presentation takes a visual approach, presenting a chronological slideshow documenting the physical stages of the decommissioning of the UofA SLOWPOKE-2 Facility. This section provides a detailed journey from the initial preparatory steps to ready the site, through to the ultimate release of the site from CNSC regulatory control.
1:30 pm - 2:45 pm Session M - Emergencies
Joint Emergency Response Exercise involving Ontario Tech University’s Nuclear Irradiation Facility and the Oshawa Fire Services HAZMAT Special Operations Unit: Experiential Insights and Lessons Learned From Planning to Debriefing
Francis Arnaldo | Ontario Tech UniversityRiver Cree Ballroom 1
Emergency planning is important for CNSC Licence Holders who manage facilities where there is a risk of both radiological and non-radiological incidents.
However, despite the best well-designed plans, interoperability training exercises with external response forces are crucial to test the joint readiness capabilities of organizations, which ultimately lead to planning improvements and more positive response outcomes. Furthermore, interoperability training exercises align with regulatory expectations and serve as an opportunity to build stronger relationships by bringing radiation protection organizations and industries together.
In August 2022, Ontario Tech University and Oshawa Fire Services (OFS) had the opportunity to collaborate on a joint training exercise involving the University's Nuclear Irradiation Facility. The goals of the exercise were to:
1. Test the various aspects of the University's Emergency Response Plan and its integration into the external response force of OFS.
2. Familiarize the OFS HAZMAT responders to responding in a nuclear facility setting.
Tabletop, drill, and functional exercises were performed to evaluate the emergency readiness of both organizations. Sharing the experiential insights and the lessons learned from the joint exercise serves to encourage other CNSC licence holders to host interoperability trainings and foster relationship building with groups who have an interest in their nuclear facilities.
The role of a Quantitative Health Objective (QHO) in emergency preparedness and risk management of a severe nuclear accident
Addie Ivanova | Canadian Nuclear Safety CommissionRiver Cree Ballroom 1
Nuclear emergency management is a shared responsibility in Canada. The Canadian Nuclear Safety Commission (CNSC) is responsible for overseeing licensee emergency preparedness and response, maintaining its own emergency preparedness program, as well as supporting provincial and federal partners. Various provisions including safety concepts, goals, objectives, principles, criteria, among other means, are in place to ensure that both the frequency and consequences of severe accidents are mitigated.
As the nuclear regulator, the CNSC can strengthen emergency management by describing how potential short- and long-term impacts of nuclear accidents are included in the regulatory framework, and by considering where appropriate improvements could be realized. In light of this, the CNSC has developed a new safety objective called a Quantitative Health Objective (QHO).
A QHO is a numerical value with an associated dose value that aims to describe the potential health impacts directly related to a nuclear accident with off-site releases. The QHO represents an increase of less than 0.5% in the lifetime probability of developing cancer in Canada, corresponding to approximately 100 mSv of dose (average dose received either acutely or chronically).
The QHO reflects a broader definition of health, which is aligned with international guidance. As such, the QHO value is set at level low enough where radiological health effects (i.e., cancer) are unlikely, but also set high enough to minimize the mental health and psychosocial consequences associated with potential long-term or permanent relocation. The purpose of this presentation will be to provide a holistic picture of CNSC’s existing safety concepts and to introduce the QHO, exploring its usage in facilitating regulatory decision-making, as a risk communication tool, and in informing emergency risk management in the unlikely event of a nuclear emergency. The CNSC is also seeking comments on an upcoming discussion paper and encourages feedback from all interested parties.
TDG new site registration. Do you need to register? What else is coming
Ali Shoushtarian | The Ottawa HospitalRiver Cree Ballroom 1
Public safety depends on Transport Canada (TC) knowing who is importing, offering for transport, handling, or transporting dangerous goods (DG) activities in Canada, what, when, and how, so we can mitigate risks. In response to recommendations from the Office of the Auditor General of Canada, TC is introducing new regulatory Site Registration Requirements through the Client Identification Database (CID) for organizations involved in DG activities to register and share information about their activities. Those who handle, offer for transport, transport or import dangerous goods will be required to register with CID. The CID created a major ripple among Canadian industry when it was first proposed. It should help Transport Canada get a clearer picture of dangerous goods operations across Canada and be a useful tool in improving the TDGR and related safety systems. This presentation will provide an overview on who, how and when do you need to register with CID. We will also highlight upcoming new training requirements and how we established the boundaries between TDG and other regulations such as WHIMS.
