September 2014
CNSC Research Report 2012-13 and 2013-14
The Science of Safety
CNSC Research Report
2012–13 and 2013–14
September 2014
September 2014
CNSC Research Report 2012-13 and 2013-14
CNSC Research and Support Program 2012–14 Research Report
The Science of Safety
© Canadian Nuclear Safety Commission (CNSC) 2014
PWGSC catalogue number CC172-114/2014E-PDF
ISBN 978-1-100-24996-4
Extracts from this document may be reproduced for individual use without permission
provided the source is fully acknowledged. However, reproduction in whole or in part for
purposes of resale or redistribution requires prior written permission from the Canadian
Nuclear Safety Commission.
Également publié en français sous le titre: La science de la sûreté - rapport de
recherche de la CCSN 2012-2013 et 2013-2014
Document availability
This document can be viewed on the CNSC website at nuclearsafety.gc.ca. To request a
copy of the document in English or French, please contact:
Canadian Nuclear Safety Commission
280 Slater Street
P.O. Box 1046, Station B
Ottawa, Ontario K1P 5S9
CANADA
Tel.: 613-995-5894 or 1-800-668-5284 (in Canada only)
Facsimile: 613-995-5086
Email: info@cnsc-ccsn.gc.ca
Website: nuclearsafety.gc.ca
Facebook: facebook.com/CanadianNuclearSafetyCommission
YouTube: youtube.com/cnscccsn
Publishing history
September, 2014
Edition 1.0
September 2014
CNSC Research Report 2012-13 and 2013-14
Table of Contents
1.
The Science of Safety......................................................................................................................1
2.
Introduction ....................................................................................................................................2
3.
Protecting Communities ................................................................................................................4
4.
Protecting Workers ........................................................................................................................8
5.
Protecting the Environment ........................................................................................................13
6.
Upholding International Commitments .....................................................................................16
7.
Advancing Regulatory Perspectives ...........................................................................................19
8.
Strengthening the Next Generation ............................................................................................23
9.
The Research and Support Program in the Years Ahead ........................................................25
10.
Summary of All Research Reports .............................................................................................26
11.
Glossary of Terms ........................................................................................................................27
12.
Annex A: CNSC Technical Papers, Presentations and Articles ...............................................29
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The Science of Safety
The Canadian Nuclear Safety Commission (CNSC) has a mandate to protect the health and safety
of Canadians, their communities and their environment, and also to respect Canada’s international
commitments on the peaceful use of nuclear energy. It is a mandate that demands objective,
scientific knowledge. It is the foundation for clear legislation, relevant regulations and reliable,
evidence-based decision making.
It is a mandate we will never compromise.
To advance that knowledge, we carry out scientific research that ensures Canada’s nuclear safety
standards and safeguards are as strong and effective as they can be.
This report is intended to share some of the key research activities the CNSC has facilitated and
supported over the past two years. The outcome of these research activities helps the CNSC
understand and address new or emerging safety issues; gain third-party perspectives on nuclear
science; and share scientific knowledge with the nuclear industry and the public at large. This
research helps support the CNSC’s mandate to disseminate objective scientific, technical and
regulatory information to the public concerning the activities of the Commission and the industry
it regulates.
That’s the science of safety.
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Introduction
The purpose of this report
The CNSC carries out a wide variety of research to support its mandate. This work is made
available to the public via the CNSC website or through its library. 1 By its nature, this research is
highly specialized and often contains scientific and technical language that would be unfamiliar
to a non-specialist. This report aims to summarize, for a more general audience, the research
and/or research-related activities carried out by the CNSC over the past two fiscal years. To assist
in understanding some of the technical language in the document, a glossary of terms has been
provided. Words that are highlighted are linked to a definition in the glossary.
The CNSC does research
The CNSC’s research program is designed to provide CNSC staff with access to external
independent advice, expertise and information. The program funds agreements with the private
sector, academic institutions, and governmental/non-governmental organizations, in Canada and
internationally.
The objectives of the research program are to:
• Support timely, science-based regulatory judgments and decisions
• Assist in the identification of problems that may give rise to health, safety, security or
environmental hazards
• Develop tools and techniques to address potential issues
• Aid in the development of safety standards
The majority of the CNSC’s research has been carried out through a competitive contracting
process sponsored solely by the CNSC. Recently, however, an increasing amount of work is
being performed in collaboration with national and international partners to effectively share the
costs and information. The CNSC has authority to contribute to these collaborative agreements,
and financial information on these expenditures is available in the CNSC’s annual Departmental
Performance Report.
In the report chapters that follow, you will find a brief description of the research projects and
other collaborative efforts that were completed between April 1, 2012 and March 31, 2014. Most
of these projects took multiple years to complete. Although many were related to the regulation of
nuclear power plants, you will find projects related to all aspects of the nuclear industry regulated
by the CNSC—from uranium mines and mills, through waste repositories, to life-saving medical
devices and radioactive substances in everyday life.
The CNSC also has a small grant budget used to facilitate the sharing of information related to
our mandate, to encourage outreach, and to fund smaller research projects. We have highlighted a
number of grant projects in this report.
In addition to the work carried out through the CNSC’s Research and Support Program contracts
and grants, CNSC staff publish scientific papers on subjects related to program activities. A list of
these scientific papers is found in Annex A.
1 A small amount of CNSC research is classified for security reasons or to protect information that
may be proprietary to a licensee.
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While much of the research is used to inform the regulatory documents and decisions made by the
Commission, CNSC staff actively work to ensure that the scientific community and the public are
informed of the scientific and technical basis that guides our regulatory effort.
Where can I get more information?
Readers interested in obtaining more details will find a link at the end of each project or report
2
description to an abstract or to the complete research report, where available. You may also
browse
the
CNSC
Research
and
Support
Program
Web
page
at
nuclearsafety.gc.ca/eng/resources/research.
Questions or queries may be directed to research-recherche@cnsc-ccsn.gc.ca.
2 In some cases, the title of a collaborative agreement is provided in this report even though the
final report has not yet been released by collaborating agencies. A link to that report will be
provided when it becomes available.
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Protecting Communities
By ensuring facilities operate safely over the long term, we protect
communities where nuclear power is generated
Nuclear plants are complex systems with thousands of interdependent parts, many of which need
to withstand years of exposure to intense heat and irradiation. A significant proportion of CNSC
research focuses on making sure these systems and components are up to the challenge.
Life past 30: Understanding the long-term effects of irradiation on calandria vessels
The target lifespan for Canada’s CANDU-based nuclear power plants when they were first built
was projected to be about 30 years, but current thinking suggests the potential to safely double
that lifespan. The CNSC requires this hypothesis to be scientifically verified by having licensees
carry out condition assessments for the various components of nuclear facilities, as part of an
integrated safety review.
When a nuclear power plant undergoes life extension,
licensees are required to assess the condition of the
structures, systems and components that will not be
replaced or refurbished. One such structure is the
calandria vessel, which cannot be replaced and is
difficult to access for potential degradation or inservice property changes. As a result, licensees must
rely on published data concerning limited stainless
steel testing programs to assess the fitness-for-service
of the vessels for long-term operation. Much of this
data has been generated for operating conditions
typical of pressurized water reactors, which do not
operate at the same temperatures and irradiation levels
as CANDU calandria vessels. The calandria vessel
houses fuel channels and contains a significant quantity
of heavy water—which can help keep fuel cool in
emergency situations.
The calandria is a cylindrical,
unpressurized stainless-steel vessel
that houses the CANDU reactor's
moderator and fuel.
Because the temperature and flux at which steel is
irradiated has a major effect on its mechanical
properties, the CNSC partnered with the University of
Illinois to better understand the effects of irradiation on stainless steel base metals and welds. It is
already known that stainless steel (of which calandria vessels are made) may become brittle with
long-term exposure to radiation, although inspections in Ontario and New Brunswick have shown
no service-related degradation after 30 years. The study also considered whether or not the data
used by licensees are adequate for predicting the end-of-life properties of CANDU calandria
vessels after 60 years in service.
