Sessions and abstracts are subject to change. Abstracts are arranged in the order the presentation is scheduled for the session.
- Tuesday 27 May 2025
- Wednesday 28 May 2025
- Thursday 29 May 2025
Tuesday 27 May 2025
8:00 am - 9:00 am Keynote - Tuesday (Room 2032)
Moderator: Tara Hargreaves
The Rhisotope Project: Using nuclear technology to help reduce the poaching of rhinoceros
James Larkin | Radiation and Health Physics Unit, University of WitwatersrandRoom 2032, 8:00 am - 9:00 am
South Africa is home to 80% of White and Black Rhinoceros populations. Over the past 150 years there has been a decline in these populations of nearly 95%, due in large part to habitat loss and poaching.
Current official rates of poaching sit at 3.2% per annum. If this number reaches 3.5% then there will be a catastrophic collapse in these populations to the point where there will no longer be any meaningful populations left in the wild.
Nuclear technology can offer a new tool to help prevent this happening. What if we were to make the horns of rhinoceros radioactive? Not to poison the end-user but rather to stop them wanting the horns in the first place.
Radiophobia is well known within the radiation protection community, how people generally radically overestimate the harm any dose might cause them. Why not use this fear against those who wish to possess rhinoceros horn to demonstrate their wealth or treat a hangover? Reduce the demand for horn and then the poaching will be reduced. No buyer–no poaching. The presence of the radioactivity also means that it is easier to detect horn that has been taken as it is moved across international borders and passes through installed radiation protection monitors.
In one simple operation the horn becomes less desirable, the risks to the smugglers increases, along with the potential penalties, and it no longer becomes necessary to dehorn these animals to ensure their continued existence.
9:00 am - 10:00 am Session A - Neutron Radiation from Waste (Room 2032)
Moderator: Julianna Liberatore
Neutron radiation from CANDU Refurbishment Waste
Iain McDade | Bruce PowerRoom 2032, 9:00 am - 9:20 am
Following identification of unanticipated neutron radiation from CANDU refurbishment waste, originating from waste associated with retube activities industry wide learning were achieved. Specific to Bruce Power we will look to present a high level overview of what transpired following identification of this hazard. The presentation will review;
- The notification, initial response and some lessons learned from the initial response
- The 3 pronged follow up we had to the event, with some high level detail on each;
- Root cause investigation
- Historic dosimetry assessment
- Neutron production mechanism
- Future/ongoing actions being taken to address the issue
10:30 am - 12:00 pm Anthony J. MacKay Student Paper Contest – Finalist’s Presentations (Room 2032)
Moderator: Alicia Douglas
AI-Driven Enhancement of Low-Count Lung Scintigraphy: Optimizing Radiation Safety and Imaging Efficiency with cGANs
Amir Jabbarpour |Room 2032, 10:30 am - 10:50 am
Enhancing Eye Dose Monitoring in Radiation Protection: Evaluating Hp(0.07) and OSLDs as an Alternative to Hp(3)
Mina Manzoor |Room 2032, 10:50 am - 11:10 am
Lens of Eye Dose Assessment for Nuclear Medicine and PET Technologists
Olivia Sharp |Room 2032, 11:10 am - 11:30 am
1:30 pm - 3:00 pm Session B - Radiation Devices & Detectors (Room 2032)
Moderator: Ryan Cooke
Enhancing Accuracy and Reproducibility in Self-Shielded Box Calibrator
Dania Shahin | McMaster UniversityRoom 2032, 1:30 pm - 1:50 pm
The McMaster University Health Physics Department provides radiation safety & health physics support to a wide range of users, both internal and external to the University. Recently, as part of an effort to enhance our services, we obtained a JL Shepherd & Associates Model 89 self-shielded Cs-137 box calibrator. This is an efficient and conventional approach to radiation instrument calibration, allowing for the calibration of all types of portable radiation detection instruments and probes. However, precise and repeatable positioning of instruments relative to the Cs-137source inside the calibrator itself remains a challenge, as even small variations in position can introduce variations in dose rate measurements. Upon receipt of the box calibrator, several projects were initiated to help ensure calibration accuracy and reproducibility. First, the primary initiative was the development of custom 3D-printed jigs tailored to each radiation instrument, alongside a 3D-printed grid and peg system that enable precise and repeatable spatial positioning. Second, an electronic, automated table positioning system was installed to control the movement of the instrument table inside of the calibrator, replacing the external hand crank and analog position indicator. Finally, an ion chamber appropriate for use as a calibration standard was purchased and is calibrated annually at the Ionizing Radiation Standards Group at the Canadian National Research Lab. This allows verification of the true dose rates within the calibrator, as opposed to exclusively relying on decay curves. Each of these actions have resulted in scalable and cost-effective enhancements to the existing calibrator, while modernizing and improving the device, ensuring McMaster is well equipped to perform quality calibration for our internal users and associated stakeholders.
Pulse Pileup Restoration Techniques for High Rate Gamma Spectroscopy with LaBr3(Ce) Scintillation detectors
Kosta Gianicos | McMaster UniversityRoom 2032, 1:50 pm - 2:10 pm
Gamma spectroscopy is limited by the effects of pulse pileup, which occurs when radiation detection events arrive in rapid succession, causing signal contributions from individual events to overlap. Traditionally, pileup events are discarded by a pileup detection algorithm, as the pileup events distort the pulse height spectrum. This mitigates the degradation in energy resolution but greatly increases the dead time of the detection system at high count rates, which are often encountered in gamma spectra measurements at CANDU maintenance areas and refurbishment workplaces. To address this, we are developing a pulse pileup restoration algorithm that identifies and restores pulse height information from overlapping events for a LaBr3(Ce) scintillator. To optimize the pileup restoration algorithm, a simulation tool was developed to refine and evaluate the restoration algorithm’s performance across various pileup cases. The tool generates synthetic pulse shapes to simulate pulse waveform data at different count rates. The rise and decay times were tuned to match expected LaBr3(Ce) pulse shapes, creating a realistic simulation environment. To complement the simulation studies, pulse waveforms were acquired using a LaBr3(Ce) detector with a commercial high speed digitizer. The setup was configured with and without a preamplifier to provide a diverse dataset for the algorithm development. Analysis of both simulated and experimental data, performed in offline postprocessing, demonstrates that the restoration algorithm effectively restores pulse heights from both pileup and non pileup events. Ongoing work will focus on collecting pulses from high rate sources up to 1 million counts per second, and the implementation of this algorithm on an FPGA forreal time spectroscopy.
