Finally, nuclear engineering textbooks with a Canadian flavour!

International Nuclear Information System (INIS)

Bonin, H.W.

2002-01-01

The need for nuclear engineering textbooks more appropriate to the Canadian nuclear industry context and the CANDU nuclear reactor program has long been felt not only among the universities offering nuclear engineering programs at the graduate level, but also within the Canadian nuclear industry itself. Coverage of the CANDU reactor system in the textbooks presently supporting teaching is limited to a brief description of the concept. Course instructors usually complement these textbooks with course notes written from their personal experience from past employment within the nuclear industry and from their research interests In the last ten years, the Canadian nuclear industry has been involved on an increasing basis with the issue of the technology transfer to foreign countries which have purchased CANDU reactors or have been in the process of purchasing one or several CANDUs. For some of these countries, the 'turn key' approach is required, in which the Canadian nuclear industry looks after everything up to the commissioning of the nuclear power plant, including the education and training of local nuclear engineers and plant personnel. Atomic Energy of Canada Limited (AECL) in particular has dispatched some personnel tasked to prepare and give short courses on some specific aspects of CANDU design and operation, but a lack of consistency was observed as different persons prepared and gave the courses rather independently. To address the many problems tied with nuclear engineering education, the CANTEACH program was set up involving major partners of the Canadian nuclear industry. Parts of the activities foreseen by CANTEACH consist in the writing of nuclear engineering textbooks and associated computer-based pedagogical material. The present paper discusses the main parts of two textbooks being produced, one in reactor physics at steady state and the other on nuclear fuel management. (author)

Proceedings of the Canadian Nuclear Society 12. annual conference

International Nuclear Information System (INIS)

1991-01-01

This volume contains the Proceedings of the seventeen Technical Sessions from the Twelfth Annual Conference of the Canadian Nuclear Society held in Saskatoon, Saskatchewan, June 9 to 12, 1991. As in previous years, the Annual Conference of the Canadian Nuclear Society was held in conjunction with the Annual Conference of the Canadian Nuclear Association. The major topics of discussion included: reactor physics; thermal hydraulics; industrial irradiation; computer applications; fuel channel analysis; small reactors; severe accidents; fuel behaviour under accident conditions; reactor components; safety related computer software; nuclear fuel management; nuclear waste management; and, uranium mining processing

Canadian nuclear risk experience

International Nuclear Information System (INIS)

Hamel, P.E.

1982-05-01

Risk assessment in the Canadian nuclear fuel cycle is a very important and complex subject. Many levels of government are involved in deciding the acceptable limits for the risks, taking into account the benefits for society [fr

Women and nuclear issues: Comments in a Canadian perspective

International Nuclear Information System (INIS)

Dionne-Marsolais, Rita

1989-01-01

When the Canadian Nuclear industry launched its information program, it was found that women were less supportive of nuclear power. Reasons were difficult to pin-point and hovered around individual perceptions and misunderstandings. The basis of the Canadian Nuclear Association Public Information program lies with its target: men and women equally. The Program Takes Into Consideration The major characteristics and nuances of these two groups. Female Characteristics from Canadian Perspective are: Strong sense of generation continuity; Detail and task oriented; Nontechnical training; Strong sense of individuality (local). Patterns of behavoiur in relation to nuclear industry for women in Canada are: not prone to take risks; micro-economic approach to decisions (local); little confidence in technology; pragmatic and balanced in their choices (local). Major concerns of Canadian women are: Safety of power plants; disposal of waste; peace and environment versus growth and energy need; trustworthiness of the industry. Canadian nuclear association public information program communirations -approach covers: the right message, down to earth language, factual and real information for real choices, effective reach: spokespeople and media buy. Results of polls: show thtt women are less in favour of Nuclear energy in Canada today than men, consider NPPs less important in Meeting Canada's energy need in the years ahead; and think that Nuclear Energy is not a choice for Canada of all sources of energy available for large scale use

Nuclear regulation - the Canadian approach

International Nuclear Information System (INIS)

Jennekens, J.

1981-09-01

Although the Atomic Energy Control Board was established 35 years ago the basic philosophy of nuclear regulation in Canada and the underlying principles of the regulatory process remain essentially unchanged. This paper outlines the Canadian approach to nuclear regulation and explains in practical terms how the principles of regulation are applied. (author)

Proceedings of the Canadian Nuclear Association 35. annual conference

International Nuclear Information System (INIS)

Loewer, R.

1995-01-01

The proceedings of the thirty-fifth annual conference of the Canadian Nuclear Association contain 22 papers organized in the following sessions: update on the status of the Canadian nuclear industry, non-proliferation and related political issues, nuclear waste disposal perspectives, regulatory issues, trade development, new markets, economics of nuclear electricity, public acceptance or rejection. In addition one paper from a CNA/CNS special session on nuclear diffraction is included. The individual papers have been abstracted separately

Certification of Canadian nuclear power plant personnel

International Nuclear Information System (INIS)

Newbury, F.

2014-01-01

The Canadian Nuclear Safety Commission (CNSC) regulates the use of nuclear energy and materials to protect health, safety, security of Canadians and the environment, and to implement Canada's international commitments on the peaceful use of nuclear energy. As part of its mandate, the CNSC requires certification of those who work in positions with direct impact on the safety of Canadian nuclear power plants (NPPs) and research reactors. Other positions, such as exposure device operators and radiation safety officers at other nuclear facilities, also require CNSC certification. In this paper, the certification process of Canadian NPP personnel will be examined. In keeping with the CNSC's regulatory philosophy and international practice, licensees bear the primary responsibility for the safe operation of their NPPs. They are therefore held entirely responsible for training and testing their workers, in accordance with applicable regulatory requirements, to ensure they are fully qualified to perform their duties. The CNSC obtains assurance that all persons it certifies are qualified to carry out their respective duties. It achieves this by overseeing a regime of licensee training programs and certification examinations, which are based on a combination of appropriate regulatory guidance and compliance activities. Reviews of the knowledge-based certification examination methodology and of lessons learned from Fukushima have generated initiatives to further strengthen the CNSC's certification programs for NPP workers. Two of those initiatives are discussed in this paper. (author)

Canadian approach to nuclear power safety

International Nuclear Information System (INIS)

Atchison, R.J.; Boyd, F.C.; Domaratzki, Z.

1983-01-01

The development of the Canadian nuclear power safety philosophy and practice is traced from its early roots at the Chalk River Nuclear Laboratories to the licensing of the current generation of power reactors. Basic to the philosophy is a recognition that the licensee is primarily responsible for achieving a high standard safety. As a consequence, regulatory requirements have emphasized numerical safety goals and objectives and minimized specific design or operating rules. In this article the Canadian licensing process is described with a discussion of some of the difficulties encountered. Examples of specific licensing considerations for each phase of a project are included

Canadian--American relations and the nuclear weapons controversy, 1958--1963

International Nuclear Information System (INIS)

Ghent, J.M.

1976-01-01

This study attempts to explain the nuclear weapons controversy as it developed between 1958 and 1963. The nuclear controversy centered around Canada's acceptance of a nuclear role, within the American alliance system, for the Canadian armed forces. In the period 1958-1959, when the critical weapons decisions were being taken, Canadian political authorities lost control of the policy-making process, permitting the Canadian and American military bureacracies to initiate nuclear plans suited to their common needs and objectives. Prime Minister Diefenbaker's reluctance to arm the systems acquired by transborder bureaucratic coalition is also re-examined. Previous analysts have regarded the government's hesitations over nuclear weapons as the product of Diefenbaker's personal antagonism towards President Kennedy or as a futile attempt to reverse the process of continental integration. The opening of the Kennedy papers reveals the degree to which Diefenbaker was committed to close Canadian-American cooperation and the effort he made to overcome the president's hostility towards him. This study emphasizes the importance of Diefenbaker's sensitivity to public, parliamentary, and cabinet opposition to nuclear arms. The secret U.S. demand for nuclear bases in Labrador and Newfoundland is revealed. Thus the question of nuclear storage in Canada for Canadian forces was complicated by U.S. insistence that Canada simultaneously provide nuclear storage for the strategic forces of the U.S. Finally, the extent of American responsibility for Diefenbaker's demise is re-assessed, and the conclusion is reached that the U.S., through Canadian-American military interaction and the initiative of the ambassador in Ottawa, did in fact help to bring down the government of Canada

The Canadian nuclear fuel waste management program

International Nuclear Information System (INIS)

Rummery, T.E.; Rosinger, E.L.J.

1983-05-01

The Canadian Nuclear Fuel Waste Management Program is now well established. This report outlines the generic research and technological development underway in this program to assess the concept of immobilization and subsequent disposal of nuclear fuel waste deep in a stable plutonic rock in the Canadian Shield. The program participants, funding, schedule and associated external review processes are briefly outlined. The major scientific and engineering components of the program, namely, immobilization studies, geoscience research and environmental and safety assessment, are described in more detail

The Canadian Centre for Nuclear Innovation

Energy Technology Data Exchange (ETDEWEB)

Root, J., E-mail: John.Root@usask.ca [Canadian Centre for Nuclear Innovation, Inc., Saskatoon, Saskatchewan (Canada)

2013-07-01

The Canadian Centre for Nuclear Innovation (CCNI) was incorporated on December 20, 2011, to help place Saskatchewan among global leaders of nuclear research, development and training, through investment in partnerships with academia and industry for maximum societal and economic benefit. As the CCNI builds a community of participants in the nuclear sector, the province of Saskatchewan expects to see positive impacts in nuclear medicine, materials research, nuclear energy, environmental responsibility and the quality of social policy related to nuclear science and technology. (author)

Finally, nuclear engineering textbooks with a Canadian flavour{exclamation_point}

Energy Technology Data Exchange (ETDEWEB)

Bonin, H.W. [Royal Military College of Canada, Dept. of Chemistry and Chemical Engineering, Kingston, Ontario (Canada)

2002-07-01

The need for nuclear engineering textbooks more appropriate to the Canadian nuclear industry context and the CANDU nuclear reactor program has long been felt not only among the universities offering nuclear engineering programs at the graduate level, but also within the Canadian nuclear industry itself. Coverage of the CANDU reactor system in the textbooks presently supporting teaching is limited to a brief description of the concept. Course instructors usually complement these textbooks with course notes written from their personal experience from past employment within the nuclear industry and from their research interests In the last ten years, the Canadian nuclear industry has been involved on an increasing basis with the issue of the technology transfer to foreign countries which have purchased CANDU reactors or have been in the process of purchasing one or several CANDUs. For some of these countries, the 'turn key' approach is required, in which the Canadian nuclear industry looks after everything up to the commissioning of the nuclear power plant, including the education and training of local nuclear engineers and plant personnel. Atomic Energy of Canada Limited (AECL) in particular has dispatched some personnel tasked to prepare and give short courses on some specific aspects of CANDU design and operation, but a lack of consistency was observed as different persons prepared and gave the courses rather independently. To address the many problems tied with nuclear engineering education, the CANTEACH program was set up involving major partners of the Canadian nuclear industry. Parts of the activities foreseen by CANTEACH consist in the writing of nuclear engineering textbooks and associated computer-based pedagogical material. The present paper discusses the main parts of two textbooks being produced, one in reactor physics at steady state and the other on nuclear fuel management. (author)

Nuclear power and the Canadian public

Energy Technology Data Exchange (ETDEWEB)

Greer-Wootten, B; Mitson, L

1976-06-01

The purpose of the study was to ascertain the opinions and attitudes of Canadians to the use of nuclear power for generating electricity, as an initial step in developing information programs attuned to the demonstrated needs of the public. This report presents the findings from the survey of the Canadian public aged 18 years and over. Over 2100 persons responded to our interviewers, generating about 200,000 answers to the questions.

Proceedings of the Canadian Nuclear Society 15. annual conference

Energy Technology Data Exchange (ETDEWEB)

Huynh, H M [Hydro-Quebec, Montreal, PQ (Canada)

1994-12-31

The proceedings of the 15. annual conference of the Canadian Nuclear Society cover a wide range of nuclear topics, but the emphasis is on CANDU reactors and Canadian experience. The 89 papers are arranged in 17 sessions dealing with the following subjects: thermalhydraulics, fuel channels, operations, reactor physics, fuel, new technology, safety, training, waste management. The individual papers have been abstracted separately.

Proceedings of the Canadian Nuclear Society 15. annual conference

International Nuclear Information System (INIS)

Huynh, H.M.

1994-01-01

The proceedings of the 15. annual conference of the Canadian Nuclear Society cover a wide range of nuclear topics, but the emphasis is on CANDU reactors and Canadian experience. The 89 papers are arranged in 17 sessions dealing with the following subjects: thermalhydraulics, fuel channels, operations, reactor physics, fuel, new technology, safety, training, waste management. The individual papers have been abstracted separately

The Canadian nuclear fuel waste management program

International Nuclear Information System (INIS)

Dormuth, K.W.; Nuttall, K.

1987-01-01

Canada has established an extensive research program to develop and demonstrate the technology for safely disposing of nuclear fuel waste from Canadian nuclear electric generating stations. The program focuses on the concept of disposal deep in plutonic rock, which is abundant in the province of Ontario, Canada's major producer of nuclear electricity. Research is carried out at field research areas in the Canadian Precambrian Shield, and in government and university laboratories. The schedule calls for a document assessing the disposal concept to be submitted to regulatory and environmental agencies in late 1988. This document will form the basis for a review of the concept by these agencies and by the public. No site selection will be carried out before this review is completed. 10 refs.; 2 figs

The Canadian approach to nuclear power safety

International Nuclear Information System (INIS)

Atchison, R.J.; Boyd, F.C.; Domaratski, Z.

1983-07-01

The development of the Canadian nuclear power safety philosophy and practice is traced from its early roots at the Chalk River Nuclear Laboratory to the licensing of the current generation of power reactors. Basic to the philosophy is a recognition that the primary responsibility for achieving a high standard of safety resides with the licensee. As a consequence, regulatory requirements have emphasized numerical safety goals and objectives and minimized specific design or operating rules. The Canadian licensing process is described along with a discussion of some of the difficulties encountered. Examples of specific licensing considerations for each phase of a project are included

Executive brief to federal government 'the Canadian nuclear industry - a national asset'

International Nuclear Information System (INIS)

1985-03-01

Over a period of 40 years Canada has developed a remarkable nuclear industry. In keeping with our mining heritage, we are the world's leading uranium producer, with the highest grade orebodies in existence still waiting to be tapped. In the realm of high technology development, our CANDU reactor is second to none. Year after year Canadian CANDUs dominate the 'top 10' performance records world-wide. The nuclear industry has created direct employment for over 30,000 Canadians. The 'high tech' sectors of the industry are now vigorously seeking export markets for their products and services. As the world recovers from the recent prolonged recession, electricity demand is rising. Once again electricity is the engine of growth. Already utilities are planning to add new generating capacity. Canadian nuclear resources, technology and skilled people are proven and available. By seizing the opportunities which are opening up for us, a properly recognized nuclear industry can make a vital contribution to Canada's economic renewal. This brief has been prepared by the Canadian Nuclear Association (CNA) in response to the challenge issued to Canadians in Finance Minister Michael Wilson's document 'A New Direction for Canada'. This brief responds in terms of the major policy issues and opportunities as seen by the Canadian nuclear industry

Forecasting Canadian nuclear power station construction costs

International Nuclear Information System (INIS)

Keng, C.W.K.