The available data on low-temperature fracture-toughness revealed that high-temperature
estimates used by licensees appear to provide conservative estimates of material toughness with
respect to CANDU usage, meaning the current data are relevant for the assessment of the longerterm integrity of calandria vessels. This analysis supports the CNSC’s recommendation that
extension of CANDU calandria vessel operation is acceptable, and that operating licences can be
granted for refurbished plants.
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Refer to the CNSC Research and Support Program website for the final report: Irradiation Effects
on Material Properties for 304L Stainless Steel Base Metal and Welds
More accurate safety assessments built upon years of experience
Ensuring the safe operation of facilities requires a clear and comprehensive overall understanding
of risk. This becomes complex when an event has the potential to cause the failure of two or more
components in a short span of time. Such events are known as adverse common-mode events, or
common-cause failures.
In 2012 the CNSC took licensee data gathered over decades of nuclear power plant operation to
estimate the probability of common-cause failures related to batteries, heat exchangers, diesel
generators and other components. Replacing previous theoretical calculations, the new estimates
provide more accurate input into safety and reliability analyses, and the data gathered generate
qualitative insights into the root causes of common-cause failures. This helps to prioritize and
improve inspections and to confirm that licensees are taking adequate corrective actions to
prevent common-cause failures.
Refer to the CNSC Research and Support Program website for the final report: Statistical
Analysis of Common-Cause Failure Data to Support Safety and Reliability Analysis of Nuclear
Power Plant Systems
Verifying a new method for calculating neutron overpower protection trip setpoints in
aging reactors
Nuclear reactors are automatically shut down if an unacceptably high level of neutron flux in the
core is measured by the neutron overpower protection detector. For each neutron overpower
protection detector within a reactor, the trip setpoint must be programmed specifically to react to
a certain level of flux. It is the neutron overpower protection trip setpoints that can shut down a
reactor to prevent potential damage of fuel in the reactor core. Ontario Power Generation and
Bruce Power have recently developed a new statistical method for calculating neutron overpower
protection trip setpoints, a method that takes into account the aging conditions at their power
stations.
As a follow-up to an independent review of the licensees’ new method in 2009, the CNSC
conducted its own review to evaluate and validate the accuracy of the methodology. This review
found the method to be sensitive to sample size and error variances. This is a concern because it
is difficult to ensure that error variances are not overestimated. The position the CNSC ultimately
takes concerning the method may require neutron overpower protection trip setpoints to be
reduced at each licensee’s power station, to the extent that electrical output will also need to be
reduced.
Refer to the CNSC Research and Support Program website for the final report: OPG/BP 2010
EVS Methodology for Calculation of NOP Trip Setpoint: Independent Verification and
Benchmarking of Statistical Method and Mathematical Framework
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Improving the management and monitoring of aging cables in nuclear power plants
A nuclear power plant contains many important power, control and instrument cables. As nuclear
facilities continue to age, the incidence of cable failure increases, posing new challenges for their
long-term safety and stability. Replacing these
cables is expensive, and no industry guidelines
for their management exist. The study involved
analyzing and comparing the cable management
programs of Canadian nuclear facilities against
those implemented around the world. The report
concluded that the current international guidance
on cable aging management is generally
appropriate. The report also made eleven
recommendations for Canadian nuclear power
plants to ensure an effective cable management
program. These recommendations will help the
CNSC draft new guidelines and regulations for
Aging cables observed in nuclear plants
cable monitoring and aging management and
with problems such as, cracked cable
ensure that all licensees have a standardized and
jackets and discolored connecter points.
effective aging management program in place.
Refer to the CNSC Research and Support Program website for the final report: Ageing
Management of Cable in Nuclear Generating Stations.
Independent assessment of steam generator tubes with a failed support plate
Assessing the state of pipes at nuclear power generating stations is
important for maintaining safety. As plants age, special attention goes to
monitoring the fatigue of pipes and their supports. One such support plate
failure took place at a Canadian nuclear power plant more than a decade
ago. This study primarily focused on the consequence of support loss to
the straight portion of steam generator tubes. This involved performing
both deterministic and probabilistic assessments. The assessments
address items of interest such as potential crack growth predictions, leak
rate predictions, support clearances, and tube crack life probabilities.
This independent study confirmed that the current lifecycle management
program for steam generators is effective and can be relied upon to
ensure continued safe operation.
Refer to the CNSC Research and Support Program website for the final
report: Investigation of the Fatigue Cracking and Leakage Rate Potential
of U-Bend Tube Bundles Subjected to Flow-Induced Vibrations
Probabilistic assessment of leak rates through steam generator tubes
This project gathered data on CANDU and pressurized water reactor
steam generator tube degradation mechanisms and resulting leak rates.
The consolidated data enable CNSC staff to evaluate, with better
confidence, the integrity of steam generator tubes for operating nuclear
power generating stations in Canada. The project involved developing
a probabilistic assessment methodology for leak rate modelling and
implementing these models in a steam generator integrity computer
6
A typical nuclear
power plant steam
generator.
September 2014
CNSC Research Report 2012-13 and 2013-14
program known as CANTIA. Further to this, an experimental database was also developed to
validate existing computer models. These models are used to help regulators assess the reliability
of plant structures, systems and components. As a result of this regulatory research, the CNSC is
at the forefront of knowledge in this field.
Refer to the CNSC Research and Support Program website for the final report: Assessment of
Leak Rates through Steam Generator Tubes
CNSC participation in the International Steam Generator Tube Integrity Program
The United States Nuclear Regulatory Commission has brought leading nuclear regulators
together to advance research on steam generator tube integrity. The purpose of the International
Steam Generator Tube Integrity Program is to generate and share data regarding known and
newly identified aging and degradation mechanisms in steam generator tubes. The data can then
be used to support or adjust fitness-for-service and safety analyses of nuclear power plants over
time. In particular, the types and severity of failures that could occur are studied. This
information, in conjunction with reliability data, is important for regulatory oversight.
Reports disclosing the present activities and results of the International Steam Generator Tube
Integrity Program are not available in the public domain. Refer to the United States Nuclear
Regulatory Commission website for information regarding past activities.
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Protecting Workers
Our research protects the environment and workers on the front lines of
Canada’s nuclear industry—in mines, mills and power plants
To keep workers safe, regulations, standards and requirements must be based on the strongest,
most up-to-date evidence and must include every facet of the nuclear workplace.
Human factors: Safety means managing fatigue
Fatigue can hinder the performance of any
job, including nuclear facility work. For this
reason, the CNSC monitors hours of work at
reactors and is formalizing its requirements in
a regulatory document. As part of the
development process for this document, an
expert on hours of work and fatigue made
recommendations based on scientific evidence
and benchmarking related to shift schedules.
The research report is an important input into
the development of evidence-based regulatory
requirements.
Operator monitors reactor systems
in the control room.
Refer to the CNSC Research and Support
Program website for the final report: Review of Criteria for Assessing Shift Schedules in the
Nuclear Industry
Estimating radiation dose ranges for radon decay products in uranium mines
Using a standard conventional approach to measure the airborne concentration of radon decay
products in uranium mines is challenging, due to significant variations in mine environments—
even between workstations in the
same mine. Studying exposure to
radon is important, as it has been
identified as the second greatest
cause of lung cancer in uranium
miners, after smoking.
Through a study completed last
year, the CNSC sought to better
understand to what degree
environmental factors (e.g.,
particle size, the ratio of
concentrations of the immediate
radon decay products) within a
mine can affect dose estimation.
This is necessary to determine
whether an epidemiological
(disease-based) or dosimetric
A uranium miner checks his gauge to ensure that all
activities are safe.
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CNSC Research Report 2012-13 and 2013-14
(dose-based) approach would be most appropriate for assessing radon-progeny (or radon decay
products) dose for Canadian uranium miners, and to better understand how environmental factors
within a mine affect radon decay products’ doses.