LightLink® – Advances in Detector Technology based on Plastic Scintillators for α, β and γ Radiation
Ralph Bose | Mirion TechnologiesRoom 2032, 2:10 pm - 2:30 pm
Plastic scintillators coupled with photomultipliertubes (PMT), have served as reliable large-area detectors for α and β radiation as well as large-volume γ detectors for many years. This contribution summarizes conventional plastic scintillation detector technologies and explores the recent strides made in detector technology through the integration of Single-Photon Avalanche Diodes (SPAD) specifically Silicon Photomultipliers (SiPM). The utilization of SiPMs brings forth a multitude of advantages over traditional detectors, ranging from reduced size and power requirements to increased robustness. This paper provides an overview of the technical aspects of these advancements, elucidating the principles behind the so-called LightLink®, SiPM-based plastic scintillator detectors and their unique features.
The discussion encompasses the practical implications of these advances, exploring their impact on the development of innovative products for detection of ionizing radiation. Applications of LightLink®-based plastic scintillator detectors in diverse fields, including handheld detectors and contamination monitors, will be elucidated, showcasing the versatility and efficacy of this evolving technology. The aim of this contribution is to provide an overview of the recent developments in plastic scintillator detector technology, emphasizing the pivotal role played by LightLink® detectors and offering insights into their potential future applications.
Performance Evaluation of the Radiacode 103 Portable Radiation Detector
Bryan McIntosh | CancerCare ManitobaRoom 2032, 2:30 pm - 2:50 pm
In recent years, there has been wider availability of radiation survey meters from direct sellers on the Internet, combined with a greater interest in surveying objects and areas for radioactive contamination. With this, we have seen a growth in radiation detector ownership among the general public. These survey meters are often limited to Geiger counters which lack the ability to identify isotopes.
The Cypriot company Radiacode has released a series of consumer-focused detectors based on CsI or GAGG scintillators coupled to a small silicon photomultiplier. Radiacode claims to have high energy resolutions for gamma spectroscopy, along with high sensitivity for dose rate measurements. The detector also links to a smartphone application to allow for data analysis in greater detail as well as location tagging of measurements.
This presentation will show the results of our characterization of the mid-range Radiacode 103 through a series of tests including the device sensitivity, accuracy across a range of different dose rates, and its ability to identify different common radioisotopes in comparison to more expensive devices that are aimed at professional use. We will also comment on the performance of the application on a range of smartphones to determine how useful the app-enabled features of the device are. Finally, we will provide a comprehensive evaluation of how suitable these devices are for use in a professional setting, especially considering its accessible price point.
1:30 pm - 3:00 pm Session C - Radioactive Waste (Room 2035/2036)
Moderator: Chris Malcolmson
Radiation Protection Practices and Environmental Stewardship: Insights from the Port Hope Area Initiative
Adetayo Onokosi | Canadian Nuclear LaboratoriesRoom 2035/2036, 1:30 pm - 1:50 pm
The Port Hope Area Initiative (PHAI) is one of Canada’s largest environmental cleanup projects, focused on safely managing historic low-level radioactive waste (LLRW) while prioritizing radiation protection and environmental responsibility. This presentation will explore the key radiation protection (RP) practices used in the project and share insights on how these measures help balance worker safety, regulatory compliance, and environmental stewardship.
PHAI has implemented a comprehensive Radiation Protection Program (RPP) to protect workers, the public, and the surrounding environment while performing a challenging radiological remediation of sites and private residential properties in the municipalities of Port Hope and Clarington. This includes radiation and dose monitoring, Air monitoring and contamination control measures at critical sites like the Port Hope Long-Term Waste Management Facility (PH LTWMF). By following ALARA (As Low As Reasonably Achievable) principles, the project ensures that radiation exposure is minimized while meeting Canadian Nuclear Safety Commission (CNSC) regulations.
Beyond radiation protection, this presentation will highlight how environmental stewardship is embedded in PHAI operations. Careful waste characterization, engineered containment, and adaptive remediation management strategies help minimize environmental impact. Ongoing collaboration with regulators, stakeholders, and the local community has also been key in maintaining transparency and public trust.
The lessons learned from PHAI provide valuable takeaways for other large-scale environmental remediation projects. By integrating strong radiation protection measures with responsible environmental management, the initiative demonstrates how complex cleanup efforts can be handled safely, efficiently, and sustainably.
CMSR CANDU LLW Source Term Characterization
Lionel Fernandes | Laurentis Energy PartnersRoom 2035/2036, 1:50 pm - 2:10 pm
Operational and legacy CANDU generated low-level radioactive waste (LLW) is monitored, inventoried, and segregated at the Clean-Energy Materials Sorting and Recycling (CMSR) laboratory, a joint project between Laurentis Energy Partners (Laurentis) and McMaster University. At the CMSR laboratory, swipes and large area wipes (LAWs) of contaminated LLW material and solid LLW samples were collected for analysis. Considering the LLW volume sample size of the research initiative, this is believed to be the most statistically significant source term characterization performed to date on CANDU generated LLW.
This research initiative has demonstrated the value in sorting and segregation as it relates to LLW volume minimization. This extends to enhanced segregation techniques, waste container space optimization, as well as the identification of non-contaminated materials in CANDU LLW. Industry standard isotopes of interest (eg. Cs-137 and Co-60) were confirmed to be present and in relatively high abundance across all waste streams and LLW vintages sampled, as expected. However, the distribution of other radionuclides associated with LLW was highly variable, and generally at much lower abundances than anticipated (if present at all). Application of dose-rate to radioactivity estimate, though efficient and technically sound, has been shown to generally overestimate and over-characterize CANDU generated LLW.
As expected, the standard for LLW bin radioactivity quantification remains conservative in nature, measuring higher when compared to the individually measured contents within (gamma signature to radioactivity correction). Although a significant number of samples were taken throughout this project, supplemental sample collection is recommended to increase the sample size of LLW vintages that were infrequently or not available throughout the duration of this study.