1985-01-01

Because of the huge volume of capital required to construct a modern electric power generating station, investment decisions have to be made with as complete an understanding of the consequences of the decision as possible. This understanding must be provided by the evaluation of future situations. A key consideration in an evaluation is the financial component. This paper attempts to use an econometric method to forecast the construction costs escalation of a standard Canadian nuclear generating station (NGS). A brief review of the history of Canadian nuclear electric power is provided. The major components of the construction costs of a Canadian NGS are studied and summarized. A database is built and indexes are prepared. Based on these indexes, an econometric forecasting model is constructed using an apparently new econometric methodology of forecasting modelling. Forecasts for a period of 40 years are generated and applications (such as alternative scenario forecasts and range forecasts) to uncertainty assessment and/or decision-making are demonstrated. The indexes, the model, and the forecasts and their applications, to the best of the author's knowledge, are the first for Canadian NGS constructions. (author)

Ecknomic benefits arising from the Canadian nuclear industry

International Nuclear Information System (INIS)

1982-03-01

This document is a collection of surveys of the Canadian nuclear industry, with forecasts covering a number of possible scenarios. Topics covered include uranium mining and processing; economic benefits arising from the design, manufacture and construction of CANDU generating stations; employment and economic activity in the Canadian nqclear industry; and an overview of the remainder of the industry

Transfer of Canadian nuclear regulatory technology

International Nuclear Information System (INIS)

Harvie, J.D.

1985-10-01

This paper discusses the Canadian approach to the regulation of nuclear power reactors, and its possible application to CANDU reactors in other countries. It describes the programs which are in place to transfer information on licensing matters to egulatory agencies in other countries, and to offer training on nuclear safety regulation as it is practised in Canada. Experience to date in the transfer of regulatory technology is discussed. 5 refs

Food and nutrition in Canadian "prime time" television commercials.

Science.gov (United States)

Ostbye, T; Pomerleau, J; White, M; Coolich, M; McWhinney, J

1993-01-01

Television is, arguably, the most influential mass medium and "prime time" viewing attracts the largest audiences. To assess the type, number and nutritional content of foods advertised on TV, commercial breaks during "prime time" (7:00 to 11:00 p.m.) on five Canadian channels (CBC-English, CBC-French, CTV, CFPL, Much Music) were recorded and analyzed. A similar analysis of Saturday morning children's TV commercials was also performed. Commercials for foods and food products constituted between 24-35% of all commercials, the largest advertising output for any group of products. The combination of food presented in commercials reflected average current consumption patterns. Of special concern was the emphasis on low nutrition beverages, especially beer, as well as snacks and candy on Much Music. While further government intervention to restrict advertising practices may be an impractical option, there is scope for increasing the alternative promotion of healthy dietary choices.

Research and Production Corporation Radiy activities within Canadian nuclear market

International Nuclear Information System (INIS)

Bakhmach, I.; Siora, O.; Kharchenko, V.; Sklyar, V.; Andrashov, A.

2011-01-01

This paper presents key results of RPC Radiy activities within Canadian nuclear market. RPC Radiy (located in Kirovograd, Ukraine) is a vendor which designs and produces digital safety I and C platform as well as turnkey applications, based on the platform, for NPPs (safety systems). The main feature of the Radiy Platform is the application of Field Programmable Gates Arrays (FPGA) as programmable components for logic control operations. Since 2009 RPC Radiy started to explore the possibility to conduct the expansion to Canadian nuclear market. The activities performed by RPC Radiy related to this direction are resulted in several joint projects with Canadian companies. (author)

Canadian Nuclear Association brief to the standing committee on Energy, Mines and Resources

Energy Technology Data Exchange (ETDEWEB)

NONE

1991-10-01

The Canadian Nuclear Association outlines points on electricity demand, environmental impact of electricity production, Canada`s nuclear technology and uranium deposits. Several recommendations are discussed that promote the Canadian nuclear industry and outline issues related to greenhouse gas emmisions, nuclear waste containment, funding of R and D and outlines the need for improving the environmental assessment approval processes.

Canadian Nuclear Association brief to the standing committee on Energy, Mines and Resources

International Nuclear Information System (INIS)

1991-10-01

The Canadian Nuclear Association outlines points on electricity demand, environmental impact of electricity production, Canada's nuclear technology and uranium deposits. Several recommendations are discussed that promote the Canadian nuclear industry and outline issues related to greenhouse gas emmisions, nuclear waste containment, funding of R and D and outlines the need for improving the environmental assessment approval processes

Canadian nuclear power plant construction cost forecast and analysis

International Nuclear Information System (INIS)

Keng, C.W.K.

1985-01-01

Because of the huge volume of capital required to construct a modern electric power generating station, investment decisions have to be made with as complete an understanding of the consequence of the decision as possible. This understanding must be provided by the evaluation of the situation to take place in the future. This paper attempts to use an econometric method to forecast the construction costs escalation of a standard Canadian nuclear generating station (NGS). A review of the history of Canadian nuclear electric power is provided. The major components of the construction costs of a Canadian NGS are studied and summarized. A data base is built and indexes are prepared. Based on these indexes an econometric forecasting model is constructed using an apparently new econometric methodology of forecasting modelling. Forecasts for a period of forty years are generated and applications of alternative scenario forecasts and range forecasts to uncertainty assessment are demonstrated. The indexes, the model, and the forecasts and their applications, to the best of the author's knowledge, are the very first ever done for Canadian NGS constructions

Nuclear communications : A Canadian perspective

International Nuclear Information System (INIS)

Macpherson, John A.

1994-01-01

Times have changed since the early days of nuclear energy when it was a symbol of a brave new world, Public information strategies have evolved to meet increasing public concerns, and have shifted from being a largely unfocused attempt at publicity to being more concerned with managing issues and solving problems. This paper describes some of the salient features of the Canadian experience in nuclear communications and examines four key aspects: opinion and attitude research; media relations; coeducation; and advertising. It also addresses the challenge of responding to the allegations and tactics of those who are actively hostile to nuclear energy, and recommends that the principles of Total Quality Management and of organizational effectiveness be applied more thorough and more consistently to the public affairs function

Proceedings of the Canadian Nuclear Society sixth annual conference

International Nuclear Information System (INIS)

French, P.M.; Phillips, G.J.

1985-01-01

The proceedings of the Sixth Annual Conference of the Canadian Nuclear Society comprise 103 papers on the following subjects: fuel technology, nuclear plant safety, instrumentation, public and regulatory matters, fusion, fuel behaviour under normal and accident conditions, nuclear plant design and operations, thermal hydraulics, reactor physics, accelerators, waste management, new reactor concepts

Intervention of the Canadian Nuclear Association to the National Energy Board

International Nuclear Information System (INIS)

1982-01-01

This submission from the Canadian Nuclear Association to the National Energy Board of Canada was made in support of the application by the New Brunswick Electric Power Commission to increase its electricity exports from the Point Lepreau nuclear station to the New England states from 205 MW to 335 MW. The Canadian Nuclear Association felt that their support was justified in view of the fact that the CANDU nuclear reactor had proven itself to be a safe, reliable and economic source of electric generation. They felt the 630 MW CANDU station at Point Lepreau, New Brunswick would have sufficient generating capacity to export 335 MW for a ten-year period

The Canadian nuclear power industry. Background paper

International Nuclear Information System (INIS)

Nixon, A.

1993-12-01

Nuclear power, the production of electricity from uranium through nuclear fission, is by far the most prominent segment of the nuclear industry. The value of the electricity produced, $3.7 billion in Canada in 1992, far exceeds the value of any other product of the civilian nuclear industry. Power production employs many more people than any other sector, the capital investment is much greater, and nuclear power plants are much larger and more visible than uranium mining and processing facilities. They are also often located close to large population centres. This paper provides an overview of some of the enormously complex issues surrounding nuclear power. It describes the Canadian nuclear power industry, addressing i particular its performance so far and future prospects. (author). 1 tab

The Canadian nuclear power industry. Background paper

Energy Technology Data Exchange (ETDEWEB)

Nixon, A [Library of Parliament, Ottawa, ON (Canada). Science and Technology Div.

1993-12-01

Nuclear power, the production of electricity from uranium through nuclear fission, is by far the most prominent segment of the nuclear industry. The value of the electricity produced, $3.7 billion in Canada in 1992, far exceeds the value of any other product of the civilian nuclear industry. Power production employs many more people than any other sector, the capital investment is much greater, and nuclear power plants are much larger and more visible than uranium mining and processing facilities. They are also often located close to large population centres. This paper provides an overview of some of the enormously complex issues surrounding nuclear power. It describes the Canadian nuclear power industry, addressing i particular its performance so far and future prospects. (author). 1 tab.

Canadian Nuclear Safety Commission's intern program

International Nuclear Information System (INIS)

Gilmour, P.E.

2002-01-01

The Intern Program was introduced at the Canadian Nuclear Safety Commission, Canada's Nuclear Regulator in response to the current competitive market for engineers and scientists and the CNSC's aging workforce. It is an entry level staff development program designed to recruit and train new engineering and science graduates to eventually regulate Canada's nuclear industry. The program provides meaningful work experience and exposes the interns to the general work activities of the Commission. It also provides them with a broad awareness of the regulatory issues in which the CNSC is involved. The intern program is a two-year program focusing on the operational areas and, more specifically, on the generalist functions of project officers. (author)

The Canadian Nuclear Safety Commission's financial guarantee requirements

International Nuclear Information System (INIS)

Ferch, R.

2006-01-01

The Nuclear Safety and Control Act gives the Canadian Nuclear Safety Commission (CNSC) the legal authority to require licensees to provide financial guarantees in order to meet the purposes of the Act. CNSC policy and guidance with regard to financial guarantees is outlined, and the current status of financial guarantee requirements as applied to various CNSC licensees is described. (author)

Proceedings of the Canadian Nuclear Association 25th annual conference

International Nuclear Information System (INIS)

1985-01-01

The twenty addresses presented in this volume celebrate the 25th anniversary of the Canadian Nuclear Association. They reflect upon evolving world electricity patterns, the nuclear power option, Canada's position as a supplier of uranium and nuclear technology, the future of the nuclear industry in Canada, and the position of the industry in the United States and Britain

Commercial nuclear-waste management

International Nuclear Information System (INIS)

Andress, D.A.

1981-04-01

This report is primarily concerned with nuclear waste generated by commercial power operations. It is clear, however, that the total generation of commercial nuclear waste does not tell the whole story, there are sizeable stockpiles of defense nuclear wastes which will impact areas such as total nuclide exposure to the biosphere and the overall economics of waste disposal. The effects of these other nuclear waste streams can be factored in as exogenous inputs. Their generation is essentially independent of nuclear power operations. The objective of this report is to assess the real-world problems associated with nuclear waste management and to design the analytical framework, as appropriate, for handling nuclear waste management issues in the International Nuclear Model. As such, some issues that are not inherently quantifiable, such as the development of environmental Impact Statements to satisfy the National Environmental Protection Act requirements, are only briefly mentioned, if at all

Proceedings of the Canadian Nuclear Association 34. annual conference

International Nuclear Information System (INIS)

Girard, A.M.

1994-01-01

The proceedings of the thirty-fourth annual conference of the Canadian Nuclear Association contain 23 complete papers and three speeches organized in the following sessions: opening, plenary, new environmental regulations and their effect on the energy industry, CANDU update, life cycle management of nuclear power plants, evolution of nuclear technology, technologies for tomorrow, nuclear used fuel and disposal of low-level waste, world economics and energy consumption. The complete papers have been abstracted separately

World-wide cooperation in nuclear power: a canadian perspective

International Nuclear Information System (INIS)

Whelan, D.

2000-01-01

This paper presents the point of view of Canadian Authorities about the future of nuclear activities. Generally speaking, OECD countries will be focusing their efforts on plant refurbishment, maintenance and life extension while non-OECD countries will be facing capacity expansion needs. This duality will favour collaboration in the nuclear field between OECD and other countries. Key areas for enhanced cooperation will be: nuclear technology, nuclear safety, regulations, waste management, non-proliferation and financing

Proceedings of the Canadian Nuclear Association 34. annual conference

Energy Technology Data Exchange (ETDEWEB)

Girard, A M [Atomic Energy of Canada Ltd., Montreal, PQ (Canada). CANDU Operations

1994-12-31

The proceedings of the thirty-fourth annual conference of the Canadian Nuclear Association contain 23 complete papers and three speeches organized in the following sessions: opening, plenary, new environmental regulations and their effect on the energy industry, CANDU update, life cycle management of nuclear power plants, evolution of nuclear technology, technologies for tomorrow, nuclear used fuel and disposal of low-level waste, world economics and energy consumption. The complete papers have been abstracted separately.

Proceedings of the seventeenth annual Canadian Nuclear Society conference

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-12-31

The seventeenth annual conference of the Canadian Nuclear Society, presented in Fredericton, New Brunswick. The conference includes papers on general topics of interest on the nuclear community, waste management and the environment, instrumentation and design of Candu reactors, safety analysis, thermal hydraulics, fuel channels, plant operations and in-core instrumentation.

Proceedings of the seventeenth annual Canadian Nuclear Society conference

International Nuclear Information System (INIS)

1996-01-01

The seventeenth annual conference of the Canadian Nuclear Society, presented in Fredericton, New Brunswick. The conference includes papers on general topics of interest on the nuclear community, waste management and the environment, instrumentation and design of Candu reactors, safety analysis, thermal hydraulics, fuel channels, plant operations and in-core instrumentation

Severe accident considerations in Canadian nuclear power reactors

International Nuclear Information System (INIS)

Omar, A.M.; Measures, M.P.; Scott, C.K.; Lewis, M.J.

1990-08-01

This paper describes a current study on severe accidents being sponsored by the Atomic Energy Control Board (AECB) and provides background on other related Canadian work. Scoping calculations are performed in Phase I of the AECB study to establish the relative consequences of several permutations resulting from six postulated initiating events, nine containment states, and a selection of meteorological conditions and health effects mitigating criteria. In Phase II of the study, selected accidents sequences would be analyzed in detail using models suitable for the design features of the Canadian nuclear power reactors

The Thai-Canadian nuclear human resources development linkage project

International Nuclear Information System (INIS)

Sumitra, Tatchai; Chankow, Nares; Bradley, K.; Bereznai, G.

1998-01-01

The Thai-Canadian Nuclear Human Resources Development Linkage Project (the P roject ) was initiated in 1994 in order to develop the engineering and scientific expertise needed for Thailand to decide whether and how the country can best benefit from the establishment of a nuclear power program. The Project was designed to upgrade current academics and people in industry, and to develop an adequate supply of new technical personnel for academic, industry, utility, regulatory and other government institutions. The key Project objectives included the establishment of a Chair in Nuclear Engineering at Chulalongkorn University, the upgrading of the current Masters level curriculum, the establishment of undergraduate and doctorate level curricula, development and delivery of an industrial training program for people in industry and government, exchanges of Thai and Canadian academics and industry experts to establish common research programs and teaching interests, and a public education program that was to test in Thailand some of the techniques that have been successfully used in Canada. (author)

Waste management in Canadian nuclear programs

International Nuclear Information System (INIS)

Dyne, P.J.

1975-08-01

The report describes the wide-ranging program of engineering developments and applications to provide the Canadian nuclear industry with the knowledge and expertise it needs to conduct its waste management program. The need for interim dry storage of spent fuel, and the storage and ultimate disposal of waste from fuel reprocessing are examined. The role of geologic storage in AECL's current waste management program is also considered. (R.A.)