The study found that data collected at modern uranium mines in support of adopting the
dosimetric approach to estimating dose is limited. The study also concluded that considerable
uncertainties exist with respect to the International Commission on Radiological Protection’s
implementation of a fully dosimetric approach. The CNSC will continue with its current practice
for monitoring, reporting and regulating miners’ exposure to radon decay products, until further
advances in this field have been made.
Refer to the CNSC Research and Support Program website for the final report: Estimation of the
Range of Radiation Dose for a Radon Progeny Working Level Due to Physical Parameters
Re-evaluation of default annual limits on intake (ALI) for yellowcake and uranium ore
Recent studies suggest the default annual limits on intake (ALI) for non-calcined yellowcake that
were previously recommended by the Atomic Energy Control Board (the CNSC’s precursor until
2000) may not be sufficiently protective. Yellowcake is an intermediate product produced in the
processing of uranium ore. The study of default ALI
is important because absorption, ingestion or
inhalation of yellowcake is dangerous, given that
chronic exposure can lead to disease due to its
chemical toxicity. This study provides ALI based on
more recent solubility data and updated dosimetric
methods published by the International Commission
on Radiological Protection (ICRP).
The CNSC contracted SENES Consultants Limited
to perform a two-phased study. The first phase
involved performing a literature review. The second
phase involved compiling solubility data available
for Canadian uranium mining and milling
operations. With the solubility data, absorption
parameters were derived as input to the dosimetric
models
used by the ICRP. The results of the
Yellowcake extracted from Uranium
dosimetric
modelling were used to calculate new
ore in a drum.
annual limits on intake values for uranium ore dust,
as well as calcined and non-calcined yellowcake. CNSC licensees operating uranium mines and
mills have been informed of the results of this study and will be asked to adopt these results into
their respective radiation protection programs.
Refer to the CNSC Research and Support Program website for the final report: Evaluation of
Default Annual Limits on Intake (ALI) for Yellowcake and Uranium Ore
Safe limits for uranium miners
Canada is one of the world’s largest uranium producers. With active mines operating in
Saskatchewan, and new projects being proposed for both Saskatchewan and Nunavut, protection
of miner health is a top priority.
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Underground uranium miners are occupationally exposed to radon and its radioactive radon decay
products. Exposure to radon has been identified as the second leading cause of lung cancer in
uranium miners, after smoking. Studies of early underground uranium miners found significantly
elevated risks of lung cancer, which led to major improvements in ventilation. Studies of
underground uranium miners provide the basis
for understanding the risk of lung cancer from
radon and radon decay products. In 2012 the
CNSC set out to update the data on Ontario’s
well-studied cohort of uranium miners—the
largest in Canada, numbering more than 30,000
since the 1950s. The CNSC contracted Statistics
Canada to gather the most recent national
mortality (1956–2007) and cancer (1969–2005)
data on the cohort. Extending the period
covered by the mortality database provides
more than 20 years of additional study since the
last update in 1986.
This study builds on the CNSC’s understanding
of the occupational health risks of uranium
A uranium miner attaches his dosimeters so
mining, essential for considering any potential
that his dose is monitored.
changes to uranium mining standards and
regulations and to further protect Canadian miners. The findings may also inform the regulatory
decision-making processes of agencies in other countries and ultimately be applied to the
estimation of cancer risk from radon progeny exposure in Canadian dwellings.
Refer to the CNSC Research and Support Program website for the final report: Summary Report
of the Ontario Uranium Miners Cohort Mortality and Cancer Incidence Study
Reviewing the “800-shot” rule for doses from portable gauges
Portable gauges are used by the construction, mining and petroleum industries to measure the
material density of inner structures or drilling sites. The gauges contain a gamma radiation
source, where safe and secure handling and storage is important.
The CNSC’s precursor, the Atomic Energy
Control Board, established the “800-shot” rule
for portable gauge users, which says that an
operator who performs fewer than 800
measurements (or “shots”) is not likely to
exceed the annual radiation dose limit of 1 mSv.
This rule also states that an individual’s annual
effective dose could be estimated by tracking the
number of measurements per year and
multiplying those by a factor of 1.2
µSv/measurement.
A portable gauge is used at a construction
sites to check density and depth of road
surfaces.
In 2012 a CNSC-led project looked at the actual
doses received by portable gauge users and reevaluated the longstanding approach to making
dose estimates. The CNSC contracted Stantec Consulting to monitor the doses received and the
number of measurements performed by more than 150 portable gauge users over approximately
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one year. The results show that while doses are generally quite low, basing estimates on the
number of measurements does not accurately represent the actual doses received.
As a result of this study and other experience gained in the regulation of portable gauge users,
CNSC staff are now evaluating other dosimetry methods that would more accurately track the
doses to portable gauge users.
Refer to the CNSC Research and Support Program website for the final report: Review of INFO0286 (1988): Doses from Portable Gauges
Supporting the Canadian Radiation Protection Association
The CNSC has continued its longstanding support of the Canadian Radiation Protection
Association (CRPA) by providing a grant in each of the last two years. The CRPA brings together
radiation safety workers from universities, hospitals, the nuclear power industry, radiation
safety consulting and all levels of government. So that society can benefit safely from the use of
radiation, the CPRA works to advance the development and communication of scientific
knowledge, and also to promote practical ways of protecting people and the environment from the
harmful effects of radiation.
Refer to the Canadian Radiation Protection Association website for more information regarding
the organization and its initiatives.
Verifying a new bunker design for radiotherapy facilities
Often, the CNSC’s involvement with students leads to important research findings. This was the
case in 2012–13 when the CNSC provided a grant to help a student in McGill University’s
medical physics graduate program conduct research into neutron dosimetry. The project studied
the safety of staff, patients and the general public located in the vicinity of the 140 or so highenergy radiation therapy bunkers operating under CNSC licence in hospitals across Canada.
This project involved a study of the
production, propagation and dosimetry of
neutrons within and beyond these bunkers.
It used Monte Carlo modelling techniques,
which were validated through measurements
in radiation therapy facilities at the McGill
University Health Centre.
In addition to providing a student with
hands-on experience in neutron dosimetry
and Monte Carlo simulations, any
associated software developed during the
course of the work could be used to perform
dosimetric analyses of new radiation therapy
facilities incorporating doorless bunkers in
their design.
A doctor and a patient in a radiotherapy
facilities where shielding would be required for
safety.
No report is available pertaining to this grant.
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Supporting the Canadian Organization of Medical Physicists Winter School
The Canadian Organization of Medical Physicists (COMP) Winter School is an annual event that
brings together experts from across the country to discuss issues of quality and safety in radiation
oncology, from the perspective of Canadian regulations and best practices. In continuing its
support for the previous three editions of the Winter School, the CNSC provided COMP with a
grant in each of the last two years to help cover the travel cost for guest speakers attending the
five-day conference.
Refer to the Canadian Organization of Medical Physicists website for more information regarding
the organization and its initiatives.
Supporting the development of an industry consensus document by the Canadian
Partnership for Quality Radiotherapy
There are currently no prescriptive requirements for conducting quality assurance testing of
radiation therapy equipment. With retirement of the obsolete industry consensus document for the
quality assurance of radiation therapy equipment, the Canadian Partnership for Quality
Radiotherapy asked the CNSC for its support in developing a new industry consensus document
outlining the required safety system tests and appropriate frequency of testing of Class II
radiation therapy equipment.
Recognizing an opportunity to contribute to the overall regulatory and safeguards framework of
the Canadian nuclear technology industry, the CNSC contributed to the development of these
standards by providing the Canadian Partnership for Quality Radiotherapy with technical
expertise and a grant in 2012–13, which enabled the document’s author to present the standards at
various scientific meetings across Canada.
Refer to the Canadian Partnership for Quality Radiotherapy website for more information
regarding the organization and its initiatives.