Advancing plans for the disposal of Canada’s intermediate and high-level waste in deep geological repositories
Chantal Medri | Nuclear Waste Management OrganizationRoom 2035/2036, 2:10 pm - 2:30 pm
The NWMO’s original mandate under the Nuclear Fuel Waste Act was to develop and implement Canada’s plan for the safe, long-term management of Canada’s used nuclear fuel. The site selection process for that repository, launched in 2010, culminated in 2024 with the selection of the Revell site between Ignace and Dryden on the traditional territory of the Wabigoon Lake Ojibway Nation. Next steps will involve a range of activities, including detailed site evaluations, completing required regulatory processes, preparing for construction, and eventually operating the facility.
As Canada’s plan for used nuclear fuel advances, the NWMO has taken on a new endeavour. As a result of the Integrated Strategy for Radioactive Waste (ISRW), which was developed by the NWMO and accepted by the Minister of Natural Resources of Canada in 2023, the NWMO is now responsible for the disposal of Canada’s intermediate-level waste and non-fuel high-level waste be disposed in a deep geological repository. As a first step and building on its experiences, the new task requires the NWMO to develop a process to find a safe and socially acceptable location for the second repository, with informed and willing hosts.
Canada’s technological, environmental and policy landscape is rapidly changing. In this evolving environment, there is potential for extending the life of existing nuclear plants and building new nuclear reactors. If implemented, these developments will result in additional volumes of high-level waste and intermediate-level waste, which will need to be safely managed in a deep geological repository for the long term. The NWMO is considering the future waste from new nuclear development and making long-term plans that include it. This presentation will provide a general update on NWMO’s activities and plans.
3:30 pm - 5:00 pm Session D - Radiation Protection of Patients (Room 2032)
Moderator: Manon Rouleau
UNSCEAR Evaluation on Second Primary Cancer after Radiotherapy
Jing Chen | Health CanadaRoom 2032, 3:30 pm - 3:50 pm
The United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) was established in 1955 by the United Nations General Assembly, with the mandate to evaluate the latest scientific data on levels, effects and risks of exposure to ionizing radiation on humans and the environment; and to provide independent, objective and up-to-date scientific basis for radiation safety. Ionizing radiation has been used to treat cancer for over a century, primarily through external beam technologies, and constitutes approximately 50% of all cancer treatments. Approximately 40% of cured cancer patients received radiotherapy as part of their treatment.
In 2017, the Scientific Committee endorsed a plan to evaluate the incidence of second primary cancer (SPC) following radiotherapy. The aim was to raise awareness in the scientific and medical communities and amongst national authorities of the fact that cancer treatment by radiation, while contributing to the effective treatment of increasing numbers of patients, can involve off-target exposures which may, in some patients, result in SPC several years later.
The Committee’s literature review indicates that between 5% and 15% of cancer survivors may develop a second primary cancer. However, the Committee considered that only a small proportion of these are likely to be attributable to radiotherapy. The Committee’s evaluation has refined the general understanding of how many of these second primary cancers can be attributed to radiotherapy. The absolute numbers depend upon the specific tissues at risk and the radiation doses received during radiotherapy treatment. In view of the significant benefit of radiotherapy, cancer patients should not be dissuaded from undergoing radiotherapy solely based on concerns regarding the possible development of a SPC. Nevertheless, future design and development of radiotherapy should involve dedicated efforts to reduce second primary cancer induction.
A systematic review on thyroid cancer and diseases from radiation exposure in adulthood
Addie Ivanova | Canadian Nuclear Safety CommissionRoom 2032, 3:50 pm - 4:10 pm
The thyroid regulates many vital functions in the body, including growth, metabolism, reproduction, heart rate, blood pressure and body temperature. The thyroid gland is vulnerable to ionizing radiation, with cancer being the primary health effect of concern following low to moderate exposures. A linear dose-response relationship between childhood radiation exposure and thyroid cancer has been well documented, and evidence indicates that exposure is also associated with non-malignant thyroid diseases, such as hypothyroidism. However, the literature focused on the risk of thyroid cancer or non-malignant diseases following adulthood exposure is more variable and could be better delineated.
The relationship between ionizing radiation and thyroid diseases is an important regulatory issue. During radiological or nuclear emergencies, public or occupational exposures could result in uptake of radioactive iodine to the thyroid. As such, the International Commission on Radiological Protection has recommended reference levels for emergencies, while Health Canada has established generic criteria that include guidance on when to take protective actions, such as stable iodine thyroid blocking. Additionally, accidental spills (in a laboratory setting, for example) could result in occupational doses with radioactive iodine uptake. While these occurrences are uncommon, there remains a gap in understanding the risks in these settings specifically for an adult population, that could have important regulatory implications in emergency management. For instance, some countries do not distribute potassium iodide to older populations, while others have chosen to do so for risk communication purposes.
Given the uncertainties that remain, the CNSC has undertaken a systematic review to improve the level of understanding of the risk of thyroid exposure to ionizing radiation in adulthood, that can in turn inform the radiation protection framework. The purpose of this presentation will be to outline the review process, progress made, challenges faced, and results to date.
The Trials and Tribulations of Implementing Safe Radiopharmaceutical Therapy at BC Cancer - Vancouver
Peter Petric | BC Cancer – Vancouver
Radiopharmaceutical therapies (RPT) using Lutetium-177 and Actinium-225 are promising treatments whose use is rapidly expanding around the world. Clinical trials using these RPT radioisotopes to treat prostate and neuroendocrine disease have shown impressive patient response.
In early 2019, BC Cancer-Vancouver administered the first Lu-177 patient treatment in British Columbia. Accomplishing this milestone required a substantial amount of preparation and administrative work including: identifying rooms suitable for RPT preparation, administration, and waste storage; identifying and training staff to carry out RPT activities; identifying and purchasing required radiation safety equipment; preparing standard-operating-procedures (SOPs) and patient and caregiver radiation safety precautions; and applying for CNSC licencing for RPT.
Initial roll-out of the RPT program at BC Cancer–Vancouver presented several minor challenges with respect to radiation safety. These included dealing with small, contained, contamination incidents, the need to optimize RPT waste decay storage and several instances of adapting to individual patient travel and living circumstances that necessitated updating patient and caregiver precautions. Expansion of RPT patient numbers coincided with a handful of more serious radiation safety incidents including substantial contaminations in the treatment rooms leading to room shut-down and eventual room renovations, building sewer main blockage that required temporary shut-down of an exterior area, and a near-miss disposal of a patient RPT dose in the building garbage.