Thursday 6 Jun 2024
9:00 am - 10:15 am Session N - Safeguards
Safeguards in Canada
Benjamin Prieur | Canadian Nuclear Safety CommissionEnoch ABC Ballroom
The CNSC is working on improving safeguards reporting on small quantities of nuclear material used Universities, research institutions and industrial locations. The CNSC’s Location Outside Facilities or LOF creation project, which aims to build awareness and commitment to reporting of small quantities, is well underway with new locations being created at Canadian Universities and other institution. Our presentation is intended to provide an introduction to safeguards and to outline nuclear material reporting requirements for institutions having small quantities of nuclear material.
10:45 am - 12:00 pm Session O - Regulatory
Update on the proposed regulatory review of the Class II Nuclear Facility and Prescribed Equipment Regulations (C2NFPER)
Mike Heimann | Canadian Nuclear Safety CommissionEnoch ABC Ballroom
In the autumn of 2022, CNSC briefed stakeholders on the proposed changes to the C2NFPER via public workshops and a discussion paper. This presentation will provide an update on the project, with a focus on what we heard from commenters following the 2022 workshops and discussion paper.
Transport of Radioactive Materials in Canada in 2021 and 2022
Rajesh Garg | Canadian Nuclear Safety CommissionEnoch ABC Ballroom
Canada is one of the world’s leading producers, users and exporters of nuclear fuel cycle products and radioisotopes for industrial, medical and research purposes. Based upon a survey conducted by the IAEA in the early 1980s, Canada was the second largest shipper of radioactive material (RAM) packages of all reporting countries. According to a survey done in 1992 by Canadian Nuclear Safety Commission (CNSC) (then Atomic Energy Control Board), over one million packages of radioactive material were exported, imported or shipped within Canada annually. A new study was recently conducted to update this data and to have a better understanding of the number of RAM shipments that currently take place each year in Canada. This information is required to disseminate to the public, to better regulate the industry and for risk management.
The study involved collecting data on RAM shipments that took place in Canada during 2021 and 2022. The study was broken down into the following six transport sectors: Industrial, Medical, Nuclear fuel cycle, Commercial, Academic and Research and others. Approximately 1500 CNSC licensees were contacted which covered over 2100 CNSC licences. The study involved contacting all types of licensees such as hospitals, universities, portable gauge users, power reactors, and fuel fabricators, as well as freight forwarders and carriers who ship and/or import-export radioactive materials. The survey collected data on:
- All types of CNSC regulated RAM transport packages i.e., excepted packages, Type IP-1, Type IP-2, Type IP-3, Type A, Type B, Type H and fissile material packages.
- Modes of transport used for shipment for these packages
- Number of packages shipped each year
- Activity (TBq) of the RAM contents shipped each year
Estimating risks from modern breast cancer radiotherapy: Implications for clinical decision-making, risk management and radiation protection
Addie Ivanova | Canadian Nuclear Safety CommissionEnoch ABC Ballroom
Breast cancer is the most common cancer among women in Canada. Adjuvant radiotherapy is received by most patients as part of their treatment, as it has been shown to reduce the risk of breast cancer recurrence and mortality. However, randomized trials have shown that breast cancer radiotherapy can also increase the risks of heart disease and second primary lung cancer and oesophageal cancer due to incidental radiation of the heart, lungs, and oesophagus, respectively. The absolute risks depend on radiation doses received by these organs at risk, and on the patients’ pre-existing risk factors.
To estimate these risks, a systematic review and meta-analysis was conducted of doses received by the heart, lungs, or oesophagus from radiotherapy in the United Kingdom for early breast cancer during 2015-2023. These values were then combined with values from dose-response relationships published in epidemiological studies to estimate absolute radiation-induced risks of heart disease, lung cancer, and oesophageal cancer. Risks were estimated considering various factors influential to organ dose received, including breast cancer laterality, clinical targets irradiated, and radiotherapy technique used, as well as pre-existing cardiac risk factors, and smoking status.
To inform clinical decisions, oncologists must weigh the absolute magnitude of the benefits from radiotherapy against the absolute magnitude of its risks for each patient. This research illustrates the importance of three considerations in patient treatment planning: patient selection (e.g., pre-existing cardiac risk factors, smoking status); cancer characteristics (e.g., laterality, localization/clinical targets); and application of modern radiotherapy techniques to limit radiation exposures to organs at risk (e.g., deep inspiration breath hold, proton therapy). The purpose of this presentation will be to present the findings of the systematic review and subsequent risk analysis, followed by an investigation on the implications to clinical decision-making, risk management, and radiation protection.