Supporting the Second International Symposium on the System of Radiological Protection
The International Commission on Radiological Protection (ICRP) is a premier international
organization for the protection of workers, patients and the public against ionizing radiation. It
was established in 1928 as the International X-ray and Radium Protection Committee to advance
the science of radiological protection, with its work in the early years focusing mainly on
occupational exposure in medicine. The ICRP has published extensively over the years, with 13
sets of general recommendations since 1928. These recommendations form the basis of radiation
safety standards worldwide. The CNSC provided a grant in 2013–14 to support the Second
International Symposium on the System of Radiological Protection, in order to help broaden
awareness of ICRP recommendations and to increase engagement with organizations interested in
radiation protection.
Refer to the International Commission on Radiological Protection website for more information
regarding the organization and its initiatives.
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Protecting the Environment
The knowledge we gather protects the environment
One of the cornerstones of the CNSC’s mandate is to minimize environmental harm in every
segment of the nuclear industry, from uranium mines to power plants, to nuclear waste storage
sites.
Determining how microbial activity affects the safety of deep geological repositories
Many countries, including Canada, are considering storing radioactive waste underground in deep
geological repositories. One of the questions needing to be answered before such projects proceed
is whether microorganisms living beneath the surface of the earth could affect the stability of
radioactive material after it has been sealed away.
CNSC staff collaborated with other Canadian and international experts to review the latest
research on microbial processes that could affect the long-term safety of deep geological
repositories. Their efforts built upon research already underway at the CNSC in preparation for
two proposed geological repositories in Canada. The resulting report recommended further
research on microbial communities to give CNSC staff better and more complete information to
review future deep geological repository construction and operating licence applications.
Refer to the CNSC website for the final report: Numerical Modelling of Gas Migration from a
Deep Geological Repository in Ontario’s Sedimentary Rocks
Understanding how excavation and operation of deep geological repositories affect
sedimentary rock formations
To provide licensing recommendations
and disseminate objective information for
stakeholders in relation to geological
disposal projects, the CNSC conducted a
study to assess the excavation damage
zone in sedimentary rock due to the deep
geological repository construction.
Researchers conducted a comprehensive
laboratory program, in collaboration with
Natural Resources Canada’s CANMET
and France’s Institut de Radioprotection et
de Sûreté Nucléaire (IRSN), investigating
the anisotropic behaviour of the
Tournemire shale in France. This shale can
be used to simulate the sedimentary rock
damage zone in deep geological repository
excavations. The researchers performed an
assessment of the excavation damage zone
and showed the extent of the excavation
damage
zone
around
a
typical
emplacement room of the Ontario Power
Generation deep geological repository.
The research demonstrated that the
An example of the proposed deep geological
repositories that are being assessed by the CNSC
as an option for safe and secure long-term
nuclear waste storage.
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damage zone caused by excavation actually extends several metres above and below the
emplacement room and will not extend into the overlying shale cap rocks.
Refer to the CNSC Research and Support Program website for the final report: Laboratory
Characterization, Modelling, and Numerical Simulation of an Excavation-Damaged Zone around
Deep Geologic Repositories in Sedimentary Rocks
Shared experience, stronger measures
To determine how its standards for uranium mines compare to the environmental expectations
placed on other types of mines in Canada, the CNSC conducted a study of waste management
practices throughout the mining sector. This yielded valuable answers for mining operations of all
stripes.
Working with Environment Canada and Natural Resources Canada’s CANMET Mining and
Mineral Sciences Laboratories, the CNSC refined its understanding of issues related to water
quality, risk identification, effective waste management and the various types of technologies
used. The research project also looked back to the period before the CNSC began enforcing
environmental protection, affirming that, as Canadian regulations have strengthened, the nuclear
industry’s environmental performance has also measurably improved.
The results of this research have been captured in a detailed report. The report findings will not
only help the CNSC enhance its regulatory framework on waste management, but due to crosssector comparisons, will contribute to improving the management of environmental performance
in other mines.
Refer to the CNSC Research and Support Program website for the final report: A Critical Review
of the Environmental Performances of Canadian Mines in Meeting Effluent and Water Quality
Criteria
Tritium transport to the terrestrial environment
Tritium is an important contributor to the public radiation dose at some CNSC-licensed facilities.
The CNSC reviews dose calculations to ensure they
appropriately account for the various ways tritium
can behave in the local environment. The CNSC
contracted the University of Ottawa to conduct field
and laboratory research on tritium’s transport and
uptake in the environment, with a focus on the
human food chain. This study specifically addressed
uncertainties relating to the formation and
persistence of organically bound tritium in soils and
food, after initially being released to the atmosphere
as tritium gas or tritiated water.
Field studies were conducted adjacent to a tritium
processing facility. Work involved growing grass
and vegetables (such as potatoes, beans and Swiss
chard). Representative weekly samples were taken
throughout the 2012 growing season, where the
14
A section of the field from the study
performed during the 2012 growing
season.
September 2014
CNSC Research Report 2012-13 and 2013-14
presence of tritiated water and organically bound tritium were measured using liquid scintillation
counting and mass spectrometry analysis. A variety of samples were taken and analyzed for
tritium concentrations, including air, precipitation, well water, soil, grass and vegetation samples.
The university concluded their study with the submission of all datasets. CNSC staff will be
analyzing the datasets to determine what, if any, additional data may be needed to meet
regulatory needs.
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Upholding International Commitments
Through research, we help fulfill Canada’s international commitments on
the peaceful use of nuclear energy
In collaboration with the International Atomic Energy Agency, nuclear and private industries, and
other governmental departments, the CNSC helps advance the evolution of safeguards and
improve the accounting for, and control of, nuclear material in Canada and abroad.
A large selection of flags from countries around the world
Does uranium processing leave “fingerprints”?
As the world’s nuclear watchdog, the International Atomic Energy Agency (IAEA) is tasked with
ensuring nuclear materials are not misused. Being able to trace nuclear material back to its origin
through unique “fingerprints” would aid them in this task. Working with Queen’s University, two
European laboratories, and industry, the CNSC traced Canadian-produced uranium through each
stage of the Canadian production process—from the mine through the mill, the refinery and the
conversion facility—where the uranium was ultimately prepared for use at Canadian fuel
fabrication facilities or for export. The objective was to see if, during processing, uranium
acquired characteristics or markers (such as impurities) that would make it traceable back to a
particular mine or facility.
Identifying predictable, repeatable characteristics of the samples proved challenging: a facility’s
processes can change over time, altering the “fingerprints” those processes leave in the uranium.
At the same time, a batch of uranium can show different patterns, depending on where and when
the sample is taken. Despite these challenges, researchers found it is indeed possible to identify
the origin of uranium, although only early in the production process. This study contributes to the
application of safeguards to Canadian exported material around the world. Experience gained in
this project is a valuable contribution to Canada’s knowledge of nuclear material forensics and
may be the basis for further research.
Taking stock in the aftermath of Fukushima
Following the accident at the Fukushima-Daiichi nuclear power plant in March 2011, the IAEA
required equipment to verify the transfer of spent nuclear fuel to a safe, long-term storage
location. The best tool for the job proved to be the Digital Cerenkov Viewing Device, codeveloped by the CNSC and the Swedish Nuclear Authority. This device meets the IAEA’s
requirements for spent fuel verification and has a minimum impact on facility operations. The
non-intrusive instrument uses the ultraviolet light produced from the interaction between the
radiation emitted from spent fuel and pool water. In support for this unique task, the CNSC
organized training courses throughout 2012 to instruct IAEA and Japanese inspectors how to use
the device effectively.
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A safe and secure nuclear monitoring network
To ensure sensitive information from IAEA-installed equipment around the world stays safe and
secure, the CNSC has supported the IAEA’s periodic evaluation of its remote monitoring network
against potential vulnerabilities. The IAEA network consists of cameras and radiation detectors
that monitor the flow of nuclear material in facilities on a daily basis. It ensures the peaceful use
of nuclear technology and material, along with the computer systems that collect and transmit
data from the equipment. The review also evaluated the IAEA’s ability to recover from failures,
whether due to malicious or other events. It is in Canada’s interest to ensure that the data sent by
these detectors are both authentic and secure. The final report on the assessment was submitted to
the IAEA in March 2013. It found no major concerns with the network’s capacity to stand up to
existing and emerging threats.