Canadian PV [photovoltaic] commercial activity report for 1989

International Nuclear Information System (INIS)

1992-01-01

The Canadian Photovoltaic Industries Association (CPIA) conducted a survey among 65 Canadian firms involved in the photovoltaic industry and technology to determine the degree of commercial activity. Overall revenue for these firms in 1989 increased nearly 15% to ca $15 million. Actual reported sales of photovoltaic (PV) modules totalled 400 kW for use in Canada and abroad, of which communications applications accounted for ca 40% of these sales. Export sales were significant, with 59% of reported sales sold as packages being exported. Sales of systems within Canada were fairly evenly distributed between Quebec, Ontario, the Prairies, and British Columbia. The private sector share of reported sales was 42% or greater in terms of both dollar or peak wattage. Residential-use and water-pumping segments of the market reported increased activity. Internationally, annual PV module sales in 1989 were reported to be 42 MW peak, a 20% increase from 1988. The USA has the world market share with 36%, followed by Japan at 30%. Survey respondents made suggestions for more equitable tax treatment for PV products, and saw environmental issues as having a major impact on marketing strategies. 27 refs., 11 tabs

Canadian fuel cell commercialization roadmap update : progress of Canada's hydrogen and fuel cell industry

International Nuclear Information System (INIS)

Filbee, S.; Karlsson, T.

2009-01-01

Hydrogen and fuel cells are considered an essential part of future low-carbon energy systems for transportation and stationary power. In recognition of this, Industry Canada has worked in partnership with public and private stakeholders to provide an update to the 2003 Canadian Fuel Cell Commercialization Roadmap to determine infrastructure requirements for near-term markets. The update includes technology and market developments in terms of cost and performance. This presentation included an overview of global hydrogen and fuel cell markets as background and context for the activities of the Canadian industry. Approaches toward commercial viability and mass market success were also discussed along with possible scenarios and processes by which these mass markets could develop. Hydrogen and fuel cell industry priorities were outlined along with recommendations for building a hydrogen infrastructure

The nuclear industry and the NPT: a Canadian view

International Nuclear Information System (INIS)

MacOwen, W.

1987-01-01

The effect of Canada's safeguards policy on Canadian industry and on the conduct of Canada's international nuclear trade is examined. When India exploded a nuclear device in 1974 Canada terminated all nuclear collaboration with India and also insisted that other countries renegotiated existing contracts to include more stringent safeguards. This damaged Canada's trading reputation and its position will have to be rebuilt. It is suggested that international agreement on some practicable and comprehensive rules for international trade in nuclear items should be pursued. (U.K.)

The Independence of the Nuclear Regulator: Notes from the Canadian Experience

International Nuclear Information System (INIS)

MacKenzie, B.

2010-01-01

The firing of Linda Keen as president and chief executive Officer of the Canadian Nuclear Safety Commission provoked considerable debate within Canada and internationally about the independence of the canadian nuclear regulator. ms. Keen was dismissed from her position from her position at the height of the crisis over a world-wide shortage of medical isotopes caused by the shutdown of the research reactor in Chalk river, Ontario. Under the terms of its licence, the reactor was required to have cooling pumps connected to an emergency power supply as a backup in case of a power outage caused by an event such an earthquake. In november 2007, after it was discovered that the pumps were not connected, the reactor was shut down. As panic over the shortage of medical isotopes grew, the government took three extraordinary measures: first, it issued a directive; second, it introduced emergency legislation in Parliament; and finally, it fired Linda Keen as President of the Commission. This paper examines those three measures and whether they constituted an unwarranted interference with the independence of the Canadian nuclear regulator. (N.C.)

The application of nuclear energy to the Canadian chemical process industry

International Nuclear Information System (INIS)

Robertson, R.F.S.

1976-03-01

A study has been made to determine what role nuclear energy, either electrical or thermal, could play in the Canadian chemical process industry. The study was restricted to current-scale CANDU type power reactors. It is concluded that the scale of operation of the chemical industry is rarely large enough to use blocks of electrical power (e) of 500 MW or thermal power (t) of 1500 MW. Thus, with a few predictable exceptions, the role of nuclear energy in the Canadian chemical industry will be as a general thermal/electrical utility supplier, serving a variety of customers in a particular geographic area. This picture would change if nuclear steam generators of 20 to 50 MW(t) become available and are economically competitive. (author)

Proceedings of the 30. Annual Conference of the Canadian Nuclear Association

International Nuclear Information System (INIS)

Burroughs, P.

1990-01-01

The nineteen papers presented at this conference discuss the energy needs and challenges facing the Canadian nuclear industry, the environment and nuclear power, the problems of maintaining and developing industrial capacity, and the challenges of the 1990's. (L.L.)

Canadian Hydrogen Association workshop on building Canadian strength with hydrogen systems. Proceedings

International Nuclear Information System (INIS)

2006-01-01

The Canadian Hydrogen Association workshop on 'Building Canadian Strength with Hydrogen Systems' was held in Montreal, Quebec, Canada on October 19-20, 2006. Over 100 delegates attended the workshop and there were over 50 presentations made. The Canadian Hydrogen Association (CHA) promotes the development of a hydrogen infrastructure and the commercialization of new, efficient and economic methods that accelerate the adoption of hydrogen technologies that will eventually replace fossil-based energy systems to reduce greenhouse gas emissions. This workshop focused on defining the strategic direction of research and development that will define the future of hydrogen related energy developments across Canada. It provided a forum to strengthen the research, development and innovation linkages among government, industry and academia to build Canadian strength with hydrogen systems. The presentations described new technologies and the companies that are making small scale hydrogen and hydrogen powered vehicles. Other topics of discussion included storage issues, hydrogen safety, competition in the hydrogen market, hydrogen fuel cell opportunities, nuclear-based hydrogen production, and environmental impacts

Proceedings of the 32. annual conference of the Canadian Nuclear Association

International Nuclear Information System (INIS)

1992-01-01

The conference proceedings comprise 34 papers, arranged under the following sessions: Plenary; The international CANDU program; Canadian used fuel management program; Public information advocates; Fuel and electricity supply; In which direction should reactors advance?; Canadian advanced nuclear research programs; International cooperation in operations; Safety in design, operation, regulation; Renovation of operating stations; CNS/CNA luncheon addresses. The individual papers have been abstracted separately

The Canadian nuclear fuel waste management program

International Nuclear Information System (INIS)

Dixon, R.S.

1984-12-01

The Canadian Nuclear Fuel Waste Management Program involves research into the storage and transportation of used nuclear fuel, immobilization of fuel waste, and deep geological disposal of the immobilized waste. The program is now in the fourth year of a ten-year generic research and development phase. The objective of this phase of the program is to assess the safety and environmental aspects of the deep underground disposal of immobilized fuel waste in plutonic rock. The objectives of the research for each component of the program and the progress made to the end of 1983 are described in this report

The potential for energy efficiency gains in the Canadian commercial building sector: A stochastic frontier study

International Nuclear Information System (INIS)

Buck, J.; Young, D.

2007-01-01

The achievement of energy efficiency in commercial buildings is a function of the activities undertaken, the technology in place, and the extent to which those technologies are used efficiently. We study the factors that affect efficient energy use in the Canadian commercial sector by applying a stochastic frontier approach to a cross-section of Canadian commercial buildings included in the Commercial and Institutional Building Energy Use Survey (CIBEUS). Structural and climate-control features of the buildings as well as climatic conditions are assumed to determine the location of the frontier, while management-related variables including such factors as ownership type and activities govern whether or not the maximally attainable efficiency along the frontier is achieved. Our results indicate that although, on average, buildings appear to be fairly efficient, certain types of operations are more likely than others to exhibit energy efficiencies that are significantly worse than average. These results, along with those related to the effects of physical characteristics on the stochastic efficiency frontier, suggest that there is scope for focused policy initiatives to increase energy efficiency in this sector

Success in nuclear technology transfer: A Canadian perspective

International Nuclear Information System (INIS)

Lawson, D.S.; Stevens, J.E.S.; Boulton, J.

1986-10-01

Technology transfer has played a significant part in the expansion of nuclear power to many countries of the world. Canada's involvement in nuclear technology transfer spans four decades. The experience gained through technology transfer, initially to Canadian industry and then to other countries in association with the construction of CANDU nuclear power plants, forms a basis from which to assess the factors which contribute to successful technology transfer. A strong commitment from all parties, in terms of both financial and human resources, is essential to success. Detailed planning of both the scope and timing of the technology transfer program is also required together with an assessment of the impact of the introduction of nuclear power on other sectors of the economy. (author)

Developments in the Canadian program for geological disposal of nuclear fuel waste

International Nuclear Information System (INIS)

Allan, C.J.; Nuttall, K.

1996-01-01

The Canadian Nuclear Fuel Waste Management Program is at the end of disposal concept and technology development and is now undergoing a comprehensive environmental review. This paper will review: the history of the Canadian program; the disposal concept and the associated technologies; the program achievements and the lessons learned; and the status of the environmental review. (author)

Commercialization of nuclear power plant decommissioning technology

International Nuclear Information System (INIS)

Williams, D.H.

1983-01-01

The commercialization of nuclear power plant decommissioning is presented as a step in the commercialization of nuclear energy. Opportunities for technology application advances are identified. Utility planning needs are presented

A comparative analysis of managing radioactive waste in the Canadian nuclear and non-nuclear industries

Energy Technology Data Exchange (ETDEWEB)

Batters, S.; Benovich, I.; Gerchikov, M. [AMEC NSS Ltd., Toronto, ON (Canada)

2011-07-01

Management of radioactive waste in nuclear industries in Canada is tightly regulated. The regulated nuclear industries include nuclear power generation, uranium mining and milling, nuclear medicine, radiation research and education and industrial users of nuclear material (e.g. radiography, thickness gauges, etc). In contrast, management of Naturally Occurring Radioactive Material (NORM) waste is not regulated by the Canadian Nuclear Safety Commission (CNSC), with the exception of transport above specified concentrations. Although these are radioactive materials that have always been present in various concentrations in the environment and in the tissues of every living animal, including humans, the hazards of similar quantities of NORM radionuclides are identical to those of the same or other radionuclides from regulated industries. The concentration of NORM in most natural substances is so low that the associated risk is generally regarded as negligible, however higher concentrations may arise as the result of industrial operations such as: oil and gas production, mineral extraction and processing (e.g. phosphate fertilizer production), metal recycling, thermal electric power generation, water treatment facilities. Health Canada has published the Canadian Guidelines for the Management of Naturally Occurring Radioactive Materials (NORM). This paper presents a comparative analysis of the requirements for management of radioactive waste in the regulated nuclear industries and of the guidelines for management of NORM waste. (author)

A comparative analysis of managing radioactive waste in the Canadian nuclear and non-nuclear industries

International Nuclear Information System (INIS)

Batters, S.; Benovich, I.; Gerchikov, M.

2011-01-01

Management of radioactive waste in nuclear industries in Canada is tightly regulated. The regulated nuclear industries include nuclear power generation, uranium mining and milling, nuclear medicine, radiation research and education and industrial users of nuclear material (e.g. radiography, thickness gauges, etc). In contrast, management of Naturally Occurring Radioactive Material (NORM) waste is not regulated by the Canadian Nuclear Safety Commission (CNSC), with the exception of transport above specified concentrations. Although these are radioactive materials that have always been present in various concentrations in the environment and in the tissues of every living animal, including humans, the hazards of similar quantities of NORM radionuclides are identical to those of the same or other radionuclides from regulated industries. The concentration of NORM in most natural substances is so low that the associated risk is generally regarded as negligible, however higher concentrations may arise as the result of industrial operations such as: oil and gas production, mineral extraction and processing (e.g. phosphate fertilizer production), metal recycling, thermal electric power generation, water treatment facilities. Health Canada has published the Canadian Guidelines for the Management of Naturally Occurring Radioactive Materials (NORM). This paper presents a comparative analysis of the requirements for management of radioactive waste in the regulated nuclear industries and of the guidelines for management of NORM waste. (author)

CANDU, an analysis of the Canadian nuclear program. Part I. Technical handbook

Energy Technology Data Exchange (ETDEWEB)

Watters, M

1975-12-01

An excellent compilation is given of facts not easily found on the Canadian nuclear program. Some background physics and radiation biology are explained. The implications of using uranium, plutonium, and thorium as nuclear fuels are discussed. Heavy water production is briefly discussed, as is management of nuclear wastes. Overall, great emphasis is placed on explicating environmental effects and possible hazards of nuclear power.

Nuclear worries of Canadian youth: Replication and extension

International Nuclear Information System (INIS)

Lewis, C.; Goldberg, S.; Parker, K.R.

1989-01-01

A national survey of Canadian adolescents assessed concern, anxiety, and sources of information about the threat of nuclear war. Results indicated few geographical or gender differences in overall levels of concern, although females were more likely to admit fear and anxiety, and students with activist parents showed more concern. Family ranked below all media as a source of information

Commercial nuclear power 1990

International Nuclear Information System (INIS)

1990-01-01

This report presents the status at the end of 1989 and the outlook for commercial nuclear capacity and generation for all countries in the world with free market economies (FME). The report provides documentation of the US nuclear capacity and generation projections through 2030. The long-term projections of US nuclear capacity and generation are provided to the US Department of Energy's (DOE) Office of Civilian Radioactive Waste Management (OCRWM) for use in estimating nuclear waste fund revenues and to aid in planning the disposal of nuclear waste. These projections also support the Energy Information Administration's annual report, Domestic Uranium Mining and Milling Industry: Viability Assessment, and are provided to the Organization for Economic Cooperation and Development. The foreign nuclear capacity projections are used by the DOE uranium enrichment program in assessing potential markets for future enrichment contracts. The two major sections of this report discuss US and foreign commercial nuclear power. The US section (Chapters 2 and 3) deals with (1) the status of nuclear power as of the end of 1989; (2) projections of nuclear capacity and generation at 5-year intervals from 1990 through 2030; and (3) a discussion of institutional and technical issues that affect nuclear power. The nuclear capacity projections are discussed in terms of two projection periods: the intermediate term through 2010 and the long term through 2030. A No New Orders case is presented for each of the projection periods, as well as Lower Reference and Upper Reference cases. 5 figs., 30 tabs

Commercial nuclear power 1990

Energy Technology Data Exchange (ETDEWEB)

1990-09-28

This report presents the status at the end of 1989 and the outlook for commercial nuclear capacity and generation for all countries in the world with free market economies (FME). The report provides documentation of the US nuclear capacity and generation projections through 2030. The long-term projections of US nuclear capacity and generation are provided to the US Department of Energy's (DOE) Office of Civilian Radioactive Waste Management (OCRWM) for use in estimating nuclear waste fund revenues and to aid in planning the disposal of nuclear waste. These projections also support the Energy Information Administration's annual report, Domestic Uranium Mining and Milling Industry: Viability Assessment, and are provided to the Organization for Economic Cooperation and Development. The foreign nuclear capacity projections are used by the DOE uranium enrichment program in assessing potential markets for future enrichment contracts. The two major sections of this report discuss US and foreign commercial nuclear power. The US section (Chapters 2 and 3) deals with (1) the status of nuclear power as of the end of 1989; (2) projections of nuclear capacity and generation at 5-year intervals from 1990 through 2030; and (3) a discussion of institutional and technical issues that affect nuclear power. The nuclear capacity projections are discussed in terms of two projection periods: the intermediate term through 2010 and the long term through 2030. A No New Orders case is presented for each of the projection periods, as well as Lower Reference and Upper Reference cases. 5 figs., 30 tabs.

Protest: The Canadian pulse

International Nuclear Information System (INIS)

Lott, J.E.