This talk will review the setup of the current BC Cancer–Vancouver RPT program including the radiation safety lessons learned along the way and how these lessons are being applied to expansion of the BC Cancer RPT program across British Columbia.
Optimizing Radiation Protection in ¹⁷⁷Lu-Based Radiopharmaceutical Therapy: The Need for Standardized Internal Dosimetry
Pardis Haghi | OntarioTech UniversityRoom 2032, 4:10 pm - 4:30 pm
Radiopharmaceutical therapy (RPT) with Lutetium-177 (¹⁷⁷Lu) has revolutionized targeted cancer treatment, offering theranostic capabilities that integrate diagnosis and therapy. However, ensuring radiation safety for patients, healthcare workers, and the environment remains a critical challenge. This study examines radiation protection measures and regulatory requirements for ¹⁷⁷Lu-based RPT in Canada, focusing on Canadian Nuclear Safety Commission (CNSC) licensing, compliance protocols, and quality assurance measures to mitigate radiation exposure risks.
A key component of patient safety in nuclear medicine is internal dosimetry, which plays a crucial role in optimizing treatment efficacy while minimizing radiation exposure to healthy tissues. Despite advancements in nuclear medicine, many treatment protocols continue to rely on fixed-dose approaches, leading to suboptimal therapeutic outcomes. This research explores the challenges and incentives of patient-specific dosimetry, including barriers such as cost, lack of standardized protocols, and dose-response uncertainties. Additionally, it evaluates different dose prescription algorithms, comparing fixed dosing, Maximum Tolerated Absorbed Dose (MTAD), and Prescribed Tumor-Absorbed Dose (PTAD) approaches in clinical applications.
The findings underscore the urgent need for standardized internal dose assessment software platforms to enhance personalized treatment planning and radiation protection strategies. The absence of a universal dosimetry framework has led to inconsistencies in dose calculations, impacting the accuracy of therapeutic radiation delivery. Future advancements should focus on developing a limited number of commercially available dosimetry platforms that are accessible across nuclear medicine departments. These platforms must ensure consistent, reproducible results for target organ absorbed doses, total body effective doses, and dose volume histograms. Furthermore, adopting a standardized data format (e.g., DICOM) will improve interoperability, enabling seamless data exchange across clinics and institutions. Implementing these improvements will enhance patient safety, maximize therapeutic benefits, and minimize radiation-related risks in the evolving field of radiopharmaceutical therapy.
Optimizing Knee X-ray Imaging: Balancing Radiation Dose and Image Quality
Nada Alomairy | Jazan UniversityRoom 2032, 4:30 pm - 4:50 pm
Background: Radiation plays a significant contributor to medical diagnostics. However, the questions about risks of repeated radiation highlight the need for the optimization of radiation doses, especially in musculoskeletal imaging like knee X-rays, to ensure safety without compromising diagnostic quality.
Objectives: The study aimed to optimize knee X-ray imaging protocols, balancing of radiation dose and image quality. Specifically, the most effective exposure factors that provide minimum radiation exposure with maximum diagnostic accuracy. This study also compared different protocols to identify the safest and most accurate technique in clinical practice.
Materials and Methods: This study was conducted at a university hospital from December 2024 to January 2025, using a Portable X-ray unit knee imaging. Three exposure protocols were used: (1) standard parameters (77.50 kV, 8 mAs), (2) the 10kV rule (73 kV, 50% reduction in mAs), and (3) a modified 10 kV rule (73 kV, 75% reduction in mAs).The Alderson Rando knee phantom was imaged in AP and LAT positions, with the radiation doses measured using OSL dosimeters. Results were analyzed using descriptive statistics, paired t-tests, and ANOVA.
Results: The standard protocol delivered the highest dose, significantly higher (p < 0.05) than the other protocols, with an average dose of 0.64 ±0.03 mGy in AP and 0.73 ± 0.07 mGy in LAT. The10 kV and modified 10 kV rules reduced doses by23.4% to 39.1% in AP and 22.2% to 42.5% in LAT. Image quality decreased with higher mAs reductions but remained clinically acceptable.
Conclusion: Optimization exposure parameters, especially using the 10 kV rule and its modification, reduced radiation doses while maintaining diagnostic accuracy. This highlights the need for a refinement of the X-ray protocols in order to minimize patient doses without compromising diagnostic value. Additional studies on the applicability of optimized protocols across different populations and imaging systems are warranted.
3:30 pm - 5:00 pm Session E - Decommissioning (Room 2035/2036)
Moderator: Ye Eun Kim
Decommissioning of Complex Nuclear Sites
Mike Grey | KinetricsRoom 2035/2036, 3:30 pm - 3:50 pm
A complex nuclear site is one that houses several nuclear facilities on a single site. Often these include different types of facilities (e.g. reactors, heavy water processing & storage and waste management) in several lifecycle stages (construction, operations, refurbishment and decommissioning). Interferences between them are possible and decommissioning often suffers from a lower priority. CSA standard N294 (Decommissioning of nuclear facilities) provides guidance on decommissioning of complex sites and REGDOC 2.11.2 (Decommissioning) requires that an overarching decommissioning plan be prepared to consider possible interferences between facilities that might arise during decommissioning. Unfortunately, the latest revision of N294 will provide little additional guidance on writing an overarching, or comprehensive, decommissioning plan. This presentation will review international experience in writing overarching decommissioning plans for complex sites and the existing domestic experience. It will also review possible guidance that might be included in the 2030 revision of CSA N294.
Decommissioning Techniques - 200 Series, Chalk River Labs
Montana Stein | Canadian Nuclear LaboratoriesRoom 2035/2036, 3:50 pm - 4:10 pm
Canadian Nuclear Laboratories’ (CNL) Chalk River Campus is home to a cluster of connected facilities, commonly known as the 200 series buildings, comprised of B200A/B, B204, and B220. These facilities are currently undergoing active decommissioning by the Facilities Decommissioning group. The 200 series buildings housed and processed spent fuel rods from the National Research Experimental (NRX) reactor.
Many innovations in decommissioning techniques have been used within the 200 series over the years, this presentation looks to focus on methods used in 2024. The majority of the work within the 200 series over the course of the year was in B204.