The key to the secure interchange of information
With the vision of a means for secure email communications among high-level safeguards staff,
the IAEA quickly identified public key infrastructure as an integral component of the information
security of their entire organization. The CNSC supported the application of this infrastructure to
IAEA email, servers, software, systems, and the IAEA remote monitoring system. The IAEA’s
capability to receive secure email allows the CNSC and its nuclear facilities to submit advance
information on the planned transfers of nuclear material and near-real time accountancy
declarations to the IAEA. This enables a more flexible and robust safeguards regime that relies on
fewer short-notice/unannounced inspections.
A portable laser-induced breakdown spectroscopy device
In collaboration with the National Research Council Canada, the CNSC has been developing a
portable hand-held device that uses laser-induced breakdown spectroscopy technology to identify
the origin of uranium yellowcake (U3O8) and other materials in the nuclear fuel cycle. The
device is intended to be used by the IAEA during inspections around the world to characterize
nuclear and non-nuclear materials for safeguards purposes. This particular project focuses on
improving the performance of previous generations in terms of robustness, design, ergonomics
and safety, while miniaturizing the device for in-field use.
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Novel technologies for the detection of undeclared
activities
The IAEA has requested its Member States to assist it
in developing new concepts, approaches, techniques
and technology for safeguards applications, in an
effort to improve and increase their ability to detect
undeclared nuclear material and activities. Under this
request, the CNSC has investigated the application of
novel technologies to safeguards, including compact
optically stimulated
luminescence-based
area
monitoring, cosmic ray inspection, passive
tomography,
and
laser-induced
breakdown
spectroscopy. The CNSC has worked with a number
of Canadian governmental organizations on these
tasks in an effort to find linkages with existing
projects, with the goal of improving the overall
safeguards system.
The CNSC monitors spent nuclear
fuel as part of its commitment to
nuclear non-proliferation.
Next-generation monitor of the flow of nuclear material
As part of the IAEA’s system that monitors the flow of nuclear material around the world, the
Canadian-developed VXI irradiated fuel monitoring system has been installed at over 40 facilities
worldwide, including at all Canadian power reactors. The detectors track the movements of
irradiated fuel, from the time it is discharged from the reactor until it is placed into long-term
storage. As part of this project, the CNSC has been assisting the IAEA in developing the next
generation of the data acquisition module at the heart of this system, to increase storage capacity
and functionality while maintaining compatibility with the existing systems. The new module will
also allow the IAEA to expand the use of the system to applications outside of nuclear power
plants.
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Advancing Regulatory Perspectives
Promoting and sharing regulatory knowledge with partners
One of the many lessons of the Fukushima-Daiichi disaster is that the impacts of nuclear
accidents are felt worldwide. The CNSC works actively with international partners and agencies,
in particular the IAEA and the Organisation for Economic Co-operation and Development’s
(OECD) Nuclear Energy Agency (NEA), to ensure that nuclear safety information and experience
is widely shared.
Developing international benchmarks for computational fluid dynamics to predict
turbulent flow in rod bundles
Analyzing the movement of fluid and heat in a nuclear reactor is very complex. The field of
computational fluid dynamics has emerged as a potentially valuable tool for analyzing flow and
heat transfer phenomena in nuclear facilities. One of the most promising applications of
computational fluid dynamics in the nuclear context relates to the cooling fluid flow around
reactor fuel, which is typically in the form of rod bundles. To explore this application, the NEA
organized an international benchmark exercise
based on experiments performed specifically for
this purpose in a South Korean research facility
owned by the Korea Atomic Energy Research
Institute (KAERI). The exercise was initiated in
April 2011 and ended in September 2012.
Part of the benchmark exercise involved 25
submissions with blind computational fluid
dynamics predictions of flow conditions, in two
experiments, from a number of organizations in
different countries. The CNSC worked with the
A typical CANDU reactor fuel bundle.
Atomic Energy of Canada Limited (AECL),
McMaster University and the University of Ottawa to produce three independent Canadian
submissions. Although a challenging task, this marked an important opportunity for the CNSC to
test the best computational fluid dynamics practice guidelines as developed and promoted
internationally by the NEA Committee on the Safety of Nuclear Installations.
The Canadian submissions were presented at the benchmark closing meeting in South Korea in
September 2012 and in a joint paper at the 24th Nuclear Simulation Symposium in Ottawa in
October 2012. The final summary report on the exercise was published by the NEA in July 2013.
Refer to the CNSC Research and Support Program website for the final report: International
Computational Fluid Dynamics (CFD) Benchmark Problem: Turbulent Flow in a Rod Bundle
with Spacers
Fire and smoke propagation testing
The CNSC, along with eight nuclear regulators, is collaborating to perform a series of fire tests to
study hot gas propagation in multi-room settings—the behavior of fire cable trays and electrical
cabinets, and the performance of fire extinguishing systems. The fire tests are being performed at
France’s Institut de Radioprotection et de Sûreté Nucléaire (IRSN) in Cadarache, France.
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The experimental data obtained from this
multi-year project will be used to validate
existing fire models and computer programs
in order to better quantify fire hazard risks.
The outcome from this collaborative project
will be useful for designers to select the best
fire protection strategy and will help nuclear
regulators with risk-informed regulatory
oversight for fire protection.
A final report will be published upon
completion of this collaborative study.
First responders during a typical fire drill.
Gathering data on international fire incidents
The CNSC collaborated with several leading nuclear regulators to create a quality-assured
database of fire events reported at nuclear facilities in each of the participating nations.
Significant effort was placed on defining the process that would capture fire event data in a
meaningful way to help with probabilistic and deterministic safety assessments. The project
participants collected and analyzed all fire events with the aim to promote preventive strategies.
The fire events database was also analyzed for trends. This analysis helps ensure that regulatory
inspections are focused on the right places, so that our plants continue to operate safely.
A final report will be published upon completion of this collaborative study.
Cyber security considerations for the application of satellite communications for remote
monitoring and controls of small modular reactors
Small reactor designs involve some novel
design and safety features. One such feature
includes the concept for remote monitoring
and control from a main control center via
satellite communication. This research
project involved surveying existing satellite
communications technology and its use in
industrial control applications. The study
identified the capabilities, strengths and
weaknesses for remote monitoring and
control
via
satellite
communication.
A satellite orbiting earth.
Numerous
standards, guidelines
and
regulations from over 30 internationally recognized institutions covering safety, cyber security,
and industrial communication networks were reviewed. The study concluded that satellite
communications may be used safely and securely under certain conditions. This input will assist
CNSC staff in establishing a regulatory position on this subject.
The final report for this project is subject to security restrictions. The CNSC cannot share the
deliverables from this study.
Supporting the Multinational Design Evaluation Programme
Established in 2007, the Multinational Design Evaluation Programme brings together several
leading national nuclear regulatory authorities, including the CNSC, to share their collective
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September 2014
CNSC Research Report 2012-13 and 2013-14
knowledge and enhance international collaboration in the areas of regulatory frameworks, vendor
inspections and the review of potential new nuclear power plant designs.
The Multinational Design Evaluation Programme incorporates a broad range of activities that
include enhancing multilateral cooperation within existing regulatory frameworks and increasing
multinational convergence of codes, standards, guides and safety goals. The CNSC recently
confirmed its continued participation in this important program to ensure staff stay on the leading
edge of developments in nuclear regulation.
Refer to the Multinational Design Evaluation Programme website for more information regarding
the organization and its initiatives.
Structural integrity impact testing
From 2008 to 2013, the CNSC participated in the Finnish-led IMPACT project. This project
examined the impact resistance of nuclear power plants under natural and human-induced
hazards, including the impact of an aircraft crash. As part of phase three of the IMPACT project,
the CNSC requested specific research and
testing be performed to address the Canadian
context—specifically, to determine whether
the containment design of new CANDU
nuclear facility concepts could withstand the
crash impact of an aircraft, along with the
safety risks resulting from such an impact.