1979-01-01

This popularly written article compares Canadian attitudes to protests against nuclear power to those in the United States. Canadian protesters are more peaceful, expressing their opinions within the law. The article describes the main anti-nuclear groups in Canada and presents the results of public opinion surveys of Canadians on the use of nuclear power for generating electricity. (TI)

Commercial nuclear power 1989

International Nuclear Information System (INIS)

1989-01-01

This report presents historical data on commercial nuclear power in the United States, with projections of domestic nuclear capacity and generation through the year 2020. The report also gives country-specific projections of nuclear capacity and generation through the year 2010 for other countries in the world outside centrally planned economic areas (WOCA). Information is also presented regarding operable reactors and those under construction in countries with centrally planned economies. 39 tabs

Canadian development program for off-gas management in nuclear facilities

International Nuclear Information System (INIS)

Sridhar, T.S.

1983-01-01

The Canadian program for the development and evaluation of processes and technology for the separation and containment of radioactive species in off-gases is directed towards the following specific aspects: 1) assessment of available treatment technology and evaluation of future clean-up requirements; 2) development and engineering evaluation, under realistic conditions, of promising new processes that would be inherently simpler and safer; and 3) specification of off-gas emission control systems for future nuclear facilities based on the most favourable technology. The program is being carried out by Atomic Energy of Canada Limited in collaboration with the electrical utility, Ontario Hydro, and selected Canadian universities. A brief description is presented of methods for removing tritium and carbon-14 from the moderator systems of CANDU power reactors, methods for removing iodine from the off-gases of a molybdenum-99 production facility at the Chalk River Nuclear Laboratories, and procedures for monitoring the off-gas effluent composition in the Thorium Fuel Reprocessing Experiment (TFRE) facility at the Whiteshell Nuclear Research Establishment

Status of the Canadian nuclear fuel waste management program

International Nuclear Information System (INIS)

Allan, C.J.; Stephens, M.E.

1992-01-01

The Canadian Concept for the permanent disposal of nuclear fuel waste has been developed extensively over the past several years, and is now well-advanced. The Concept, which involves the construction of a waste vault 500 to 1000 metres deep in plutonic rock located in the Canadian Precambrian Shield, is supported by an R ampersand D program with the following objectives: (1) to develop and demonstrate technology to site, design, build and operate a disposal facility; (2) to develop and demonstrate a methodology to evaluate the performance of the disposal system; and (3) to demonstrate that sites are likely to exist in the Canadian Precambrian Shield that would meet the regulatory requirements. A combination of engineered and natural barriers will be used to ensure that the vault design will meet rigorous safety standards. Experimental work is being carried out to elucidate all the important phenomena associated with the safety of the vault, including the performance of engineered barriers, natural geological barriers, and the biosphere

Canadian seismic agreement

International Nuclear Information System (INIS)

Wetmiller, R.J.; Lyons, J.A.; Shannon, W.E.; Munro, P.S.; Thomas, J.T.; Andrew, M.D.; Lamontagne, M.; Wong, C.; Anglin, F.M.; Plouffe, M.; Lapointe, S.P.; Adams, J.; Drysdale, J.A.

1990-04-01

This is the twenty-first progress report under the agreement entitled Canadian Seismic Agreement between the US Nuclear Regulatory Commission (NRC) and the Canadian Commercial Corporation. Activities undertaken by the Geophysics Division of the Geological Survey of Canada (GD/GSC) during the period from July 01, 1988 to June 30, 1989 and supported in part by the NRC agreement are described below under four headings; Eastern Canada Telemetred Network and local network developments, Datalab developments, strong motion network developments and earthquake activity. In this time period eastern Canada experienced its largest earthquake in over 50 years. This earthquake, which has been christened the Saguenay earthquake, has provided a wealth of new data pertinent to earthquake engineering studies in eastern North America and is the subject of many continuing studies, which are presently being carried out at GD and elsewhere. 41 refs., 21 figs., 7 tabs

Papers presented by A.E.C.L. to the International Conference of the Canadian Nuclear Association

International Nuclear Information System (INIS)

1964-06-01

The International Conference of the Canadian Nuclear Association was held in Toronto, Ontario, Canada on May 25-27, 1964. There were six papers presented by Atomic Energy of Canada Limited. The titles were: I. Canada - A Nuclear Power Plant Supplier, by J.L. Gray; II. Nuclear Power Development in Canada and Other Countries, by W.B. Lewis; III. The Development and Some Applications of Cobalt-60 Irradiators, by R.F. Errington; IV. The Definition and Achievement of Development Targets for the Canadian Power Reactor Program, by A.J. Mooradian; V. Recent Applications of Tracers in the Physical Sciences in Canada, by R.H. Betts and J.A. Davies; and, VI. Economic Comparison of Oyster Creek, Nine Mile Point and CANDU-type Stations under Canadian Conditions, by G.A. Pon and R.L. Beck.

The Canadian nuclear fuel waste management program

International Nuclear Information System (INIS)

Rummery, T.E.; Rosinger, E.L.J.

1984-12-01

The Canadian Nuclear Fuel Waste Management Program is in the fourth year of a ten-year generic research and development phase. The objective of this phase of the program is to assess the basic safety and environmental aspects of the concept of isolating immobilized fuel waste by deep underground disposal in plutonic rock. The major scientific and engineering components of the program, namely immobilization studies, geoscience research, and environmental and safety assessment, are described. Program funding, scheduling and associated external review processes are briefly outlined

Learning from elsewhere (problems at US and Canadian nuclear power plants)

International Nuclear Information System (INIS)

Horgan, J.

1984-01-01

This article examines a series of technical and managerial problems that have struck US and Canadian nuclear power plants since 1979. Topics considered include the failure of automatic reactor trip components; ruptures, leaks, and corrosion in steam-generator tubes; pipe cracks in boiling-water reactors; leaks in pressure tubes of Canadian heavy-water reactors; the unreliability of emergency power sources for safety systems; mistakes by operators and other plant personnel; the lack of acceptable emergency-preparedness plans; and poor quality control at construction projects. Most of the discussed problems have solutions, either developed explicitly by a utility most affected by the problem or demonstrated implicitly by a utility that has avoided the problem. It is shown how incidents at sites other than Three Mile Island have expanded the nuclear knowledge base and may help contribute to the solutions of new and older problems

Engineers and scientists in the Canadian nuclear industry 1992-2007

International Nuclear Information System (INIS)

Stoll, P.

1993-01-01

The study utilized a survey of large employers to identify the current level of employment of engineers and scientists in applications of nuclear technology. The labour market implications of three possible alternative future evolutionary paths over the 1992-2007 period were assessed to determine the adequacy of the available labour force to maintain a competitive Canadian presence in domestic and international markets. It is shown that under the nuclear phaseout and no-growth scenarios, the requirements for nuclear experts decline; under the growth scenario, requirements increase, although not at a rate which cannot be met from domestic sources. 2 tabs., 7 refs

Cosmic radiation exposure on Canadian-based commercial airline routes

Energy Technology Data Exchange (ETDEWEB)

Lewis, B.J.; Tume, P.; Bennett, L.G.I.; Pierre, M.; Green, A.R

1998-07-01

As a result of the recent recommendations of the ICRP-60 and in anticipation of possible regulation on occupational exposure of commercial aircrew, a two-phase investigation was carried out over a one-year period to determine the total dose equivalent on representative Canadian-based flight routes. In the first phase of the study, dedicated scientific flights on a Northern round-trip route between Ottawa and Resolute Bay provided the opportunity to characterize the complex mixed-radiation field, and to intercompare various instrumentation using both a conventional suite of powered detectors and passive dosimetry. In the second phase, volunteer aircrew carried (passive) neutron bubble detectors during their routine flight duties. From these measurements, the total dose equivalent was derived for a given route with a knowledge of the neutron fraction as determined from the scientific flights and computer code (CART-LF) calculations. This study has yielded an extensive database of over 3100 measurements providing the total dose equivalent for 385 different routes. By folding in flight frequency information and the accumulated flight hours, the annual occupational exposures of 26 flight crew have been determined. This study has indicated that most Canadian-based domestic and international aircrew will exceed the proposed annual ICRP-60 public limit of 1 mSv y{sup -1} but will be well below the occupational limit of 20 mSv y{sup -1}. (author)

Cosmic Radiation Exposure on Canadian-Based Commercial Airline Routes

Energy Technology Data Exchange (ETDEWEB)

Lewis, B.J.; Tume, P.; Bennett, L.G.I.; Pierre, M.; Green, A.R.; Cousins, T.; Hoffarth, B.E.; Jones, T.A.; Brisson, J.R

1999-07-01

As a result of the recent recommendations of ICRP 60 and in anticipation of possible regulation on occupational exposure of commercial aircrew, a two-part investigation was carried out over a one-year period to determine the total dose equivalent on representative Canadian-based flight routes. As part of the study, a dedicated scientific measurement flight (using both a conventional suite of powered detectors and passive dosimetry) was used to characterise the complex mixed radiation field and to intercompare the various instrumentation. In the other part of the study, volunteer aircrew carried (passive) neutron bubble detectors during their routine flight duties. From these measurements, the total dose equivalent was derived for a given route with a knowledge of the neutron fraction as determined from the scientific flight and computer code (CARI-LF) calculations. This investigation has yielded an extensive database of over 3100 measurements providing the total dose equivalent for 385 different routes. By folding in flight frequency information and the accumulated flight hours, the annual occupational exposures of 26 flight crew have also been determined. This study has indicated that most Canadian-based domestic and international aircrew will exceed the proposed annual ICRP 60 public limit of 1 mSv.y{sup -1}, but will be below the occupational limit of 20 mSv.y{sup -1}. (author)

Second interim assessment of the Canadian concept for nuclear fuel waste disposal. Volume 2

International Nuclear Information System (INIS)

Gillespie, P.A.; Wuschke, D.M.; Guvanasen, V.M.; Mehta, K.K.; McConnell, D.B.; Tamm, J.A.; Lyon, R.B.

1985-12-01

The nuclear fuel waste disposal concept chosen for development and assessment in Canada involves the burial of corrosion-resistant containers of waste in a vault located deep in plutonic rock in the Canadian Shield. As the concept and the assessment tools are developed, periodic assessments are performed to permit evaluatin of the methodology and provide feedback to those developing the concept. The ultimate goal of these assessments is to predict what impact the disposal system would have if the concept were implemented. The second assessment was performed in 1984 and is documented in Second Interim Assessment of the Canadian Concept for Nuclear Fuel Waste Disposal - Volumes 1 to 4. This volume, entitled Background, discusses Canadian nuclear fuel wastes and the desirable features of a waste disposal method. It outlines several disposal options being considered by a number of countries, including the option chosen for development and assessment in Canada. The reference disposal systems assumed for the second assessment are described, and the approach used for concept assessment is discussed briefly. 79 refs

The Sylvia Fedoruk Canadian Centre for Nuclear Innovation: advancing knowledge through partnerships

Energy Technology Data Exchange (ETDEWEB)

Alexander, N.; Root, J.H., E-mail: neil.alexander@usask.ca, E-mail: john.root@usask.ca [Sylvia Fedoruk Canadian Centre for Nuclear Innovation, Saskatoon, SK (Canada); Chad, K., E-mail: karen.chad@usask.ca [Univ. of Saskatchewan, Saskatoon, SK (Canada); Bereznai, G., E-mail: george.bereznai@uoit.ca [Univ. of Ontario Inst. of Tech., Faculty of Energy Systems and Nuclear Science, Oshawa, ON (Canada); Dalzell, M.T.J., E-mail: matthew.dalzell@usask.ca [Sylvia Fedoruk Canadian Centre for Nuclear Innovation, Saskatoon, SK (Canada)

2014-07-01

The vision of the Sylvia Fedoruk Canadian Centre for Nuclear Innovation is to place the Canadian province of Saskatchewan among global leaders in nuclear research, development and training through partnerships with industry and academia for economic and social benefit. Saskatchewan is one of the world's largest producers of uranium and home to pioneering research in nuclear medicine, most notably the development of cobalt-60 teletherapy. The Fedoruk Centre is striving to build on this legacy through the attainment of four strategic goals: (1) building nuclear expertise and capacity through the support to academic programs and research projects in partnership with industry, academic institutions and research organizations in nuclear medicine, materials research, energy and the environment; (2) enhancing innovation in partnership with the research community and industry; (3) engaging communities and increasing understanding of risks, benefits and potential impacts of nuclear technologies; and (4) ensuring the sustainability and accountability of the Centre and its resources. The Fedoruk Centre's mandate includes the stewardship of select nuclear facilities, the first being a 24 MeV cyclotron and nuclear substances laboratory as a resource for the development of novel imaging agents, training and production of radioisotopes for clinical diagnoses. By attracting new research leadership in the nuclear domain, developing networks of expertise, training highly-qualified personnel in nuclear disciplines, stimulating industrial partnerships, and creating conditions for fact-based conversation regarding nuclear issues, the Fedoruk Centre is working to establish a research and innovation capacity to support a vibrant nuclear sector in Saskatchewan. (author)

The Sylvia Fedoruk Canadian Centre for Nuclear Innovation: advancing knowledge through partnerships

International Nuclear Information System (INIS)

Alexander, N.; Root, J.H.; Chad, K.; Bereznai, G.; Dalzell, M.T.J.

2014-01-01

The vision of the Sylvia Fedoruk Canadian Centre for Nuclear Innovation is to place the Canadian province of Saskatchewan among global leaders in nuclear research, development and training through partnerships with industry and academia for economic and social benefit. Saskatchewan is one of the world's largest producers of uranium and home to pioneering research in nuclear medicine, most notably the development of cobalt-60 teletherapy. The Fedoruk Centre is striving to build on this legacy through the attainment of four strategic goals: (1) building nuclear expertise and capacity through the support to academic programs and research projects in partnership with industry, academic institutions and research organizations in nuclear medicine, materials research, energy and the environment; (2) enhancing innovation in partnership with the research community and industry; (3) engaging communities and increasing understanding of risks, benefits and potential impacts of nuclear technologies; and (4) ensuring the sustainability and accountability of the Centre and its resources. The Fedoruk Centre's mandate includes the stewardship of select nuclear facilities, the first being a 24 MeV cyclotron and nuclear substances laboratory as a resource for the development of novel imaging agents, training and production of radioisotopes for clinical diagnoses. By attracting new research leadership in the nuclear domain, developing networks of expertise, training highly-qualified personnel in nuclear disciplines, stimulating industrial partnerships, and creating conditions for fact-based conversation regarding nuclear issues, the Fedoruk Centre is working to establish a research and innovation capacity to support a vibrant nuclear sector in Saskatchewan. (author)

Guide to the Canadian nuclear fuel waste management program. 2.ed

International Nuclear Information System (INIS)

Rosinger, E.L.J.; Lyon, R.B.; Gillespie, P.; Tamm, J.

1983-02-01

This document describes the administrative structure and major research and development components of the Canadian Nuclear Fuel Waste Management Program. It outlines the participating organizations, summarizes the program statistics, and describes the international cooperation and external review aspects of the program

Proceedings of the 11th Annual Conference of the Canadian Nuclear Society

International Nuclear Information System (INIS)

Rouben, B.

1990-01-01

This volume contains the proceedings of the thirteen technical sessions at the 11. annual conference of the Canadian Nuclear Society. The 68 papers presented at this conference cover the areas of programmes and issues for the 90's; thermalhydraulics; reactor physics and fuel management; nuclear safety; small reactors; fuel behaviour; energy production and the environment; computer applications; nuclear systems; fusion; reactor decommissioning, irradiated fuel and materials handling; and reactor components, (L.L.)