The B204 fuel rod bays are connected to NRX via a fuel rod trench. The bays in the facility were required to be shielded and therefore significant planning and coordination between many groups was developed in order to achieve this work within the required time scale. Due to the significant dose rates involved, ALARA measures for this work concentrated on remote tooling, CCTV, and drone scans all while considering methods to reduce the time team members needed to spend in elevated fields.
Characterization of neutron fields around refurbishment waste at Bruce Power and OPG using neutron spectrometry and Monte Carlo modelling
Jovica Atanackovic | Ontario Power Generation and McMaster UniversityRoom 2035/2036, 4:10 pm - 4:30 pm
Using neutron spectrometry, we characterized the neutron energy spectra coming from irradiated components of a refurbished CANDU reactor. The measured neutron energy spectra were from refurbishment waste from calandria tubes (CTs) and pressure tubes (PTs). The measurements were conducted using a Nested Neutron Spectrometer (NNS), manufactured by Canadian company DETEC Inc. They were performed at Bruce Power, around a single isolated waste container, filled with approximately 2000 kg of PTs or CTs that were volume reduced into small coupons and stored in retube waste containers (RWCs), made almost entirely of high carbon steel. Using Monte Carlo modelling and the results from this spectroscopy campaign it was concluded that neutron fields coming from the waste containers are due to presence of Cf-252 spontaneous fission neutrons. It was found that the origin of Cf-252 in CTs and PTs is a trace amount of U-238 in Zr alloys of CTs and PTs. This U-238 is converted into Cf-252 after over thirty years of continuous neutron bombardment in high neutron fluence rate environment of a CANDU reactor core. In fact, the presence of Cf-252 in the refurbishment waste is a result of a multiple neutron captures and several beta decays. Another set of spectroscopy measurements, after a period of six months, measured the decay rate of the neutron source term within the RWCs and confirmed Cf-252 half life of 2.65 years. This work is a first of a kind, identifying a presence of spontaneous fission neutrons in CANDU reactor waste material. These findings have significant impact on radiation protection, dosimetry, waste management and radiation protection regulations.
Wednesday 28 May 2025
8:00 am - 9:00 am Keynote - Wednesday (Room 2032)
Moderator: Josip Zic
Bruce Power Radiation Protection – Our role in site operations and the future of Bruce Power
Zach Brajuha | Bruce PowerRoom 2032, 8:00 am - 9:00 am
9:00 am - 10:00 am Session F - Emerging Technology (Room 2032)
Moderator: Bryan McIntosh
Shaping the Future of Health Physics: Innovations, Challenges, and Opportunities in Radiological Protection
Lekhnath Ghimire | Ontario Tech UniversityRoom 2032, 9:00 am - 9:20 am
This research provides an in-depth exploration of the future trajectory of health physics, considering both external and internal factors shaping its development. Externally, the presentation examines the challenges and priorities associated with measuring low-dose radiation (10–100 mSv) and highlights the transformative potential of biomarkers in understanding radiation susceptibility from low-dose exposures. Emerging technologies, such as plastic scintillators with triple discrimination capabilities and plastic scintillation microsphere (PSm) sensors, are discussed for their ability to estimate alpha and beta-emitting radionuclides in environmental samples. Additionally, remote detection systems, including drones, robot dogs, and quantum sensors, are explored for their heightened sensitivity and precision in radiation detection. A key focus is the integration of artificial intelligence (AI) and data analytics, which have the potential to redefine health physics by reducing radiation exposure risks. The presentation also covers innovations in radiation shielding materials, advances in virtual reality applications, and preparation for radiological protection in conflict zones. Furthermore, it addresses the evolving landscape of decommissioning health physics and the importance of understanding the broader contextual factors, such as regulatory shifts ,geopolitics, and socioeconomic influences, that will shape the future of the field. Internally, the presentation explores the transformation of health physics education and training, emphasizing the expansion of educational opportunities, innovative delivery methods, and targeted student outreach strategies. It also focuses on career pathways in the dynamic job market and the development of new risk communication strategies. Finally, the presentation underscores the significance of health physics summer schools and consortia in fostering interdisciplinary collaboration and advancing education. These multifaceted insights will guide the field into a new era of technological and educational progress, influencing both practice and policy for years to come. Overall, this presentation aims to stimulate dialogue and collaboration, defining a path for health physics' unpredictable yet promising future.
Canadian and International Requirements for Security Scanners using Ionizing Radiation
Laura Boksman | Radiation Safety Institute of CanadaRoom 2032, 9:20 am - 9:40 am
Technology is rapidly outpacing the creation of regulations in the area of security scanners utilizing ionizing radiation. There are various types of scanners that utilize ionizing radiation, including systems designed specifically for screening of humans and systems designed for screening of vehicles or cargo containers which may contain humans (the driver or a stowaway).
There are two main security imaging technologies that use ionizing radiation, including backscatter and transmission scanners. Backscatter technology is used mainly to image objects hidden under clothing while transmission systems are also used to image objects under clothing but also those that have been ingested, hidden in body cavities, or implanted under the skin. Generally, radiation dose to scanned individuals is much lower from a back scatter system than from a transmission system.
Security scanners that use ionizing radiation are already in Canada, and their use is increasing. However, Canada has limited to no regulations for such technology. There are no Canadian regulations with requirements for the design, construction and functioning of such equipment, to ensure protection of individuals. Additionally, there are no regulations for the safe use of such equipment, for the protection of the persons being scanned. Legislation for the protection of workers who use or are near X-ray systems exist in some provinces and territories, but are not specific for this type of system and only cover workers, not the scanned population.
This presentation will discuss various types of systems and how they are categorized, based on international standards, due to the lack of Canadian regulations. For transmission scanners, which result in more dose to the scanned persons, the design and functional recommendations from the international standards will be reviewed.
Radiation Protection Programs for Security Scanners using Ionizing Radiation
Laura Boksman | Radiation Safety Institute of CanadaRoom 2032, 9:40 am - 10:00 am
Technology is rapidly outpacing the creation of regulations in the area of security scanners utilizing ionizing radiation. The previous presentation discussed various types of such scanners, including systems designed specifically for screening of humans and systems designed for screening of vehicles or cargo containers which may contain humans (the driver or a stowaway).