The results of this project are incorporated
into the CNSC’s regulatory framework and
acceptance criteria for the design of future
nuclear power plant containment. They are
also applicable not only to CANDU plants,
but to several new designs (ATMEA1 and
APR14000) and existing nuclear power
The aftermath of an impact test.
plants. For this reason, the results are
implemented in IAEA Safety Reports.
The CNSC cannot share the deliverables from this collaboration, as they contain proprietary
information subject to access restriction. Two papers were written by CNSC staff concerning
relevant testing and analysis performed between 2011 and 2013 3, 4
Supporting the Annual Meeting of the International Cooperative
Environmentally Assisted Cracking of Water Reactor Materials
Group
on
The CNSC is a member of the International Cooperative Group on Environmentally Assisted
Cracking of Water Reactor Materials (ICG-EAC), which coordinates international efforts to
develop a fundamental understanding and relevant database for design criteria ensuring safe
operation and life extension of water-cooled reactors.
A grant was provided to support ICG-EAC’s 2012 annual meeting in Québec City. The meeting
provided a unique forum for more than 80 member organizations from 20 countries to exchange
3 N. Orbovic, A. Blahoianu, et al., 2013, Tests to Determine the Influence of Transverse Reinforcement on Perforation Resistance of
RC Slabs under Hard Missile Impact, Structural Mechanics in Reactor Technology, San Francisco, August18-23, 2013.
4 G. Sagals, N. Orbovic, and A. Blahoianu, 2013, Effect of Transverse Reinforcement for Missile Impact on Reinforced Concrete
Slabs, Structural Mechanics in Reactor Technology, San Francisco, August 18-23, 2013.
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CNSC Research Report 2012-13 and 2013-14
the latest ideas and data on material degradation, failure instances and emerging structural
integrity challenges of nuclear power plants.
Refer to the International Cooperative Group on Environmentally Assisted Cracking website for
more information regarding the organization and its initiatives. A report concerning the 2012
annual meeting is not available in the public domain.
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Strengthening the Next Generation
Our research is strengthening the next generation of scientists
Building Canada’s future scientific capacity is key to maintaining a safe, strong and innovative
nuclear industry. The CNSC is committed to reaching out to young Canadians and capturing their
interests early in their scientific careers, through (sometimes literally) out-of-this-world learning
opportunities.
Supporting the Deep River Science Academy summer program
The Deep River Science Academy offers high
school students the experience of hands-on
research and work under the direct supervision
of a university-level tutor and a professional
scientist. The Academy’s students perform
research work, much of which is at the Chalk
River Laboratories and is nuclear-related. Their
work includes setting up experiments, gathering
and analyzing data, and writing technical
reports, as well as giving oral presentations. The
program offers students two high-school credits.
The CNSC has continued its longstanding
support of the Deep River Science Academy by
providing a grant for each of the last two years.
Students are eagerly engaged in hands-on
work through the Deep River Science
Academy.
Refer to the Deep River Science Academy website for more information regarding the
organization and its initiatives.
Putting students in the spotlight
The CNSC is a significant supporter of the University Network of Excellence in Nuclear
Engineering (UNENE). UNENE brings together Canadian universities, nuclear power utilities,
and research and regulatory agencies, to support and advance nuclear education and research and
development. It also provides a sustainable supply of qualified nuclear engineers and scientists
for the country’s nuclear industry.
Among UNENE’s many activities, it provides for an annual
student workshop that allows students to showcase their
work through a poster session. The poster session attracts
graduate students from universities across Canada, allowing
them a valuable opportunity to present their research to
industry and CNSC representatives. The CNSC supported
the annual student poster session with a grant in each of the
last two years.
In December 2012, first prize was presented to the project “A Study of Gamma-Radiation
Induced Carbon Steel Corrosion” by K. Daub, X. Zhang, J. Noel and J.C. Wren of Western
University.
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In December 2013, first prize was presented to the project
“Determining Personal Protection Equipment Exposure in
Response to Radiation Hazard Scenarios” by M. Roeterink,
E.C. Corcoran, D.G. Kelly, and E.G. Dickson.
Refer to the University Network of Excellence in Nuclear
Engineering website for more information regarding the
organization and its initiatives.
Talking science with a famous Canadian astronaut
To spark students’ curiosity and raise awareness of how exciting careers in science can be, the
CNSC helped Let’s Talk Science bring radiation studies to classrooms across the country, and
connected one lucky group of kids with astronaut Chris Hadfield (who was at that time aboard the
International Space Station).
Let’s Talk Science is a national charitable organization focused on engaging children and youth
in science, technology, engineering and math. When it proposed a year-long program on
“Radiation and You”, the CNSC was eager to lend its support. The project represented an
opportunity for the CNSC to interact directly with Canadian youth and educate them about the
Canadian nuclear sector. A CNSC grant
allowed the purchase of personal
neutron detectors for schools, the
production of bilingual educational
resources, and the development of an
online tool for classrooms to enter their
data and compare radiation levels across
the country. The CNSC also provided its
expertise to develop educational
resources, and made its scientists
available to participate in a live Web
chat with students to answer their
questions about radiation- and sciencerelated careers.
A highlight of the initiative was Chris
Hadfield’s downlink (on March 11,
2013) with nearly 1,000 students at Bert
Church High School in Airdrie, Alberta.
From the International Space Station,
Chris Hatfield generating interest in science
Hadfield talked to the students about his
amongst young Canadians.
work using neutron detectors to measure
background radiation. As an extension of that one event, the “Radiation and You” program
equipped more than 7,500 Canadian school kids with their own detectors, allowing them to
measure background radiation on Earth and compare their results to Hadfield’s radiation readings
in space, through the Let’s Talk Science website.
Refer to the Let’s Talk Science website for more information regarding the organization and its
initiatives.
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CNSC Research Report 2012-13 and 2013-14
The Research and Support Program in the Years Ahead
Our research will always focus on health, safety, security and the
environment
Each year, CNSC staff set objective-driven regulatory research priorities to advance scientific
knowledge in areas where uncertainties exist and safety margins may be better characterized.
Regulatory research is also utilized to set a risk-informed regulatory position for existing and new
technologies.
In the near term, regulatory research will seek to:
• Enhance knowledge concerning the biological effects from alpha emitters.
• Enhance the capability to respond to a severe accident based on external hazards
analyzed and lessons learned from Fukushima.
• Advance knowledge to assess the safety margins of reactor pressure tubes and steam
generator tubes while taking aging-related degradation into account. Research in this area
will assist CNSC staff in assessing the aging management programs for each Canadian
nuclear site.
• Advance knowledge in structural seismic analysis as it pertains to nuclear reactor
facilities. New information may influence regulatory requirements and set a higher bar
for new designs.
• Advance knowledge concerning the long-term suitability of underground radioactive
waste storage in response to proposed deep geological repository sites.
• Advance knowledge of permafrost degradation predictions in Canadian northern regions
to assess potential environmental impacts of proposed uranium mining and long-term
uranium tailings storage sites in continuous permafrost zones.
• Acquire the latest knowledge in examination techniques and methodologies to assess
their suitability for certification testing of reactor operators and exposure device
operators.
Readers interested in obtaining more information may refer to the CNSC Research and Support
Program Web page at nuclearsafety.gc.ca/eng/resources/research.
