Technical papers, presentations and articles
Experts at the Canadian Nuclear Safety Commission (CNSC) are often requested to present technical papers and presentations about the nuclear industry at conferences, seminars, technical meetings and workshops in Canada and around the world. Also, these experts write technical articles that are published in various journals.
CNSC experts also contribute to the development of research projects. Abstracts and the final research reports are available under the CNSC Research and Support Program.
Below is a listing of abstracts for published papers, presentations and journal articles.
To obtain a copy of the document that is related to an abstract, contact the CNSC. When contacting the CNSC, please provide the title and date of the abstract.
2024
| Title: | Probabilistic Evaluation of the Impact of Inspection Uncertainties on the Estimation of Flaw Growth Rate |
|---|---|
| Topic: | Fitness for Service of Steam Generators |
| Date: | October 7-9, 2024 |
| Presented at: | 5th International Symposium on Probabilistic Methodologies for Nuclear Applications (ISPMNA) |
| Location: | Tokyo, Japan |
| Prepared by: | Bogdan Wasiluk & M. Pandey |
| Type: | Abstract of a technical presentation |
| Title: | CNSC Safety considerations for the review of Small Modular Reactors |
|---|---|
| Topic: | Severe accidents |
| Presented at: | International Atomic Energy Agency (IAEA) |
| Date: | October 14-17, 2024 |
| Location: | Vienna, Austria * In-person |
| Prepared by: | Mounia Berdaï |
| Type: | Abstract of a presentation |
| Title: | Beyond Design Basis Thermo-Mechanical Approaches to Improving Safety Performance |
|---|---|
| Topic: | Improvements to Physical design |
| Presented at: | Structural Mechanics in Reactor Technology SMiRT27 |
| Date: | March 3-8, 2024 |
| Location: | Yokohama, Japan |
| Prepared by: | Thambiayah Nitheanandan1 |
| Type: | Extended Abstract |
| Subject: | Numerical Analysis of in-vessel Melt Retention of CANDU Reactors During a Severe Accident |
|---|---|
| Published in: | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) proceedings |
| Date: | August 25-28, 2024 |
| Location: | Vancouver, B.C., Canada |
| Authors: | S. Gyepi-Garbrah, F. Mehdi Zadeh, B. Moore, T. Nitheanandan |
| Type: | Abstract of a technical paper |
| Title: | Regulatory Role of PSA in Canada and lessons learned from its use in advanced reactor facilities |
|---|---|
| Topic: | Probabilistic Safety Assessment |
| Presented at: | 17th International Conference on Probabilistic Safety Assessment and Management & Asian Symposium on Risk Assessment and Management |
| Date: | 7-11 October, 2024 |
| Location: | Sendai International Center, Sendai, Miyagi, Japan |
| Prepared by: | Hayat Chatri, Michael Xu, Abderrazzaq Bounagui |
| Type: | Abstract of a technical paper |
| Title: | Optimizing Filtered Containment Vent System Performance for CANDU Reactors |
|---|---|
| Topic: | Severe Accident Safety Analysis |
| Presented at: | Specialists Workshop on Advanced Instrumentation and Measurement Techniques for Nuclear Reactor Thermal-Hydraulics and Severe Accidents (SWINTH-2024) |
| Date: | June 17-20, 2024 |
| Location: | Dresden, Germany |
| Prepared by: | Mohamed Shawkat |
| Type: | Abstract of a technical paper for a conference |
| Title: | Trilateral Principles Paper on the Deployment of Artificial Intelligence in Nuclear Activities |
|---|---|
| Topic: | Artificial Intelligence |
| Date: | TBD – Sept 2024 |
| Prepared by: | Kevin Lee (CNSC) along with Andrew White (UK ONR), Daniel Finnigan (UK ONR) and Matt Dennis (US NRC). |
| Type: | Principle Paper |
| Title: | Load Carrying Capacities of Small-Diameter Pipe Bends under Internal Pressure: Analytical and Computational Predictions |
|---|---|
| Topic: | Fitness for Service of Feeders |
| Presented at: |
Proceedings of 2024 Pressure Vessels and Piping Conference (PVP 2024) by American Society of Mechanical Engineers |
| Date: | July 28-August 2, 2024 |
| Location: | Bellevue, WA, USA |
| Prepared by: |
N. Robinson and X. Wang, Carleton University B. Wasiluk, Canadian Nuclear Safety Commission |
| Type: | Abstract of a technical paper |
| Title: | CNSC activities in support to severe accident research |
|---|---|
| Topic: | Regulatory framework |
| Presented at: | Cooperative Severe Accident Research Program (CSARP) |
| Date: | June 3-7, 2024 |
| Location: | Bethesda United State (virtually) |
| Prepared by: | Mounia Berdaï |
| Type: | Abstract of a presentation |
| Title: | Towards a technology neutral regulatory framework: Example of containment |
|---|---|
| Topic: | Regulatory framework |
| Presented at: | Cooperative Severe Accident Research Program (CSARP) |
| Date: | June 3-7, 2024 |
| Location: | Bethesda United State (virtually) |
| Prepared by: | Mounia Berdaï |
| Type: | Abstract of a presentation |
| Title: | The Canadian Nuclear Safety Commission’s Role in Facing Challenges related to Severe Accident Analysis associated with Small Modular Reactors |
|---|---|
| Presented at: | The 11th European Review Meeting on Severe Accident Research Conference (ERMSAR 2024) |
| Date: | May 13-16, 2024 |
| Location: | Stockholm, Sweden |
| Prepared by: | Samuel Gyepi-Garbrah |
| Type: | Abstract of a technical presentation |
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