In this presentation we will explore the practical implementation of security scanners that use ionizing radiation and the aspects that should be included in a radiation protection program for the protection of the scanned persons as well as protection of the workers. This will be based on international standards due to the lack of current Canadian regulations. The classification of scanner types was discussed in the previous presentation and will not be repeated here.
We will discuss the radiation protection principles of justification, optimization, and dose limits and how these would be applied to the planned exposure scenario of security screening of humans. Strategies for dose reduction will be considered, as well as administrative limits for dose to scanned persons and regulatory or recommended limitations for dose to workers. The need for policies and procedures will be examined, and we will discuss what should be included in such documents. Personnel requirements, including the need for training of system operators, nearby workers, and X-ray Safety Officers will be discussed, along with recommendations for educational materials for scanned persons.
9:00 am - 10:00 am Session G - Non-Reactor Waste (Room 2035/2036)
Moderator: Laila Omar-Nazir
Implementation of an economical waste monitor for quantification of gamma emitting radionuclides in university research waste streams
Matt Hutcheson | University of SaskatchewanRoom 2035/2036, 9:00 am - 9:20 am
In recent years, the nature of the radioactive waste at the University of Saskatchewan (USask) has changed to include more novel accelerator produced isotopes, longer lived contaminants, and isotopes with very restrictive disposal limits such as Ac-227. Existing methods of conservative estimation and generous decay times had become impractical, as overestimating the concentrations could lead to storing large volumes of waste for decades. A single detector waste monitor, MHOS 9700 HWM-S (ELSE Nuclear), was purchased to streamline the quantification and final disposal of gamma emitter waste streams. This presentation gives an overview of the USask experience implementing an updated waste management system to take full advantage of the available technology.
Lessons Learned in Change Management for CLS's Medical Isotope Production Facility
Darin Street | Canadian Light SourceRoom 2035/2036, 9:20 am - 9:40 am
The Canadian Light Source (CLS) holds a CNSC Class II Licence for a 40kW, 35MeV linear accelerator used to produce medical isotopes. CLS maintains the radiation protection program associated with the licence and oversees operation of the facility by a contractor. This presentation will discuss the change management, safety challenges and recent events relating to radiation protection that have occurred as the facility has transitioned from one contractor previously operating the accelerator to another contractor currently operating it.
Quantifying Isotope Activities Using a Gamma Spectrometer Survey Meter
Brian Bewer | Canadian Light SourceRoom 2035/2036, 9:40 am - 10:00 am
During the operation of high energy accelerators, activated materials are commonly created. The activity and isotopes present in these materials must be characterised for their clearance and release from the facility, or to ascertain their duration of stay in a radiological storage area. An activity estimate method using a gamma spectrum collecting survey meter is presented. Using several reference radioactive sources the detection efficiency and dead time of the survey meter were characterised. This information combined with the physical properties of the survey meter, the counting time and the properties of the measured photon energy emissions can be used to calculate an accurate activity estimate for localised activation on accelerator components, or loose contamination on isolated waste materials.
10:30 am - 12:00 pm Session H - Emergency Response (Room 2032)
Moderator: Jeff Dovyak
A Series of Unfortunate Events – Decontructing the Requirements for Reporting on Norm Related Incidents
Tanya Vlaskalin | Toronto Metropolitan UniversityRoom 2032, 10:30 am - 10:50 am
Norm related materials and events associated with these materials have ‘normally’ fostered confusion on their oversight within the NSC Act and Regs. In light of the resurgence of interest for safeguards reporting, this presentation will review an incident that highlighted the need to understand the use of dosimetry for personnel exposure to radiation emitting devices and how reporting is not always black and white when dealing with the nuclear regulator and the dosimetry service provider. This presentation will highlight the reporting requirements and lessons learned for x-ray users who also have access to norm and ‘non regulated’ materials in an academic setting.
Yeast-Based Impedance Biodosimetry for Retrospective Assessment of Radiation Exposures
Amna Hassan | Canadian Nuclear LaboratoriesRoom 2032, 10:50 am - 11:10 am
Saccharomyces cerevisiae yeast cells were investigated as fortuitous dosimeters for retrospective assessments of exposures following large-scale radiological or nuclear accidents. The radiation response of yeast cells was examined by using cellular metabolic activity and electrical impedance of the solution to evaluate dose. Active laboratory-grade dry yeast cells were used as the biological material as these samples are simple to handle and have a long shelf-life. A novel dosimeter design was developed with precise fabrication and measurement procedures to ensure reproducibility of samples was achievable. To assess the feasibility of impedance biodosimetry, a dose-response curve was developed by irradiating S. cerevisiae cells from 0.5 Gy to 8 Gy using a ¹³⁷Cs gamma source. The dose-response curve showed a linear relationship of dose with changes in the impedance response. Additionally, in a separate experiment, the detection limit of this technique was determined to be 300 mGy. Fading of the impedance signal was also investigated, where no noticeable decrease in the response over a 7-month period was observed. Finally, the impedance and radiation response of Fleischmann's® yeast was examined, and it was found that commercially available yeast exhibit a similar response to laboratory-grade yeast. S. cerevisiae cells were determined to be suitable and convenient samples to use for retrospective dosimetry applications since they are widely available and require no additional processing. In the event of a radiological accident, yeast-based impedance biodosimetry could be used as an alternative technique to evaluate initial dose estimates to exposed areas.
Partnership in Preparation: Strengthening Radiological Response Capabilities Through Collaboration with Community Partners
Chris Malcolmson | McMaster UniversityRoom 2032, 11:10 am - 11:30 am
Emergency Preparedness and planning for radiological emergencies can be challenging. This session will introduce tools and strategies for mitigating the impact of these obstacles. As part of these strategies, insight into how community partnerships can strengthen response capabilities and overcome these challenges will be proposed. The mutually beneficial relationships developed between the City of Hamilton First Response Teams and the McMaster University Health Physics Department Radiation Safety Specialists will be presented as a model for bolstering overall response to emergencies involving nuclear material, radiation, contamination, or other radiological emergencies. Finally, there will be a breakdown of two case studies involving multi-team, co-operative response to simulated large-scale nuclear emergencies. Planning for radiological emergencies is hard enough, why do it alone?!