Government intervention in the Canadian nuclear industry

Energy Technology Data Exchange (ETDEWEB)

Doern, G B [Carleton Univ., Ottawa, Ontario (Canada). School of Public Administration

1980-01-01

Several facets of government intervention in the Canadian nuclear industry are examined by reviewing the general historical evolution of intervention since the Second World War and by a more detailed analysis of three case studies. The case studies are the public sector - private sector content of the initial CANDU reactor program in the 1950's, the regulation of the health and safety of uranium miners in the late 1960's and early 1970's, and the Ontario Hydro decision in 1978 to enter into longer-term (40 year) contracts for uranium for its power reactors.

Safety improvements at Canadian nuclear power plants in the aftermath of Fukushima accident

International Nuclear Information System (INIS)

Rzentkowski, G.; Khouaja, H.

2014-01-01

This paper describes the safety review of operating nuclear power plants undertaken by the Canadian Nuclear Safety Commission in light of the March 11, 2011 accident at the Fukushima Daiichi Nuclear Power Plants (NPPs). The review confirmed that the Canadian NPPs are robust and have a strong design relying on multiple layers of defence to protect the public from credible external events. Nevertheless, in the spirit of continuous safety improvements, the review identified a number of recommendations to further strengthen reactor defence-in-depth in preventing and mitigating the consequences of beyond design basis accidents, enhance onsite and offsite emergency response, and improve the CNSC regulatory framework. Progress achieved to date, in implementing these measures, is described in this paper along with a summary of safety benefits for each level of the reactor defence-in-depth. (author)

Safety improvements at Canadian nuclear power plants in the aftermath of Fukushima accident

Energy Technology Data Exchange (ETDEWEB)

Rzentkowski, G.; Khouaja, H. [Canadian Nuclear Safety Commission, Ottawa, ON (Canada)

2014-07-01

This paper describes the safety review of operating nuclear power plants undertaken by the Canadian Nuclear Safety Commission in light of the March 11, 2011 accident at the Fukushima Daiichi Nuclear Power Plants (NPPs). The review confirmed that the Canadian NPPs are robust and have a strong design relying on multiple layers of defence to protect the public from credible external events. Nevertheless, in the spirit of continuous safety improvements, the review identified a number of recommendations to further strengthen reactor defence-in-depth in preventing and mitigating the consequences of beyond design basis accidents, enhance onsite and offsite emergency response, and improve the CNSC regulatory framework. Progress achieved to date, in implementing these measures, is described in this paper along with a summary of safety benefits for each level of the reactor defence-in-depth. (author)

Regulatory oversight strategy for chemistry program at Canadian nuclear power plants

International Nuclear Information System (INIS)

Kameswaran; Ram

2012-09-01

Chemistry program is one of the essential programs for the safe operation of a nuclear power plant. It helps to ensure the necessary integrity, reliability and availability of plant structures, systems and components important to safety. Additionally, the program plays an important role in asset preservation, limiting radiation exposure and environmental protection. A good chemistry program will minimize corrosion of materials, reduce activation products, minimize of the buildup of radioactive material leading to occupational radiation exposure and it helps limit the release of chemicals and radioactive materials to the environment. The legal basis for the chemistry oversight at Canadian NPPs is established by the Nuclear Safety and Control Act and its associated regulations. It draws on the Canadian Nuclear Safety Commission's regulatory framework and NPP operating license conditions that include applicable standards such as CAN/CSA N286-05 Management System Requirements for Nuclear Power Plants. This paper focuses on the regulatory oversight strategy used in Canada to assess the performance of chemistry program at the nuclear power plants (NPPs) licensed by CNSC. The strategy consists of a combination of inspection and performance monitoring activities. The activities are further supported from information gathered through staff inspections of cross-cutting areas such as maintenance, corrective-action follow-ups, event reviews and safety related performance indicators. (authors)

Canadian Experience in Nuclear Power Technology Transfer

International Nuclear Information System (INIS)

Boulton, J.

1987-01-01

Technology transfer has and will continue to play a major role in the development of nuclear power programs. From the early beginnings of the development of the peaceful uses of nuclear power by just a few nations in the mid-1940s there has been a considerable transfer of technology and today 34 countries have nuclear programs in various stages of development. Indeed, some of the major nuclear vendors achieves their present position through a process of technology transfer and subsequent development. Canada, one of the early leaders in the development of nuclear power, has experience with a wide range of programs bout within its own borders and with other countries. This paper briefly describes this experience and the lessons learned from Canada's involvement in the transfer of nuclear power technology. Nuclear technology is complex and diverse and yet it can be assimilated by a nation given a fire commitment of both suppliers and recipients of technology to achieve success. Canada has reaped large benefits from its nuclear program and we believe this has been instrumentally linked to the sharing of goals and opportunity for participation over extended periods of time by many interests within the Canadian infrastructure. While Canada has accumulated considerable expertise in nuclear technology transfer, we believe there is still much for US to learn. Achieving proficiency in any of the many kinds of nuclear related technologies will place a heavy burden on the financial and human resources of a nation. Care must be taken to plan carefully the total criteria which will assure national benefits in industrial and economic development. Above all, effective transfer of nuclear technology requires a long term commitment by both parties

AECL's strategy for decommissioning Canadian nuclear facilities

International Nuclear Information System (INIS)

Joubert, W.M.; Pare, F.E.; Pratapagiri, G.

1992-01-01

The Canadian policy on decommissioning of nuclear facilities as defined in the Atomic Energy Control Act and Regulations is administered by the Atomic Energy Control Board (AECB), a Federal Government agency. It requires that these facilities be decommissioned according to approved plans which are to be developed by the owner of the nuclear facility during its early stages of design and to be refined during its operating life. In this regulatory environment, Atomic Energy of Canada (AECL) has developed a decommissioning strategy for power stations which consists of three distinctive phases. After presenting AECL's decommissioning philosophy, its foundations are explained and it is described how it has and soon will be applied to various facilities. A brief summary is provided of the experience gained up to date on the implementation of this strategy. (author) 3 figs.; 1 tab

Canadian public and leadership attitudes to nuclear power

International Nuclear Information System (INIS)

Dobson, J.K.

1976-01-01

Surveys of the Canadian public and leadership were carried out to determine levels of knowledge, perceptions and attitudes toward the use of nuclear power in Canada. The public sample included population over 18 years broken down by region, age, sex and education. The leadership study sampled businessmen, politicians, civil servants, academics and environmentalists. Only 56 % of the public indicated a knowledge of the use of nuclear power: 68 % were in favour, and of these, 39 % were unsure of its safety. Environmentalits were the most knowledgealbe of all the leadership groups, with academics second, and the remaining groups having low levels of information. Fear-producing aspects defined by the survey should be used as the basis for providing information. All leadership groups except environmentalists favoured nuclear power development. Leadership groups identified the same disadvantages as the public (radiation, waste management, pollution and explosions) but added cost. (J.T.A.)

Commercial nuclear power: Assuring safety for the future

International Nuclear Information System (INIS)

Ramsey, C.B.; Modarres, M.

1998-03-01

This timely book offers insights into the benefits of nuclear power as well as the technological and environmental challenges facing the nuclear industry. Containing the results of worldwide scientific studies and industrial site visits, the book represents a timely focus on the applications of commercial nuclear power, the potential benefits to be gained from contained nuclear use, the environmental risks of nuclear power, and the prevention of nuclear accidents.This timely book offers insights into the benefits of nuclear power as well as the technological and environmental challenges facing the nuclear industry. Containing the results of worldwide scientific studies and industrial site visits, the book represents a timely focus on the applications of commercial nuclear power, the potential benefits to be gained from contained nuclear use, the environmental risks of nuclear power, and the prevention of nuclear accidents

Joint submission of the Canadian Nuclear Association and the Organization of CANDU Industries to the Ontario Nuclear Safety Review

International Nuclear Information System (INIS)

1987-08-01

The manufacturing company members of the Canadian Nuclear Association and the Organization of CANDU Industries are proud to have played their part in the development of the peaceful application of nuclear technology in Ontario, and the achievement of the very real benefits discussed in this paper, which greatly outweigh the hypothetical risks

Government intervention in the Canadian nuclear industry

International Nuclear Information System (INIS)

Doern, G.B.

1980-01-01

Several facets of government intervention in the Canadian nuclear industry are examined by reviewing the general historical evolution of intervention since the Second World War and by a more detailed analysis of three case studies. The case studies are the public sector - private sector content of the initial CANDU reactor program in the 1950's, the regulation of the health and safety of uranium miners in the late 1960's and early 1970's, and the Ontario Hydro decision in 1978 to enter into longer-term (40 year) contracts for uranium for its power reactors. (auth)

Canadian nuclear power principles for beyond design basis events - supporting rationale

International Nuclear Information System (INIS)

Elliott, M.; Newman, G.; Bhaloo, A.

2014-01-01

The development of the following principles and their rationale began during a special Chief Nuclear Engineers forum held on March 25th, 2013 in Toronto. These principles are intended to provide guidance to the Canadian Nuclear Power Industry in developing responses to the lessons learned from the Fukushima event of March 2011. These principles were accepted and signed off by the Chief Nuclear Officers of each of the three utilities in August 2013 and were presented to the CNSC at a public hearing on August 21, 2013. This document provides the underlying rationale for the principles. (author)

Canadian nuclear power principles for beyond design basis events - supporting rationale

Energy Technology Data Exchange (ETDEWEB)

Elliott, M. [OPG Nuclear, Ontario (Canada); Newman, G. [Bruce Power, Ontario (Canada); Bhaloo, A. [New Brunswick Power, New Brunswick (Canada)

2014-09-15

The development of the following principles and their rationale began during a special Chief Nuclear Engineers forum held on March 25th, 2013 in Toronto. These principles are intended to provide guidance to the Canadian Nuclear Power Industry in developing responses to the lessons learned from the Fukushima event of March 2011. These principles were accepted and signed off by the Chief Nuclear Officers of each of the three utilities in August 2013 and were presented to the CNSC at a public hearing on August 21, 2013. This document provides the underlying rationale for the principles. (author)

Canadian nuclear power principles for beyond design basis events - supporting rationale

Energy Technology Data Exchange (ETDEWEB)

Elliott, M. [Ontario Power Generation Nuclear, Pickering, ON (Canada); Newman, G. [Bruce Power, Tiverton, ON (Canada); Bhaloo, A. [New Brunswick Power, Fredericton, NB (Canada)

2014-07-01

The development of the following principles and their rationale began during a special Chief Nuclear Engineers forum held on March 25th, 2013 in Toronto. These principles are intended to provide guidance to the Canadian Nuclear Power Industry in developing responses to the lessons learned from the Fukushima event of March 2011. These principles were accepted and signed off by the Chief Nuclear Officers of each of the three utilities in August 2013 and were presented to the CNSC at a public hearing on August 21, 2013. This document provides the underlying rationale for the principles. (author)

Nuclear Analytical Techniques for Commercial Applications in China

International Nuclear Information System (INIS)

Chai, Z.; Zhang, Z.; Feng, S.; Yang, J.; Ouyang, H.; Feng, X.; Mao, X.

2013-01-01

Since the establishment of the first Chinese nuclear reactor and accelerator in 1958, the nuclear analytical techniques (NATs) in China have dramatically developed in past half century. Nowadays 10 research nuclear reactors and over 100 small accelerators are available in China. Roughly, about 50 % of the machine time is applied for commercial purpose at the moment. The versatile nuclear analytical methods, mainly NAA, PIXE, XRF, etc., in China have been and are being applied widely and extensively in the following three fields: scientific, training, and commercial. This paper will briefly describe the past experience and present status about NATs for commercial applications. Some practical examples to demonstrate the role of NATs in this aspect will be given as well. Basically, the NATs used for the commercial applications in China can be divided into two types, i.e. off-line and on-line. The former mainly includes instrumental neutron activation analysis (INAA) for compositional determination, particle induced X-ray emission (PIXE) also for compositional analysis, accelerator-based mass-spectrometry (AMS) for analysis of C-14, Be-7, Cl-36 and other long-lived radioactive nuclides, solid state nuclear track detector

Technology transfer from Canadian nuclear laboratories

International Nuclear Information System (INIS)

MacDonald, R.D.; Evans, W.; MacEwan, J.R.; Melvin, J.G.

1985-09-01

Canada has developed a unique nuclear power system, the CANDU reactor. AECL - Research Company (AECL-RC) has played a key role in the CANDU program by supplying its technology to the reactor's designers, constructors and operators. This technology was transferred from our laboratories to our sister AECL companies and to domestic industries and utilities. As CANDUs were built overseas, AECL-RC made its technology available to foreign utilities and agencies. Recently the company has embarked on a new transfer program, commercial R and D for nuclear and non-nuclear customers. During the years of CANDU development, AECL-RC has acquired the skills and technology that are especially valuable to other countries embarking on their own nuclear programs. This report describes AECL-RC's thirty years' experience with the transfer of technology

Canadian photovoltaic commercial activity review

International Nuclear Information System (INIS)

Adkinson, D.J.; Royer, J.

1992-01-01

A survey was performed on the activities of the Canadian photovoltaic (PV) industry during 1988 for the three years of 1985-1987, and a similar survey was carried out in 1989. The findings of the latest survey are reported and compared with the previous survey. Market growth rates in the order of 15%/y and greater in the international market are reflected in the Canadian scene with an estimated 1989 activity in the range of $15 million. Details are presented of the distribution of firms across Canada, the distribution of annual sales activities by application, annual PV module sales in Europe and globally, breakdown of PV module powers produced by the United States, Japan, Europe, and others, breakdown of reported sales in Canada by source/destination, regional distribution of sales for installation in Canada, distribution by purchaser type for sales of PV equipment in Canada, and a summary of sales classified by application. In 1989 for the first time global demand for PV modules exceeded supply. 8 refs., 9 tabs

Analysis directory of Canadian commercial coals, Supplement No. 3. [Government sampling and analysis listed by mine and province

Energy Technology Data Exchange (ETDEWEB)

Tibbetts, T. E.; Montgomery, W. J.; Faurschou, D. K.

1978-12-15

Chemical and physical analyses of thermal and metallurgical coals currently produced by mines in Nova Scotia, New Brunswick, Saskatchewan, Alberta and British Columbia are reported. The evaluations are part of a continuing CANMET project to monitor Canadian commercial coals to assist marketing and resource assessment activities. The coals were sampled by personnel of the Energy Research Labs. Most of the sampling was done during 1976 and 1977. Generally, the samples represent production on a specific day of both mine run and prepared coals sampled independently by CANMET staff at operating mines, coal washeries and delivery points. Coals are identified by the operator and name of mine, seam coalfield, and location. Information is arranged by province and is intended to provide a ready indication of the quality of commercially available Canadian coals. As such, this document complements the coal industry statistics available in other federal and provincial reports.

Radiological environmental monitoring programs at Canadian nuclear facilities - a practical model for follow-up activities under the Canadian Environmental Assessment Act

International Nuclear Information System (INIS)

Tamm, J.A.; Zach, R.

2000-01-01

Under the Canadian Environmental Assessment Act (the Act), a federal authority, if it considers it appropriate, is to design a follow-up program for a project undergoing a federal environmental assessment and arrange for implementation of that program. Under the Act a follow-up program means a set of activities for verifying the accuracy of the environmental assessment (EA) of a project and for determining the effectiveness of any measures taken to mitigate any adverse environmental effects resulting from the project. The Act currently does not include regulations, guidelines, standards or procedures regarding the design, content and implementation requirements for follow-up programs (Canadian Environmental Assessment Agency [the Agency] 1999). Uncertainties also exist regarding the roles and responsibilities in designing, implementing, enforcing and auditing such activities. The Agency is presently specifying appropriate activities to address these issues. This paper considers the existing radiological environmental monitoring programs at nuclear facilities. Such programs consist of two types of monitoring-radioactivity releases from the facility via liquid and gaseous waste streams, and radioactivity in the environment at large, beyond the facility's immediate location. Such programs have been developed by AECL, Canadian nuclear utilities and uranium mining companies. Our analysis show that these programs can provide a good model for follow-up programs under the Act. (author)

Status of the Canadian Nuclear Fuel Waste Management Program

International Nuclear Information System (INIS)

Lyon, R.B.