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CNSC Research Report 2012-13 and 2013-14
Summary of All Research Reports
Protecting Communities
1) Irradiation Effects on Material Properties for 304L Stainless Steel Base Metal and Welds
2) Statistical Analysis of Common-Cause Failure Data to Support Safety and Reliability
Analysis of Nuclear Power Plant Systems
3) OPG/BP 2010 EVS Methodology for Calculation of NOP Trip Setpoint: Independent
Verification and Benchmarking of Statistical Method and Mathematical Framework
4) Ageing Management of Cable in Nuclear Generating Stations
5) Investigation of the Fatigue Cracking and Leakage Rate Potential of U-Bend Tube
Bundles Subjected to Flow-Induced Vibrations
6) Assessment of Leak Rates through Steam Generator Tubes
Protecting Workers
1) Review of Criteria for Assessing Shift Schedules in the Nuclear Industry
2) Estimation of the Range of Radiation Dose for a Radon Progeny Working Level Due to
Physical Parameters
3) Evaluation of Default Annual Limits on Intake (ALI) for Yellowcake and Uranium Ore
4) Summary Report of the Ontario Uranium Miners Cohort Mortality and Cancer Incidence
Study
5) Review of INFO-0286 (1988): Doses from Portable Gauges
Protecting the Environment
1) Numerical Modelling of Gas Migration from a Deep Geological Repository in Ontario’s
Sedimentary Rocks
2) Laboratory Characterization, Modelling, and Numerical Simulation of an ExcavationDamaged Zone around Deep Geologic Repositories in Sedimentary Rocks
3) A Critical Review of the Environmental Performances of Canadian Mines in Meeting
Effluent and Water Quality Criteria
Advancing Regulatory Perspectives
1) International Computational Fluid Dynamics (CFD) Benchmark Problem: Turbulent
Flow in a Rod Bundle with Spacers
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Glossary of Terms
Anisotropic
Exhibiting properties with different values when measured in
different directions.
Calandria
A cylindrical, unpressurized stainless-steel vessel that holds a
CANDU reactor's moderator. Pressure tubes containing the fuel
and coolant span the two endplates of the calandria.
Computational fluid dynamics
The study of numerical methods and algorithms used to analyze
fluid flow and heat transfer. Computational fluid dynamics are
often used to analyze the interactions of liquids and gases with
metal surfaces.
Cosmic ray
High-energy charged particles, originating in outer space, that
travel at nearly the speed of light and strike Earth from all
directions. Also called cosmic radiation.
Deterministic safety analysis
An analysis of nuclear power plant responses to an event
performed using predetermined rules and assumptions (e.g.,
those concerning the initial operational state, availability and
performance of the systems and operator actions). Deterministic
analysis can use either conservative or best-estimate methods.
Dosimetry
A scientific subspecialty in radiation protection and medical
physics that calculates the internal and external doses from
ionizing radiation.
Integrated safety review
A comprehensive assessment of nuclear facility design and
operation that deals with the cumulative effects of aging,
modifications, operating experience, technical developments
and siting aspects, and aims at ensuring a high level of safety
throughout the operating life of the facility (or activity).
Laser-Induced breakdown
spectroscopy
A non-destructive technique used to detect the elements of a
given surface of matter, regardless whether it is solid, liquid or
gas.
Liquid scintillation counting
A method used to measure tritium. Tritium is a very weak beta
radiation emitter, usually measured by mixing a sample with
chemicals that emit light when they come into contact with beta
radiation. The tritium sample and the light emitting chemical
mixture are placed inside a light measuring instrument, called a
scintillation detector. This is calibrated to count the amount of
tritium in the sample.
Mass spectrometry analysis
A technique that produces spectra of the masses of the atoms or
molecules comprising a sample of material. The atoms or
molecules in the sample can be identified by correlating known
masses to the identified masses.
Monte Carlo modelling
A method that uses computational algorithms for simulating the
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CNSC Research Report 2012-13 and 2013-14
behaviour of various physical and mathematical systems by the
use of random numbers.
Optically stimulated
luminescence
A method used to measure dose from ionizing radiation.
Passive tomography
An imaging procedure that detects gamma rays emitted when
positrons from a positron-emitting source (such as F-18) collide
with electrons in tissue.
Probabilistic safety assessment
The probability, progression and consequences of equipment
failures or transient conditions to derive numerical estimates
that provide a consistent measure of safety.
Radionuclide
A nucleus of an atom that possesses properties of spontaneous
disintegration (i.e., radioactivity). Nuclei are distinguished by
their mass and atomic number. This term is often used
synonymously with radioisotope.
Tritium
A radioisotope of the element hydrogen (symbol T or 3H).
Tritium is produced both naturally and as a by-product in
nuclear reactors. The nucleus of tritium contains one proton and
two neutrons. Tritium atoms can replace hydrogen atoms in
water molecules to form tritiated water (HTO), in organic
molecules to form organically bound tritium (OBT), and in air
to form tritiated gas (HT). Tritium also exists in many other
compounds such as tritiated hydrocarbons, tritiated particulates,
tritiated thymidine, and metal tritides. Tritium decays by
emitting an electron (beta radiation) and has a half-life of 12.33
years.
Yellowcake
The concentrated oxide of uranium formed in the milling of
uranium ore. Yellowcake undergoes calcination (or is calcined)
to remove impurities from the milling process to produce
commercial-grade uranium.
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Annex A: CNSC 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 author technical
articles that are published in various journals.
Below is a listing of abstracts for published papers, presentations and journal articles.
To obtain a copy of the document related to an abstract, please contact us at info@cnscccsn.gc.ca or call 613-995-5894 or 1-800-668-5284 (in Canada). When contacting us, please
provide the title and date of the abstract.
Subject
Presented at or
published in
Publisher or
location
delivered
Date
Authors
Type
A reanalysis of cancer mortality in
Canadian nuclear workers (1957-1994)
based on revised exposure and cohort
data
British Journal of
Cancer
November
1, 2013
Nature
Publishing
Group
L.B. Zablotska (University of
California), R.S.D. Lane (CNSC),
P.A. Thompson (CNSC)
Peer-reviewed
journal article
CANDU Safety Design
CNS CANDU
Technology and
Safety Course
October
28–30,
2013
Toronto, Ontario
W. Shen (CNSC)
Abstract of a
technical
presentation
A nuclear forensic method for
determining the age of radioactive
cobalt sources
Analytical
Methods
October 25,
2013
Royal Society of
Chemistry
L. Charbonneau, J.-M. Benoit, S.
Jovanovic, N. St-Amant, S. Kiser,
M.W. Cooke, J.-F. Mercier, K.
Nielsen, D. Kelly, P. Samuleev, R.
Galea, K. Moore, P.R.B. Saull, D.B.
Chamberlain, J.L. Steeb, D.G.
Graczyk, Y. Tsai, V.S. Sullivan, I.C.
Dimayuga, Y. Shi, R. Rao, D.
Larivière
Peer-reviewed
journal article
WGAMA/WGFS Status Report on
Spent Fuel Pool (SFP) under loss of
cooling accident conditions
WGAMA/WGFS
Status Report on
Spent Fuel Pool
(SFP)
October 2425, 2013
Paris, France
W. Grant (CNSC)
Abstract of a
technical
presentation
Regulatory Review of the CANDU
Fuel Modification Program in Canada
The 12th
International
Conference on
CANDU Fuel
September
15–18,
2013
Kingston,
Ontario
Y. Guo (CNSC)
Abstract of a
technical
presentation
Fuel performance in aging CANDU
reactors – A quick overview of the
CNSC regulatory oversight activities
of the past 15 years and of the lessons
learned
The 12th
International
Conference on
CANDU Fuel
September
15–18,
2013
Kingston,
Ontario
M. Couture (CNSC)
Abstract of a
technical
presentation
Radiation Exposure and Cancer
Incidence (1990 to 2008) Around
Nuclear Power Plants in Ontario,
Canada
Journal of
Environmental
Protection
September
1, 2013
Scientific
Research
Publishing
R. Lane, E. Dagher, J. Burtt, P.A.
Thompson (CNSC)
Peer-reviewed
journal article
IRIS 2012 Benchmark – Part I:
Overview and Summary of the Results
SMiRT-22
August 18–
23, 2013
San Francisco,
California
N. Orbovic (CNSC), F. Tarallo
(IRSN), J.-M. Rambach (IRSN), A.
Blahoianu (CNSC)
Abstract of a
technical
presentation
IRIS 2012 Benchmark – Part II:
Lessons Learned and
Recommendations
SMiRT-22
August 18–
23, 2013
San Francisco,
California
N. Orbovic (CNSC), F. Tarallo
(IRSN), J.-M. Rambach (IRSN), A.