10:30 am - 12:00 pm Session I - General Radiation Protection (Room 2035/2036)
Moderator: Jennifer Clarke
From Medical Physics to Health Physics: Navigating a Career Shift Across Borders
Clauzi Guerini | TRIUMFRoom 2035/2036, 10:30 am - 10:50 am
Transitioning careers across countries is never easy, especially in a specialized field like radiation protection. In this presentation, I will share my personal journey from working as a Radiation Safety Officer (RSO) in Brazil’s healthcare sector to establishing a career in health physics in Canada.
Arriving in Canada, I faced challenges common to many internationally trained professionals—navigating a new job market, understanding different regulatory frameworks, and proving my expertise in a competitive field. I will discuss the strategies I used to break into the Canadian radiation protection industry, including networking, professional development, and leveraging my previous experience to secure my first role.
Starting as a Radiation Protection Surveyor, I quickly adapted to the operational aspects of radiation safety in a new setting. My background in dosimetry and regulatory compliance allowed me to transition into a Dosimetry Specialist role, where I contributed to radiation monitoring programs and safety improvements. With continued dedication and growth, I eventually advanced to my current position as Operational Radiation Safety Group Lead at an accelerator laboratory.
This talk aims to inspire and provide insights for professionals looking to transition into the field, whether they are newcomers to Canada or seeking a career shift. I will highlight key lessons learned, the importance of adaptability, and how international experience can be an asset in a new professional environment.
Radiation Safety Improvements for a New Self-Contained High Dose Rate Research Irradiator
Chris Vanderpool | Hopewell Designs, Inc.Room 2035/2036, 10:50 am - 11:10 am
Current best practices for industrial applications of radiation technology needing high dose rates embrace utilizing self-contained research irradiators for application specific irradiation. Although a stable mainstay of radiation testing campaigns for many decades, the Gammacell 220 has inherent external radiation leakage that contributes to worker dose. The model GR420 by Hopewell Designs is intended to be a market replacement for the GC220 with improvements in radiation safety. The radiation shielding and safety mechanisms are designed to limit radiation levels to 20 uSv/hr at 30cm with the systems shielded enclosure for all modes of use (loading/unloading, irradiation, and transition). This talk includes a high-level overview of the GR420 irradiator design, dose rates around the device in all modes of operation, and notable improvements in safety and operation over the legacy GC220.
Benchmarked survey of (and solutions for) workplace laser safety regulations in Canada
Randolph Paura, P. Eng., CLSO, B11 LMSS | Dynamic Laser Solutions Inc.Room 2025/2036, 11:10 am - 11:50 am
The proliferation of laser technology has significantly lowered the barrier to entry, leading to widespread adoption across various industries. However, this rapid integration has outpaced the understanding of the inherent hazards associated with lasers, resulting in misconceptions and gaps in knowledge regarding compliant and safe workplace practices.
Firstly, this paper aims to identify and discuss international principles and guidance for workplace laser safety, which is premised upon the acquisition of compliant equipment thereby enabling safe use. It identifies baseline international principles for workplace laser safety exposure limits set by the ICNIRP (International Commission on Non-Ionizing Radiation Protection) and control measures proposed by the ILO (International Labour Organization). Equipment build and user safety consensus standards will be reviewed to ensure an understanding of global best practices.
Following this universal foundation, is a survey of workplace laser safety regulations in Canada, including Federal, Provincial, and Territorial provisions. An explanation of what is intended by the General Duty and Due Diligence clauses of Occupational Health and Safety regulations is provided and ill-informed misconceptions about such are addressed. This section delves into the specific regulatory frameworks and safety protocols mandated across different jurisdictions within Canada. Apparent gaps should not be misconstrued as allowing for lax requirements in the workplace as best practices are referenced by OH&S and judicial professionals. Lastly, the paper will propose an informational OH&S webpage as a baseline resource for workplace laser safety premised upon international OH&S best practices. This webpage aims to serve as a foundational tool, offering detailed guidance and resources to ensure compliant and safe laser operations within workplaces for all stakeholders.
1:30 pm - 3:00 pm Session J - Future of Radiation Protection (Room 2032)
Moderator: Jeff Fleming
Considerations Regarding Operational Dose Quantities Proposed by ICRU 95
Josip Zic | McMaster UniversityRoom 2032, 1:30 pm - 1:50 pm
In 2021, the ICRP initiated the revision of the general recommendations of the system of Radiation Protection, and part of it will focus on dose quantities. The recently published ICRP Publication 147 and ICRU Report 95 have described the extent of the proposed modifications and paved the way for the strategy to be adopted. These revisions would seek to simplify, improve the accuracy and extend the field of use of dose quantities. Although here is a notable improvement in the estimation of the protection quantities and the usefulness of such changes for the medical and research sector, the benefits of the proposed new system seem limited for the nuclear industry and industries involving naturally occurring radioactive materials (NORM). Furthermore, the complexity associated with changing a long standing and robust system seem unjustified bearing in mind the likely cost. All organizations implementing nuclear technologies should be evaluating the impact of these proposed changes as they apply to implementing the irradiation safety programs and communicating radiological risk to workers and the public.
Reevaluating the Linear No-Threshold Model: The Role of Organ-on-Chip Technology
Charles Wilson | University of Alabama at BirminghamRoom 2032, 1:50 pm - 2:10 pm
The linear no-threshold (LNT) model, the long-standing basis for radiation regulation, faces persistent and significant scientific debate regarding its accuracy at low doses (below 10cSv/y). Recent studies offer no conclusive resolution, with results distributed across LNT, non-linear risk models, and hermetic models. Additionally, research is expanding into the potential role of radiation in non-cancerous diseases such as heart disease, Parkinson’s disease, and diabetes. While LNT's use leads to public anxiety and costly remediation efforts, it remains the regulatory standard due to insufficient evidence for alternatives. To address this, further investigation utilizing advanced techniques (e.g., machine learning, Edisonian data analysis) compounded with a laboratory model that more accurately reproduces in-vivo results are being explored. Organ-on-Chip (OOC) technology significantly improves the ability to reproduce in-vitro conditions for multiple organs of interest and their various interoperations in the study of pharmacokinetics and radiobiology. This presentation will provide an overview of current LNT studies and OOCs with a focus on the advantages this technology facilitates in low dose and low dose rate radiation studies
Addressing the Decline of Academic Health Physics Programs: Challenges, Solutions, and Opportunities for the Future
Emily Caffrey | University of Alabama at BirminghamRoom 2032, 2:10 pm - 2:30 pm
This presentation will highlight the status of academic Health Physics programs in North America, introduce potential solutions, and share some opportunities for practicing experts to efficiently maximize their impact on the next generation. The need for Health Physicists continues to grow with new reactor designs, the increase in novel radiopharmaceuticals, the need to manage environmental exposure scenarios, and the looming potential to harness fusion energy. The ability to research the safety issues of tomorrow, solve yesterday’s problems, and teach the next generation in the field of Health Physics is vital.