1985-10-01

The Canadian Nuclear Fuel Waste Management Program is in the fifth year of a ten-year generic research and development phase. The major objective of this phase of the program is to assess the basic safety and environmental aspects of the concept of isolating immobilized fuel waste by deep underground disposal in plutonic rock. The major scientific and engineering components of the program, namely immobilization studies, geoscience research, and environmental and safety assessment, are well established

Organizing the Canadian nuclear industry to meet the challenge

International Nuclear Information System (INIS)

Lortie, Pierre.

1983-06-01

The CANDU reactor is struggling for a share of the dwindling reactor market against formidable and well-established competition. The Canadian nuclear industry has historically depended upon two crown corporations, Atomic Energy of Canada Ltd. and Ontario Hydro, which have taken the lead in designing and engineering the reactor. Crown corporations are not notably successful in marketing, however, and the time has come for the industry to organize itself in preparation for an aggressive export drive

Proceedings of the Canadian Nuclear Association 28. annual conference held in Winnipeg, Manitoba, June 12-15, 1988

International Nuclear Information System (INIS)

1988-01-01

The proceedings of the 28. CNA (Canadian Nuclear Association) conference contain 28 papers under the following headings: power reactors; fuel cycles; nuclear power and public understanding; future trends; and, applications of nuclear technology. CANDU reactors are emphasized. The individual papers have been abstracted separately

Second interim assessment of the Canadian concept for nuclear fuel waste disposal. Volume 1

International Nuclear Information System (INIS)

Wuschke, D.M.; Gillespie, P.A.; Main, D.E.

1985-07-01

The nuclear fuel waste disposal concept chosen for development and assessment in Canada involves the isolation of corrosion-resistant containers of waste in a vault located deep in plutonic rock. As the concept and the assessment tools are developed, periodic assessments are performed to permit evaluation of the methodology and provide feedback to those developing the concept. The ultimate goal of these assessments is to predict what impact the disposal system would have on man and the environment if the concept were implemented. The second assessment was performed in 1984 and is documented in the Second Interim assessment of the Canadian Concept for Nuclear Fuel Waste Disposal Volumes 1 to 4. This volume, entitled Summary, is a condensation of Volumes 2, 3 and 4. It briefly describes the Canadian nuclear fuel waste disposal concept, and the methods and results of the second interim pre-closure and post-closure assessments of that concept. 46 refs

Nuclear at Niagara. 32nd Annual Canadian Nuclear Society conference and 35th CNS/CNA student conference

International Nuclear Information System (INIS)

2011-01-01

The 32nd Annual Canadian Nuclear Society Conference and 35th CNS/CNA Student Conference was held in Niagara Falls, Ontario, Canada on June 5-8, 2011. The theme of the conference, 'Nuclear at Niagara', brought together scientists, engineers, technologists, senior management, government officials, and students interested in all aspects of nuclear science and technology and its applications, including nuclear power generation, fuel production, uranium mining and refining, management of radioactive wastes and used fuel. Other topics include medical and industrial uses of radionuclides, occupational and environmental radiation protection, the science and technology of nuclear fusion, and associated activities in research and development. and applications of energy from the atom. The central objective of this conference was to exchange views on how nuclear science and technology can best serve the needs of humanity, now and in the future. Over 400 delegates from across Canada and other nuclear countries were in attendance.

An overview of heat exchanger technology in the Canadian nuclear program

International Nuclear Information System (INIS)

Carlucci, L.N.; Dalrymple, D.G.; Ko, P.L.; Pathania, R.; Pettigrew, M.I.; Scott, D.A.

1981-06-01

This paper provides an overview of the Canadian approach to the reliability and serviceability of heat exchange equipment used in nuclear power stations and heavy water plants. Current work in vibration and fretting predictions, thermal-hydraulic analyses, and corrosion research is described. Procedures developed for in-service inspection, in situ tube replacment and chemical cleaning of corrosion products are also outlined

Nuclear power and the Canadian public. A national and regional assessment of public attitudes and perceptions of the use of nuclear power for the production of electricity

Energy Technology Data Exchange (ETDEWEB)

Greer-Wootten, B; Mitson, L [York Univ., Toronto, Ontario (Canada)

1976-06-01

Over 2,100 persons from the Canadian public aged 18 years and over were interviewed to ascertain the opinions and attitudes of Canadians toward the use of nuclear power for generating electricity. The results of this survey are presented.

Vault submodel for the second interim assessment of the Canadian concept for nuclear fuel waste disposal

International Nuclear Information System (INIS)

LeNeveu, D.M.

1986-02-01

The consequences to man and the environment of the disposal of nuclear fuel waste are being studied within the Canadian Nuclear Fuel Waste Management Program. The concept being assessed is that of a sealed disposal vault at a depth of 1000 m in plutonic rock in the Canadian Shield. To determine the consequences, the vault and its environment are simulated using a SYstem Variability Analysis Code (SYVAC), a stochastic model of the disposal system. SYVAC contains three submodels that represent the three major parts of the disposal system: the vault, the geosphere and the biosphere. This report documents the conceptual and mathematical framework of the vault submodel

Nuclear at Niagara. 32nd Annual Canadian Nuclear Society conference and 35th CNS/CNA student conference

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-07-01

The 32nd Annual Canadian Nuclear Society Conference and 35th CNS/CNA Student Conference was held in Niagara Falls, Ontario, Canada on June 5-8, 2011. The theme of the conference, 'Nuclear at Niagara', brought together scientists, engineers, technologists, senior management, government officials, and students interested in all aspects of nuclear science and technology and its applications, including nuclear power generation, fuel production, uranium mining and refining, management of radioactive wastes and used fuel. Other topics include medical and industrial uses of radionuclides, occupational and environmental radiation protection, the science and technology of nuclear fusion, and associated activities in research and development. and applications of energy from the atom. The central objective of this conference was to exchange views on how nuclear science and technology can best serve the needs of humanity, now and in the future. Over 400 delegates from across Canada and other nuclear countries were in attendance.

Proceedings of the 13. annual conference of the Canadian Nuclear Society. V. 1

Energy Technology Data Exchange (ETDEWEB)

1993-12-31

Volume 1 of the proceedings of the 13. annual conference of the Canadian Nuclear Society includes sessions on the following topics: reactor physics, new concepts and technology, fuel behaviour, reactor design, safety analysis, fuel channel behaviour, equipment and design qualification. The individual papers have been abstracted separately.

Canadian perspectives in evaluating transparency

International Nuclear Information System (INIS)

Herwig, L.

2007-01-01

The Canadian Nuclear Safety Commission's mission is to regulate the use of nuclear energy and materials to protect the health, safety, and security of Canadians and the environment, as well as to respect Canada's international commitments on the peaceful use of nuclear energy. In 2001, the CNSC established a vision to be one of the best nuclear regulators in the world and established four strategic priorities of effectiveness, transparency, excellence in staff, and efficiency. While fulfilling a very comprehensive mandate, the CNSC operates with a. very clear vision of its clientele - the Canadian people. That commitment guides every employee and every action of the CNSC and ensures a firm commitment to transparency. The presentation will begin with a brief overview of the worldwide context of transparency and transparency measurement, with a look at what lessons can be learned from other organizations and initiatives. It will look broadly at the Canadian context and the government framework that establishes transparency, including the keystone legislation of the Access to Information Act. The presentation will then focus on the Canadian Nuclear Safety Commission. The CNSC is firmly committed to putting additional measures in place to ensure transparency, which is being done concurrently with an overall organisational performance measurement system. It is within this framework that the presentation will address the transparency efforts at the CNSC as well transparency measurement activities. And, finally, the presentation will look at future directions for transparency and its measurement at the CNSC. (author)

Organic diagenesis in commercial nuclear wastes

International Nuclear Information System (INIS)

Toste, A.P.; Lechner-Fish, T.J.

1988-01-01

The nuclear industry currently faces numerous challenges. Large volumes of already existing wastes must be permanently disposed using environmentally acceptable technologies. Numerous criteria must be addressed before wastes can be permanently disposed. Waste characterization is certainly one of the key criteria for proper waste management. some wastes are complex melting pots of inorganics, radiochemicals, and, occasionally, organics. It is clear, for example, that organics have been used extensively in nuclear operations, such as waste reprocessing, and continue to be used widely as solvents, decontamination agents, etc. The authors have analyzed the organic content of many kinds of nuclear wastes, ranging from commercial to defense wastes. In this paper, the finale analyses are described of three commercial wastes: one waste from a pressurized water reactor (PWR) and two wastes from a boiling water reactor (BWR). The PWR waste is a boric acid concentrate waste. The two BWR wastes, BWR wastes Nos. 1 and 2, are evaporator concentrates of liquid wastes produced during the regeneration of ion-exchange resins used to purify reactor process water. In preliminary analyses, which were reported previously, a few know organics and myriad unknowns were detected. Recent reexamination of mass-spectral data, coupled with reanalysis of the wastes, has resulted in the firm identification of the unknowns. Most of the compounds, over thirty distinct organics, are derived from the degradation, or diagenesis, of source-term organics, revealing, for the first time, that organic diagenesis in commercial wastes is both vigorous and varied

Qualified Coatings in Nuclear Power Plants. Commercial products; Qualified Coatings in Nuclear Power Plants. Commercial products. Pinturas homologadas en centrales nucleares. Productos comerciales

Energy Technology Data Exchange (ETDEWEB)

Barcena, J.; Nunez, B.; Romero, M.; Baladiam, M.

2014-07-01

Recently, the supplier of paints that were qualified for use in nuclear applications as protective coatings have ceased to supply in Spain the paints that was used in areas or components with special requirements for nuclear power plants (NPPs). This lack of the common commercial products called for the search for and homologation of other products. A study was performed on the current status of the homologation of commercial products for NPPs and on the codes and standards governing them. The criteria to be met have been defined and the results of the tests performed on the selected paints have been compared against the established criteria so as to allow the homologation of the paints. (Author)

Commercial nuclear power in Western Europe: experience and prospects

International Nuclear Information System (INIS)

Hart, D.

1986-01-01

The commercialization of nuclear power in Western Europe is likely to bring nuclear's share of electricity production from its current level of 30% to as high as 50% by the year 2000. Although France will build most of this new capacity and Denmark and Austria are abstaining, there is a clear trend in the region. Western Europe will likely decline in its share of world nuclear power as capacity increases in Eastern Europe and the Soviet Union even though its growth has been faster than that of the US. The author compares capacity changes, plant performance, and nuclear trade developments in the individual European countries with those of the US, Soviet Union, and Japan. The author also describes the nuclear fuel cycle, the commercialization of fast breeder reactors, and public opposition to the European Community's policy of expanding nuclear power. The use of nuclear heat for district heating in addition to electric power could change the prospects over the long term. 3 tables

Developing new products from Canadian nuclear technology

International Nuclear Information System (INIS)

Hatcher, S.R.; Lyon, R.B.

1987-06-01

By 1990, the Federal Government will have reduced its support for Atomic Energy of Canada Limited's nuclear R and D from the 1985 level of $200 million, to $100 million (1985 dollars). To meet the need for a broadened funding base, AECL Research Company has been restructured to become more responsive to our sponsors and customers. Although supporting the CANDU nuclear power program remains by far our largest R and D activity, we have put in place a comprehensive process for generating new business and commercial activities. Examples of such business opportunities are presented in the paper

The Canadian Nuclear Safety Commission Compliance Program for Uranium Mines and Mills

Energy Technology Data Exchange (ETDEWEB)

Schryer, D., E-mail: denis.schryer@cnsc-ccsn.gc.ca [Canadian Nuclear Safety Commission, Saskatoon, Saskatchewan (Canada)

2014-05-15

The Canadian Nuclear Safety Commission (CNSC) is the principal nuclear regulator in Canada. The CNSC is empowered through the Nuclear Safety and Control Act (NSCA) and its associated regulations, to regulate the entire nuclear cycle which includes: uranium mining and milling, uranium refining and processing, fuel fabrication, power generation and nuclear waste management. A CNSC uranium mine licence is required by a proponent to site, prepare, construct, operate, decommission and abandon this nuclear facility. The CNSC licence is the legal instrument that authorizes the regulated activities and incorporates conditions and regulatory controls. Following a favourable Commission Tribunal decision to issue a licence to authorize the licensed activities, CNSC develops and executes a compliance plan of the licensee’s programs and procedures. The CNSC compliance plan is risk-informed and applies its resources to the identified higher risk areas. The compliance program is designed to encourage compliance by integrating three components: promotion, verification and enforcement and articulates the CNSC expectations to attain and maintain compliance with its regulatory requirements. The licensee performance is assessed through compliance activities and reported to the Commission to inform the licensing process during licence renewal. The application of the ongoing compliance assessment and risk management model ensures that deviations from impact predictions are addressed in a timely manner. The Uranium Mines and Mills Division of the CNSC are preparing to meet the challenges of the planned expansion of their Canadian uranium mining industry. The presentation will discuss these challenges and the measures required to address them. The Uranium Mines and Mills Division (UMMD) have adopted a structured compliance framework which includes formal procedures to conduct site inspections. New UMMD staff are trained to apply the regulations to licensed sites and to manage non

Commercialization of the global nuclear energy partnership (GNEP)

International Nuclear Information System (INIS)

Loewen Eric P.; Boaz, Jeffery; Saito, Earl; Boardman, Chuck

2007-01-01

In February 2006 President Bush announced the Advanced Energy Initiative, which included the Department of Energy's (DOE) Global Nuclear Energy Partnership (GNEP). GNEP has seven broad goals, one of the major elements being to develop and deploy advanced nuclear fuel recycling technology. DOE is contemplating accelerating the deployment of these technologies to achieve the construction of a commercial scale application of these technologies. DOE now defines this approach as 'two simultaneous tracks: (1) deployment of commercial scale facilities for which advanced technologies are available now or in the near future, and (2) further research and development of transmutation fuels technologies'. GE believes an integrated technical solution, using existing reactor and fuel reprocessing technologies, is achievable in the near term to accelerate the commercial demonstration of GNEP infrastructure. The concept involves a single, integrated, commercial scale, recycling facility consisting of the Consolidated Fuel Treatment Center (CFTC), capable of processing LWR and fast reactor Spent Nuclear Fuel (SNF) and fabricating Advanced Recycling Reactor (ARR) actinide fuel. The integrated facility would include a fast reactor that uses actinide-bearing fuel to produce electricity. For optimal performance, GE believes this integrated facility should be co-located to eliminate transportation between the CFTC and ARR, and enhance proliferation resistance. This Advanced Recycling Center takes advantage of previous investments by government and industry in fast reactor technology research and development. To allow for commercial acceptance, a prototypical demonstration reactor and associated fuel cycle facility will be constructed, tested, and licensed. Taking advantage of GE's NRC-reviewed modular sodium-cooled PRISM reactor, only a single reactor will be needed and the cost and risk minimized in the initial phase of the program. This paper outlines a process and a schedule to

Nuclear energy technology: theory and practice of commercial nuclear power

International Nuclear Information System (INIS)

Knief, R.A.