Blahoianu (CNSC)
Abstract of a
technical
presentation
Lack of Correlation (Incoherence)
Modeling and Effect from Realistic 3D
Inclined, Body and Surface Seismic
Motions
SMiRT-22
August 18–
23, 2013
San Francisco,
California
N. Tafazzoli (University of
California), T. Ancheta (Risk
Management Solutions), N. Orbovic
(CNSC), A. Blahoianu (CNSC), B.
Jeremic (Lawrence Berkeley
National Laboratory)
Abstract of a
technical
presentation
29
September 2014
Subject
CNSC Research Report 2012-13 and 2013-14
Presented at or
published in
Publisher or
location
delivered
Date
Authors
Type
Synthetic Earthquake Ground Motions
at Closely Spaced Distances with
SYNACC
SMiRT-22
August 18–
23, 2013
San Francisco,
California
M.I. Todorovska (U. Southern
California), M.D. Trifunac (U.
Southern California), V.W. Lee (U.
Southern California), N. Orbovic
(CNSC)
Abstract of a
technical
presentation
Effect of Transverse Reinforcement
for Missile Impact on Reinforced
Concrete Slabs
SMiRT-22
August 18–
23, 2013
San Francisco,
California
G. Sagals, N. Orbovic, A. Blahoianu
(CNSC)
Abstract of a
technical
presentation
Tests to Determine the Influence of
Transverse Reinforcement on
Perforation Resistance of RC Slabs
under Hard Missile Impact
SMiRT-22
August 18–
23, 2013
San Francisco,
California
N. Orbovic (CNSC), F. Tarallo
(IRSN), J.-M. Rambach (IRSN), A.
Blahoianu (CNSC)
Abstract of a
technical
presentation
PSA Approach for Evaluation of
External Hazards as part of CNSC
Fukushima Action Items
International
Workshop on
PSA of Natural
External Hazards
Including
Earthquakes
June 17–19,
2013
Prague, Czech
Republic
M. Xu (CNSC)
Abstract of a
technical
presentation
Application of Probabilistic Safety
Goals to Regulation of Nuclear Power
Plants in Canada
34th Annual
Conference of
Canadian Nuclear
Society
June 9–12,
2013
Toronto, Ontario
G. Rzentkowski, Y. Akl, S. Yalaoui
(CNSC)
Abstract of a
technical
presentation
Flashing Flow of Subcooled Liquid
Through Small Cracks
Procedia
Engineering
May 1,
2013
Elsevier
S. Revankar, B. Wolf, J. Riznic
(CNSC)
Peer reviewed
journal article
Independence of Nuclear Regulators in
the Aftermath of the Fukushima
Daiichi Nuclear Accident: A
Comparative Approach
IAEA
International
Conference on
Effective Nuclear
Regulatory
Systems
Nordic PSA
Conference,
Castle Meeting –
Swedish
Radiation Safety
Authority (SSM)
April 8–12,
2013
Ottawa, Ontario
M. Bacon-Dussault (CNSC)
Abstract of
technical paper
April 10–
12, 2013
Stockholm,
Sweden
S. Yalaoui (CNSC)
Abstract of a
technical
presentation
CNSC Regulatory Requirements on
Reliability of Nuclear Power Plants
Society of
Reliability
Engineers –
Ottawa Chapter
March 27,
2013
Ottawa, Ontario
S. Yalaoui (CNSC)
Abstract of a
technical
presentation
Mortality (1950-1999) And Cancer
Incidence (1969-1999) Of Workers In
The Port Hope Cohort Study Exposed
To A Unique Combination Of
Radium, Uranium And Gamma-Ray
Doses
BMJ Open
February 1,
2013
BMJ Group
L.B. Zablotska (University of
California), R.S.D. Lane (CNSC),
S.E. Frost (Frost & Frost
Consultants)
Peer-reviewed
journal article
Life Extension of Nuclear Research
Reactors
The European
Nuclear
Conference
(ENC), 2012
December
9–12, 2012
Manchester, UK
I. Erdebil, A. Omar (CNSC)
Abstract of
technical paper
CNSC Nuclear Power Plant Accident
Handbook
2012 ANS Winter
Meeting and
Nuclear
Technology Expo
November
11–15,
2012
San Diego,
California
C. Cole (CNSC), T. Nitheanandan,
M.J. Brown, S.M. Petoukhov, A.
Wood (AECL)
Abstract of
technical paper
Coupling Between DONJON and
CATHENA Using a Bash Script for
RIH Break Opening Time Assessment
24th CNS Nuclear
Simulation
Symposium
October
14–16,
2012
Ottawa, Ontario
M. Fassi Fehri (CNSC)
Abstract of
technical paper
Focus Areas for the Regulatory
Review of the Probabilistic Safety
Assessment of Seismic Events
30
September 2014
Subject
CNSC Research Report 2012-13 and 2013-14
Presented at or
published in
Publisher or
location
delivered
Date
Authors
Type
Canadian Participation in
OECD/NEA-KAERI ROD Bundle
Benchmark for CFD Codes
24th CNS Nuclear
Simulation
Symposium
October
14–16,
2012
Ottawa, Ontario
J. Szymanski (CNSC), D. Chang
(University of Ottawa), D. Novog
(McMaster University), K. Podila, J.
Bailey, Y. Rao, A. Rashkovan, S.
Tavoularis (AECL)
Abstract of
technical paper
Development of a Simplified Generic
PRA Model for Regulatory
Application
Workshop on
Advanced Code
Suites for Design,
Safety Analysis
and Operation of
Heavy Water
Reactors
October 2–
5, 2012
Ottawa, Ontario
A. Patel, R. Gheorghe, Y. Akl
(CNSC)
Abstract of
technical paper
Challenges in PSA Regulatory
Expectations for Nuclear Power Plants
in Canada
Technical
Meeting on
Probabilistic
Safety
Assessment for
New Nuclear
Power Plants'
Design
October –15, 2012
Vienna, Austria
(IAEA
Headquarters)
G. Renganathan, R. Gheorghe
(CNSC)
Abstract of a
technical
presentation
A Regulatory Perspective on the
Establishment of Fuel Safety Criteria
for the Large Loss of Coolant
Accident
Technical
Meeting on Fuel
Integrity during
Normal Operating
and Accident
Conditions in
Pressurised Heavy
Water Reactors
(PHWRs)
September
24–27,
2012
Bucharest,
Romania
A. El-Jaby (CNSC)
Abstract of
technical paper
Lung cancer mortality (1950-1999)
among Eldorado uranium workers: A
comparison of the TSCE and ERR
models
PLoS ONE
August 24,
2012
Public Library
of Science
M. Eidemüller, P. Jacob, R. Lane
(CNSC), S.E. Frost, L. Zablotska
Open access,
peer-reviewed
scientific
journal
Regulatory experience in applying a
radiological environmental protection
framework for existing and planned
nuclear facilities
Annals of the
ICRP
August 22,
2012
Elsevier Ltd.
S. Mihok, P. Thompson (CNSC)
Peer-reviewed
journal article
Nuclear Power Plant Accident
Handbook, A CNSC Emergency
Operations Centre Tool
33rd Conference
of the Canadian
Nuclear Society
June 10–13,
2012
Saskatoon,
Saskatchewan
C. Cole (CNSC), T. Nitheanandan,
M.J. Brown, S.M. Petoukhov, A.
Wood (AECL)
Abstract of
technical paper
Canadian Regulatory Requirements for
Safety Analysis of Nuclear Power
Plants
The 2nd
International
Nuclear Energy
Congress
May 22-–
24, 2012
Warsaw, Poland
J. Kowalski (CNSC)
Abstract of a
technical
presentation
Why an effective national regulatory
infrastructure is essential for a
country’s radiation protection system
13th International
Congress of the
International
Radiation
Protection
Association
May 18–24,
2012
Glasgow, UK
D. Mroz,* E. Reber, H. Suman, I.
Shadad, T. Hailu, H. Mansoux
(IAEA)
Abstract of a
technical
presentation
*D. Mroz, currently with CNSC,
posted as an IAEA staff member at
the time of this publication
31