The trend of closing academic programs and lack of people coming into the industry was foreshadowed in the National Council on Radiation Protection and Measurements (NCRP) published Statement 12 from 2015, “Where are the Radiation Professionals?” and reiterated recently in Physics Today [1], the Bulletin of the Atomic Scientists [2], and the Journal of Applied Clinical Medical Physics [3]. In April 2023, the International Commission on Radiological Protection (ICRP) published a paper that stemmed from their symposium in Vancouver in 2022. The paper stated that the ICRP is“...concerned that a shortage of investment in training, education, research, and infrastructure seen in many sectors and countries may compromise society’s ability to properly manage radiation risks, leading to unjustified exposure to or unwarranted fear of radiation, impacting the physical, mental, and social well-being of our peoples.” [4] The paper called for worldwide action to strengthen expertise in radiological protection.
The United States is down to seven active graduate programs, Canada two, and Mexico none. The lack of experts entering the field is also evidenced by the number of experts willing and able to teach. McMaster University and the University of Alabama at Birmingham have teamed together to share skills and facilities to optimize the transfer of information to the next generation.
[1] https://pubs.aip.org/physicstoday/article/76/10/18/2912730/Alarm-sounded-over-declining-US-radiation
[2] https://thebulletin.org/2023/07/nuclear-safety-staffing-in-the-united-states-a-crisis-with-no-easy-fix/
[3] https://www.ncbi.nlm.nih.gov/pmc/articles/PMC9880967/
[4] https://link.springer.com/article/10.1007/s00411-023-01024-5
1:30 pm - 3:00 pm Session K - Environmental Monitoring (Room 2035/2036)
Moderator: Lionel Fernandes
The prospective for radiological sustainability through the reuse of NORM residues in construction materials
Esther Osei Akuo-ko
A comprehensive radiological investigation of soils and water resources in artisanal gold mining areas in Ghana: Mining activities vs radiological risks
Esther Osei Akuo-ko
Environmental Dosimetry and its Role in Radiological Monitoring from Coast to Coast to Coast
Nick Maddox | Health Canada/National Dosimetry ServiceRoom 2035/2036, 2:10 pm - 2:30 pm
Health Canada’s National Dosimetry Service Division (NDS), runs a small environmental dosimetry program in support of the HC National Monitoring Section’s (NMS) efforts to characterize the gamma component of background rates across Canada. Passive environmental dosimeters (Landauer InLight design), are distributed to NMS stations in every province and territory on a quarterly basis, which are then deployed and retrieved by NMS partners. A specialized algorithm processes the optically stimulated luminescence (OSL) elements of the dosimeter to calculate the ambient equivalent dose equivalent, H*(10). These data are then sent to the NMS, which publishes the results to the Canadian Radiological Monitoring Network – Environmental Dosimetry website (https://open.canada.ca/data/en/dataset/67bedee8-beb0-4b3a-a1c6-24a4cda08afe). Emphasis would be placed on the rationale for passive environmental dosimetry, and dosimeter design.
Thursday 29 May 2025
9:00 am - 10:00 am Keynote - Thursday (Room 2032)
Moderator: Corie Houldsworth
Creating the Future Together: Canada's Plan for Used Nuclear Fuel
Kelly Liberda | Nuclear Waste Management OrganizationRoom 2032, 9:00 am - 10:00 am
10:30 am - 12:00 pm Session L - Regulatory (Room 2032)
Moderator: Ali Shoushtarian
The Future is Now: Coming improvements in the CNSC licensing process and streamlining your licence
Diana Moscu | Canadian Nuclear Safety CommissionRoom 2032, 10:30 am - 10:50 am
The Canadian Nuclear Safety Commission (CNSC)is striving to modernize the way it works. Timely updates of regulatory documents ensure that the regulatory framework aligns with international requirements, includes operational experience and the comments of licensees. Work is underway to support the innovation of new technologies, from small modular reactors and proton therapy to those developments being made at universities and clinics. The CNSC is building processes that can address licensing of devices, projects, and experiments, from benchtop to commercialization.
Another CNSC modernization initiative relates to improvements in the digital tools used by staff in day-to-day operations. This may mean simpler licence applications, improved sharing of digital materials and may end the reliance on mailing physical documents. Through this process there are many opportunities to streamline CNSC licenses, making it easier to manage and improve daily operations at licensed facilities. Working together, the CNSC and licensees can ensure that we all learn and adapt to the challenges of the future while protecting the environment and ensuring nuclear safety and security for all people in Canada.
This presentation will address the modernization undertaken by the CNSC and its potential impact on licensees.
Radiation Protection Performance in Nuclear Medicine: Trends and Guidance
Lindsay Pozihun | Canadian Nuclear Safety CommissionRoom 2032, 10:50 am - 11:10 am
Every year, the CNSC tracks performance data for our licensees to identify trends and inform our regulatory efforts. In recent years, the nuclear medicine subsector has shown a significant decline in performance in the Radiation Protection Safety and Control area. This presentation will give an overview of nuclear medicine compliance data in Canada. It will describe the most common non-compliances and provide guidance on how to improve compliance in these areas. There will be a specific focus on instrumentation including the selection, calibration and use. It will also cover the best practices seen at some of the highest performing licensees.
CNSC Question & Answer Panel
Various | Canadian Nuclear Safety CommissionRoom 2032, 11:10 am - 12:00 pm
Join us for a question and answer session with CNSC management! The panel will include:
-The Director General of the Directorate of Nuclear Substance Regulation
-The Director of the Accelerators and Class II Facilities Division
-The Director of the Operations Inspection Division
-The Director of the Nuclear Substances and Radiation Devices Licensing Division