1982-01-01

Reviews Nuclear Energy Technology: Theory and Practice of Commercial Nuclear Power by Ronald Allen Knief, whose contents include an overview of the basic concepts of reactors and the nuclear fuel cycle; the basics of nuclear physics; reactor theory; heat removal; economics; current concerns at the front and back ends of the fuel cycle; design descriptions of domestic and foreign reactor systems; reactor safety and safeguards; Three Mile Island; and a brief overview of the basic concepts of nuclear fusion. Both magnetic and inertial confinement techniques are clearly outlined. Also reviews Nuclear Fuel Management by Harry W. Graves, Jr., consisting of introductory subjects (e.g. front end of fuel cycle); core physics methodology required for fuel depletion calculations; power capability evaluation (analyzes physical parameters that limit potential core power density); and fuel management topics (economics, loading arrangements and core operation strategies)

Economic Experience in Creation and Operation of Commercial Propulsion Nuclear Plants. Annex VII

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-12-15

This annex considers the reduction of capital costs in commercial nuclear power by employing commercial scale production and common technologies of equipment design and fabrication, based on the vast production and operation experience of Russian Federation nuclear propulsion plants. The performed consideration proves the expediency of adopting the most effective engineering solutions and approaches used for production of propulsion nuclear plants in the production of commercial nuclear power plants.

Towards a regional siting approach for canadian nuclear fuel waste

International Nuclear Information System (INIS)

Kuhn, R.G.

1999-01-01

The proposal to construct a nuclear fuel waste (NFW) disposal facility in Canada is fraught with difficulties, particularly with respect to gaining public acceptance and consent. Public perceptions of risk associated with a disposal facility are generally negative. Indeed, it was found that over 60% of residents in northern Ontario communities are opposed to the possibility of a disposal facility being constructed within 120 km of their community. Even after being offered the possibility of compensation and incentives, the majority of residents are strongly opposed. Canadian decision makers have generally endorsed a siting framework known as the open siting approach. The major characteristic of this approach is that it allows for substantial public participation in any siting process. It is premised on the notion that only communities where a majority of citizens favour the siting of a facility will be considered as potential hosts. However, given that the majority of residents on the Ontario portion of the Canadian Shield are strongly opposed to a NFW facility, the open approach will not be a panacea for a successful siting process. The major limitation of this approach is the fact that a single community cannot be isolated from its surrounding region and communities. The purpose of this paper is to work towards the development of a regional siting strategy for Canadian nuclear fuel waste management. There are no clear precedents of a regional siting approach to facility location in Canada. However, some analogous planning regimes and initiatives have been attempted. Common to these initiatives is the consideration of a large geographical region and attempts to integrate, at least formally, social, cultural, political and environmental concerns in a coherent and comprehensive manner. Under this type of 'siting strategy' NFW management would be considered within a broad array of resource management initiatives, social and cultural priorities, and institutional

Safety analysis of the proposed Canadian geologic nuclear waste repository

International Nuclear Information System (INIS)

Prowse, D.R.

1977-01-01

The Canadian program for development and qualification of a geologic repository for emplacement of high-level and long-lived, alpha-emitting waste from irradiated nuclear fuel has been inititiated and is in its initial development stage. Fieldwork programs to locate candidate sites with suitable geological characteristics have begun. Laboratory studies and development of models for use in safety analysis of the emplaced nuclear waste have been initiated. The immediate objective is to complete a simplified safety analysis of a model geologic repository by mid-1978. This analysis will be progressively updated and will form part of an environmental Assessment Report of a Model Fuel Center which will be issued in mid-1979. The long-term objectives are to develop advanced safety assessment models of a geologic repository which will be available by 1980

Current Status of World Nuclear Fuel Cycle Technology (I): Canada and Latin America

International Nuclear Information System (INIS)

Choi, Hang Bok; Ko, Won Il

2007-05-01

Canada produces about one third of the world's uranium mine output, most of it from two new mines. After 2007 Canadian production is expected to increase further as more new mines come into production. About 15% of Canada's electricity comes from nuclear power, using indigenous technology, and 18 reactors provide over 12,500 MWe of power. Mexico has two nuclear reactors generating almost 5% of its electricity. Its first commercial nuclear power reactor began operating in 1989. There is some government support for expanding nuclear energy to reduce reliance on natural gas. Argentina has two nuclear reactors generating nearly one tenth of its electricity. Its first commercial nuclear power reactor began operating in 1974. Brazil has two nuclear reactors generating 4% of its electricity. Its first commercial nuclear power reactor began operating in 1982

Commercial grade item (CGI) dedication of generators for nuclear safety related applications

International Nuclear Information System (INIS)

Das, R.K.; Hajos, L.G.

1993-01-01

The number of nuclear safety related equipment suppliers and the availability of spare and replacement parts designed specifically for nuclear safety related application are shrinking rapidly. These have made it necessary for utilities to apply commercial grade spare and replacement parts in nuclear safety related applications after implementing proper acceptance and dedication process to verify that such items conform with the requirements of their use in nuclear safety related application. The general guidelines for the commercial grade item (CGI) acceptance and dedication are provided in US Nuclear Regulatory Commission (NRC) Generic Letters and Electric Power Research Institute (EPRI) Report NP-5652, Guideline for the Utilization of Commercial Grade Items in Nuclear Safety Related Applications. This paper presents an application of these generic guidelines for procurement, acceptance, and dedication of a commercial grade generator for use as a standby generator at Salem Generating Station Units 1 and 2. The paper identifies the critical characteristics of the generator which once verified, will provide reasonable assurance that the generator will perform its intended safety function. The paper also delineates the method of verification of the critical characteristics through tests and provide acceptance criteria for the test results. The methodology presented in this paper may be used as specific guidelines for reliable and cost effective procurement and dedication of commercial grade generators for use as standby generators at nuclear power plants

Impact of Commercial Strain Use on Saccharomyces cerevisiae Population Structure and Dynamics in Pinot Noir Vineyards and Spontaneous Fermentations of a Canadian Winery.

Directory of Open Access Journals (Sweden)

Jonathan T Martiniuk

Full Text Available Wine is produced by one of two methods: inoculated fermentation, where a commercially-produced, single Saccharomyces cerevisiae (S. cerevisiae yeast strain is used; or the traditional spontaneous fermentation, where yeast present on grape and winery surfaces carry out the fermentative process. Spontaneous fermentations are characterized by a diverse succession of yeast, ending with one or multiple strains of S. cerevisiae dominating the fermentation. In wineries using both fermentation methods, commercial strains may dominate spontaneous fermentations. We elucidate the impact of the winery environment and commercial strain use on S. cerevisiae population structure in spontaneous fermentations over two vintages by comparing S. cerevisiae populations in aseptically fermented grapes from a Canadian Pinot Noir vineyard to S. cerevisiae populations in winery-conducted fermentations of grapes from the same vineyard. We also characterize the vineyard-associated S. cerevisiae populations in two other geographically separate Pinot Noir vineyards farmed by the same winery. Winery fermentations were not dominated by commercial strains, but by a diverse number of strains with genotypes similar to commercial strains, suggesting that a population of S. cerevisiae derived from commercial strains is resident in the winery. Commercial and commercial-related yeast were also identified in the three vineyards examined, although at a lower frequency. There is low genetic differentiation and S. cerevisiae population structure between vineyards and between the vineyard and winery that persisted over both vintages, indicating commercial yeast are a driver of S. cerevisiae population structure. We also have evidence of distinct and persistent populations of winery and vineyard-associated S. cerevisiae populations unrelated to commercial strains. This study is the first to characterize S. cerevisiae populations in Canadian vineyards.

Impact of Commercial Strain Use on Saccharomyces cerevisiae Population Structure and Dynamics in Pinot Noir Vineyards and Spontaneous Fermentations of a Canadian Winery.

Science.gov (United States)

Martiniuk, Jonathan T; Pacheco, Braydon; Russell, Gordon; Tong, Stephanie; Backstrom, Ian; Measday, Vivien

2016-01-01

Wine is produced by one of two methods: inoculated fermentation, where a commercially-produced, single Saccharomyces cerevisiae (S. cerevisiae) yeast strain is used; or the traditional spontaneous fermentation, where yeast present on grape and winery surfaces carry out the fermentative process. Spontaneous fermentations are characterized by a diverse succession of yeast, ending with one or multiple strains of S. cerevisiae dominating the fermentation. In wineries using both fermentation methods, commercial strains may dominate spontaneous fermentations. We elucidate the impact of the winery environment and commercial strain use on S. cerevisiae population structure in spontaneous fermentations over two vintages by comparing S. cerevisiae populations in aseptically fermented grapes from a Canadian Pinot Noir vineyard to S. cerevisiae populations in winery-conducted fermentations of grapes from the same vineyard. We also characterize the vineyard-associated S. cerevisiae populations in two other geographically separate Pinot Noir vineyards farmed by the same winery. Winery fermentations were not dominated by commercial strains, but by a diverse number of strains with genotypes similar to commercial strains, suggesting that a population of S. cerevisiae derived from commercial strains is resident in the winery. Commercial and commercial-related yeast were also identified in the three vineyards examined, although at a lower frequency. There is low genetic differentiation and S. cerevisiae population structure between vineyards and between the vineyard and winery that persisted over both vintages, indicating commercial yeast are a driver of S. cerevisiae population structure. We also have evidence of distinct and persistent populations of winery and vineyard-associated S. cerevisiae populations unrelated to commercial strains. This study is the first to characterize S. cerevisiae populations in Canadian vineyards.

Fuel isolation research for the Canadian nuclear fuel waste management program

International Nuclear Information System (INIS)

1982-06-01

This document is intended to give a broad outline of the Fuel Isolatikn program and to indicate how this program fits into the overall framework of the Canadian Nuclear Fuel Waste Management Program. Similar activities in other countries are described, and the differences in philosophy behind these and the Canadian program are highlighted. A program plan is presented that outlines the development of research programs that contribute to the safety assessment of the disposal concept and the development of technology required for selection and optimization of a feasible fuel isolation system. Some indication of the work that might take place beyond concept assessment, at the end of the decade, is also given. The current program is described in some detail, with emphasis on what the prkgram has achieved to date and hopes to achieve in the future for the concept assessment phase of the waste management program. Finally, some major capital facilities associated with the fuel isolation program are described

MAPLE: a Canadian multipurpose reactor concept for national nuclear development

International Nuclear Information System (INIS)

Lidstone, R.F.

1984-06-01

Atomic Energy of Canada Limited, following an investigation of Canadian and international needs and world-market prospects for research reactors, has developed a new multipurpose concept, called MAPLE (Multipurpose Applied Physics Lattice Experimental). The MAPLE concept combines H 2 O- and D 2 O-moderated lattices within a D 2 O calandria tank in order to achieve the flux advantages of a basic H 2 O-cooled and moderated core along with the flexibility and space of a D 2 O-moderated core. The SUGAR (Slowpoke Uprated for General Applied Research) MAPLE version of the conept provides a range of utilization that is well suited to the needs of countries with nuclear programs at an early stage. The higher power MAPLE version furnishes high neutron flux levels and the variety of irradiation facilities that are appropriate for more advanced nuclear programs

Embracing the future: Canada's nuclear renewal and growth. 28th annual conference of the Canadian Nuclear Society and 31st CNS/CNA student conference

International Nuclear Information System (INIS)

2007-01-01

The 28th Annual Conference of the Canadian Nuclear Society and 31st CNS/CNA Student Conference was held on June 3-6, 2007 in Saint John, New Brunswick. The central objective of this conference was to provide a forum for exchange of views on how this technical enterprise can best serve the needs of humanity, now and in the future. 'Embracing the Future: Canada's Nuclear Renewal and Growth' was the theme for this year's gathering of nuclear industry experts from across Canada and around the world. This theme reflects the global renaissance of interest in nuclear technology, strongly evident here in Canada through plant refurbishments (underway and planned), new-build planning, renewal and expansion of the nuclear workforce, and growth in public support for environmentally sustainable technology. Topics for discussion at this conference include: the nuclear renaissance in Canada and around the world, recent developments at Canadian utilities, status of plant refurbishment and new build plans, and uranium supply issues. For business, energy, and science reporters this conference offers an insight into major nuclear projects and an opportunity to meet leaders in the nuclear sector. Over 100 technical papers were presented, as well as over 20 student papers, in the following sessions: control room operation; safety analyses; environment and waste management; plant life management and refurbishment; reactor physics; advanced reactor design; instrumentation control; general nuclear topics and standards; chemistry and materials; probabilistic safety assessment; and, performance improvement

Waste management in Canadian nuclear programs

International Nuclear Information System (INIS)

Dyne, P.J.

The objectives of the Canadian radioactive waste management program are described. Recycling actinides through reactors is being studied. Low and medium level waste treatments such as reverse osmosis concentration, immobilization in bitumen and plastics, and incineration are under study. Spent fuel can be stored dry in concrete canisters above ground and ultimate storage of wastes in salt deposits or hard rock is appropriate to Canadian conditions. (E.C.B.)

An approach for risk informed safety culture assessment for Canadian nuclear power stations

International Nuclear Information System (INIS)

Nelson, W.R.

2010-01-01

One of the most important components of effective safety and risk management for nuclear power stations is a healthy safety culture. DNV has developed an approach for risk informed safety culture assessment that combines two complementary paradigms for safety and risk management: loss prevention - for preventing and intervening in accidents; and critical function management - for achieving safety and performance goals. Combining these two paradigms makes it possible to provide more robust systems for safety management and to support a healthy safety culture. This approach is being applied to safety culture assessment in partnership with a Canadian nuclear utility. (author)

Current Status of World Nuclear Fuel Cycle Technology (I): Canada and Latin America

Energy Technology Data Exchange (ETDEWEB)

Choi, Hang Bok; Ko, Won Il

2007-05-15

Canada produces about one third of the world's uranium mine output, most of it from two new mines. After 2007 Canadian production is expected to increase further as more new mines come into production. About 15% of Canada's electricity comes from nuclear power, using indigenous technology, and 18 reactors provide over 12,500 MWe of power. Mexico has two nuclear reactors generating almost 5% of its electricity. Its first commercial nuclear power reactor began operating in 1989. There is some government support for expanding nuclear energy to reduce reliance on natural gas. Argentina has two nuclear reactors generating nearly one tenth of its electricity. Its first commercial nuclear power reactor began operating in 1974. Brazil has two nuclear reactors generating 4% of its electricity. Its first commercial nuclear power reactor began operating in 1982.

Canadian programs on understanding and managing aging degradation of nuclear power plant components

International Nuclear Information System (INIS)

Chadha, J.A.; Pachner, J.

1989-06-01

Maintaining adequate safety and reliability of nuclear power plants and nuclear power plant life assurance and life extension are growing in importance as nuclear plants get older. Age-related degradation of plant components is complex and not fully understood. This paper provides an overview of the Canadian approach and the main activities and their results towards understanding and managing age-related degradation of nuclear power plant components, structures and systems. A number of pro-active programs have been initiated to anticipate, detect and mitigate potential aging degradation at an early stage before any serious impact on plant safety and reliability. These programs include Operational Safety Management Program, Nuclear Plant Life Assurance Program, systematic plant condition assessment, refurbishment and upgrading, post-service examination and testing, equipment qualification, research and development, and participation in the IAEA programs on safety aspects of nuclear power plant aging and life extension. A regulatory policy on nuclear power plants is under development and will be based on the domestic as well as foreign and international studies and experience

Geoscience research for the Canadian nuclear fuel waste management program

International Nuclear Information System (INIS)

Whitaker, S.H.

1987-01-01

The Canadian Nuclear Fuel Waste Management Program is assessing the concept of deep disposal of nuclear fuel waste in plutonic rock. As part of that assessment, a broad program of geoscience and geotechnical work has been undertaken to develop methods for characterizing sites, incorporating geotechnical data into disposal facility design, and incorporating geotechnical data into environmental and safety assessment of the disposal system. General field investigations are conducted throughout the Precambrian Shield, subsurface investigations are conducted at designated field research areas, and in situ rock mass experiments are being conducted in an Underground Research Laboratory. Samples from the field research areas and elsewhere are subjected to a wide range of tests and experiments in the laboratory to develop an understanding of the physical and chemical processes involved in ground-water-rock-waste interactions. Mathematical models to simulate these processes are developed, verified and validated. 114 refs.; 13 figs

Commercialization of nuclear fuel cycle business

International Nuclear Information System (INIS)

Yakabe, Hideo

1998-01-01

Japan depends on foreign countries almost for establishing nuclear fuel cycle. Accordingly, uranium enrichment, spent fuel reprocessing and the safe treatment and disposal of radioactive waste in Japan is important for securing energy. By these means, the stable supply of enriched uranium, the rise of utilization efficiency of uranium and making nuclear power into home-produced energy can be realized. Also this contributes to the protection of earth resources and the preservation of environment. Japan Nuclear Fuel Co., Ltd. operates four business commercially in Rokkasho, Aomori Prefecture, aiming at the completion of nuclear fuel cycle by the technologies developed by Power Reactor and Nuclear Fuel Development Corporation and the introduction of technologies from foreign countries. The conditions of location of nuclear fuel cycle facilities and the course of the location in Rokkasho are described. In the site of about 740 hectares area, uranium enrichment, burying of low level radioactive waste, fuel reprocessing and high level waste control have been carried out, and three businesses except reprocessing already began the operation. The state of operation of these businesses is reported. Hereafter, efforts will be exerted to the securing of safety through trouble-free operation and cost reduction. (K.I.)

Nuclear the next generation. 34th Annual Canadian Nuclear Society conference and 37th CNS/CNA student conference

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-07-01

The 34th Annual Canadian Nuclear Society Conference and 37th CNS/CNA Student Conference was held in Toronto, Ontario, Canada on June 10-13, 2013. With the theme of the conference, 'Nuclear the Next Generation{sup ,} the conference actively engaged 400 participants in the many facets of this well-rum event. The conference combined excellent plenary speakers, a full set of technical papers, challenging student poster competitions, and interesting exhibits. The plenary session focussed on the themes: 'Nuclear Power - a Business Driver for the Next Generation'; and, 'Designing - the Next Generation'. The technical session titles were: Reactor and Radiation Physics; Environment and Spent Fuel Management; Operations and Maintenance; Fusion Science and Technology; Advanced Reactors and Fuels; Plant Life Extension, Refurbishment and Aging; Safety and Licensing; Chemistry and Materials; and, Thermalhydraulics. The student conference session was well attended and completed the 4 day event.

An assessment of the feasibility of indefinite containment of Canadian nuclear fuel wastes

International Nuclear Information System (INIS)

Shoesmith, D.W.; King, F.; Ikeda, B.M.

1995-05-01

This report presents an analysis of the expected corrosion behaviour of nuclear fuel waste containers in a conceptual Canadian disposal vault. The container materials considered are dilute Ti alloys (Grades-2, -12 and -16) and oxygen-free copper. The corrosive conditions within the disposal vault change with time as the initially trapped oxygen is consumed and as the heat and γ-radiation produced by the waste decays. This evolution of the vault environment is broadly classified into an early, warm and oxidizing period followed by a period of long-term, stable, cool and non-oxidizing conditions. The corrosion behaviour of both types of material during these two periods is discussed, and various models that have been developed to predict the lifetimes of the containers are presented. The conclusion is that indefinite containment of the waste is feasible with both copper and titanium alloys under Canadian disposal conditions. (author). refs., tabs., figs

Interaction of electromagnetic pulse with commercial nuclear-power-plant systems

Energy Technology Data Exchange (ETDEWEB)

Ericson, D.M. Jr.; Strawe, D.F.; Sandberg, S.J.; Jones, V.K.; Rensner, G.D.; Shoup, R.W.; Hanson, R.J.; Williams, C.B.

1983-02-01

This study examines the interaction of the electromagnetic pulse from a high altitude nuclear burst with commercial nuclear power plant systems. The potential vulnerability of systems required for safe shutdown of a specific nuclear power plant are explored. EMP signal coupling, induced plant response and component damage thresholds are established using techniques developed over several decades under Defense Nuclear Agency sponsorship. A limited test program was conducted to verify the coupling analysis technique as applied to a nuclear power plant. The results are extended, insofar as possible, to other nuclear plants.

Interaction of electromagnetic pulse with commercial nuclear-power-plant systems

International Nuclear Information System (INIS)

Ericson, D.M. Jr.; Strawe, D.F.; Sandberg, S.J.; Jones, V.K.; Rensner, G.D.; Shoup, R.W.; Hanson, R.J.; Williams, C.B.

1983-02-01

This study examines the interaction of the electromagnetic pulse from a high altitude nuclear burst with commercial nuclear power plant systems. The potential vulnerability of systems required for safe shutdown of a specific nuclear power plant are explored. EMP signal coupling, induced plant response and component damage thresholds are established using techniques developed over several decades under Defense Nuclear Agency sponsorship. A limited test program was conducted to verify the coupling analysis technique as applied to a nuclear power plant. The results are extended, insofar as possible, to other nuclear plants

Commercial Satellite Imagery Analysis for Countering Nuclear Proliferation

Science.gov (United States)

Albright, David; Burkhard, Sarah; Lach, Allison

2018-05-01

High-resolution commercial satellite imagery from a growing number of private satellite companies allows nongovernmental analysts to better understand secret or opaque nuclear programs of countries in unstable or tense regions, called proliferant states. They include North Korea, Iran, India, Pakistan, and Israel. By using imagery to make these countries’ aims and capabilities more transparent, nongovernmental groups like the Institute for Science and International Security have affected the policies of governments and the course of public debate. Satellite imagery work has also strengthened the efforts of the International Atomic Energy Agency, thereby helping this key international agency build its case to mount inspections of suspect sites and activities. This work has improved assessments of the nuclear capabilities of proliferant states. Several case studies provide insight into the use of commercial satellite imagery as a key tool to educate policy makers and affect policy.

Instrumentation and control in the Canadian nuclear power program -1989 status

International Nuclear Information System (INIS)

Lepp, R.M.

1990-01-01

Canada currently has 18 CANDU Pressurized Heavy Water Reactors in operation and 4 under construction, for an installed nuclear capacity of 15,500 MWe. Most of the reactors are in the province of Ontario where 50% of the electricity is nuclear generated. Atomic Energy of Canada is developing the CANDU-3, a 450 MWe reactor incorporating the latest available technologies, including distributed control. The three Canadian Utilities with CANDU reactors have made a major commitment to full-scope training simulators. In Canada there is a growing commitment to developing major improvements to the interface between the control systems, the field equipment and the operating staff. The development program underway makes extensive use of information technology, particularly expert systems and interactive media tools. Out of this will come an advanced CANDU control concept that should further improve the reliability and availability of CANDU stations. (author). 3 refs

Canadian Public and Stake holder Engagement Approach to a Spent Nuclear Fuel Management

Energy Technology Data Exchange (ETDEWEB)

Hwang, Yong Soo; Kim, Youn Ok [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Whang, Joo Ho [Kyunghee University, Yongin (Korea, Republic of)

2008-09-15

After Canada has struggled with a radioactive waste problem over for 20 years, the Canadian government finally found out that its approach by far has been lack of social acceptance, and needed a program such as public and stake holder engagement (PSE) which involves the public in decision-making process. Therefore, the government made a special law, called Nuclear Fuel Waste Act (NFWA), to search for an appropriate nuclear waste management approach. NFWA laid out three possible approaches which were already prepared in advance by a nuclear expert group, and required Nuclear Waste Management Organization (NWMO) to be established to report a recommendation as to which of the proposed approaches should be adopted. However, NFWA allowed NWMO to consider additional management approach if the other three were not acceptable enough. Thus, NWMO studied and created a fourth management approach after it had undertaken an comparison of the benefits, risks and costs of each management approach: Adaptive Phased Management. This approach was intended to enable the implementers to accept any technological advancement or changes even in the middle of the implementation of the plan. The Canadian PSE case well shows that technological R and D are deeply connected with social acceptance. Even though the developments and technological advancement are carried out by the scientists and experts, but it is important to collect the public opinion by involving them to the decision-making process in order to achieve objective validity on the R and D programs. Moreover, in an effort to ensure the principles such as fairness, public health and safety, security, and adoptability, NWMO tried to make those abstract ideas more specific and help the public understand the meaning of each concept more in detail. Also, they utilized a variety of communication methods from face-to-face meeting to e-dialogue to encourage people to participate in the program as much as possible. Given the fact that Korea

Canadian Public and Stake holder Engagement Approach to a Spent Nuclear Fuel Management

International Nuclear Information System (INIS)

Hwang, Yong Soo; Kim, Youn Ok; Whang, Joo Ho

2008-01-01

After Canada has struggled with a radioactive waste problem over for 20 years, the Canadian government finally found out that its approach by far has been lack of social acceptance, and needed a program such as public and stake holder engagement (PSE) which involves the public in decision-making process. Therefore, the government made a special law, called Nuclear Fuel Waste Act (NFWA), to search for an appropriate nuclear waste management approach. NFWA laid out three possible approaches which were already prepared in advance by a nuclear expert group, and required Nuclear Waste Management Organization (NWMO) to be established to report a recommendation as to which of the proposed approaches should be adopted. However, NFWA allowed NWMO to consider additional management approach if the other three were not acceptable enough. Thus, NWMO studied and created a fourth management approach after it had undertaken an comparison of the benefits, risks and costs of each management approach: Adaptive Phased Management. This approach was intended to enable the implementers to accept any technological advancement or changes even in the middle of the implementation of the plan. The Canadian PSE case well shows that technological R and D are deeply connected with social acceptance. Even though the developments and technological advancement are carried out by the scientists and experts, but it is important to collect the public opinion by involving them to the decision-making process in order to achieve objective validity on the R and D programs. Moreover, in an effort to ensure the principles such as fairness, public health and safety, security, and adoptability, NWMO tried to make those abstract ideas more specific and help the public understand the meaning of each concept more in detail. Also, they utilized a variety of communication methods from face-to-face meeting to e-dialogue to encourage people to participate in the program as much as possible. Given the fact that Korea

Cost effective nuclear commercial grade dedication

International Nuclear Information System (INIS)

Maletz, J.J.; Marston, M.J.

1991-01-01

This paper describes a new computerized database method to create/edit/view specification technical data sheets (mini-specifications) for procurement of spare parts for nuclear facility maintenance and to develop information that could support possible future facility life extension efforts. This method may reduce cost when compared with current manual methods. The use of standardized technical data sheets (mini-specifications) for items of the same category improves efficiency. This method can be used for a variety of tasks, including: Nuclear safety-related procurement; Non-safety related procurement; Commercial grade item procurement/dedication; Evaluation of replacement items. This program will assist the nuclear facility in upgrading its procurement activities consistent with the recent NUMARC Procurement Initiative. Proper utilization of the program will assist the user in assuring that the procured items are correct for the applications, provide data to assist in detecting fraudulent materials, minimize human error in withdrawing database information, improve data retrievability, improve traceability, and reduce long-term procurement costs

Prospective needs for decommissioning commercial nuclear facilities

International Nuclear Information System (INIS)

Stevens, G.H.; Yasui, M.; Laraia, M.

1992-01-01

The answers to the questions: How many reactors will face the end of their operating lifetime over the next few decades? To what extent are the issues of decommissioning urgent? The answers will lead us to those issues that should be tackled now in order to complete smoothly the decommissioning of commercial nuclear power plants. The prospective needs for decommissioning of nuclear power plants are illustrated from the viewpoint of reactor age, and some of the issues to be tackled, in particular by governments, in this century are discussed, to prepare for the future decommissioning activities. (author) 18 refs.; 2 figs.; 2 tabs

Suggested non-proliferation criteria for commercial nuclear fuel cycles

International Nuclear Information System (INIS)

Laney, R.V.; Heubotter, P.R.

1978-01-01

Based on the Administration's policy to prevent nuclear weapons proliferation through diversion of fuel from commercial reactor fuel cycles, a ''benchmark'' set of nonproliferation criteria was prepared for the commercial nuclear fuel cycle. These criteria should eliminate incremental risks of proliferation beyond those inherent in the present generation of low-enriched-uranium-fueled reactors operating in a once-through mode, with internationally safeguarded storage of spent fuel. They focus on the balanced application of technical constraints consistent with the state of the technology, with minimal requirements for institutional constraints, to provide a basis for assessing the proliferation resistance of proposed fission power systems. The paper contains: (1) our perception of the nuclear energy policy and of the baseline proliferation risk accepted under this policy; (2) objectives for a reactor and fuel cycle strategy which address the technical, political, and institutional aspects of diversion and proliferation and, at the same time, satisfy the Nation's needs for efficient, timely, and economical utilization of nuclear fuel resources; (3) criteria which are responsive to these objectives and can therefore be used to screen proposed reactor and fuel cycle strategies; and (4) a rationale for these criteria

Technical meeting on commercial applications of nuclear analytical techniques. Meeting report

International Nuclear Information System (INIS)

2004-01-01

This report summarizes the findings of the Technical Meeting on the Commercial Applications of Nuclear Analytical Techniques held in Vienna on 23-26 November 2004, where an assessment was initiated of the world capacity and market potentials for neutron activation analysis and nuclear spectroscopy, including an estimation of economic revenues. Industry and governmental agencies were identified as stakeholders for these laboratories. Examples are given of potential benefits of these techniques to the stakeholders. The potentials for commercial applications of neutron activation analysis and nuclear spectroscopy (measurement of alpha, beta and gamma ray emitting radionuclides) are addressed. First estimates are given of the worldwide capacity of these laboratories, suggestions and examples are given for potential markets and the typical organizational and technical constraints are discussed. Two case studies of commercial neutron activation analysis laboratories at a small and a medium-size reactor are given in the 'individual contributions' section of this document. An assessment of other nuclear analytical techniques such as X ray Fluorescence Spectrometry, Particle Induced X ray Emission Spectrometry or Ion Beam Analysis Spectrometry has been completed after a comprehensive collection of background information

Technical meeting on commercial applications of nuclear analytical techniques. Meeting report

Energy Technology Data Exchange (ETDEWEB)

NONE

2004-07-01

This report summarizes the findings of the Technical Meeting on the Commercial Applications of Nuclear Analytical Techniques held in Vienna on 23-26 November 2004, where an assessment was initiated of the world capacity and market potentials for neutron activation analysis and nuclear spectroscopy, including an estimation of economic revenues. Industry and governmental agencies were identified as stakeholders for these laboratories. Examples are given of potential benefits of these techniques to the stakeholders. The potentials for commercial applications of neutron activation analysis and nuclear spectroscopy (measurement of alpha, beta and gamma ray emitting radionuclides) are addressed. First estimates are given of the worldwide capacity of these laboratories, suggestions and examples are given for potential markets and the typical organizational and technical constraints are discussed. Two case studies of commercial neutron activation analysis laboratories at a small and a medium-size reactor are given in the 'individual contributions' section of this document. An assessment of other nuclear analytical techniques such as X ray Fluorescence Spectrometry, Particle Induced X ray Emission Spectrometry or Ion Beam Analysis Spectrometry has been completed after a comprehensive collection of background information.

A reanalysis of cancer mortality in Canadian nuclear workers (1956–1994) based on revised exposure and cohort data

Science.gov (United States)

Zablotska, L B; Lane, R S D; Thompson, P A

2014-01-01

Background: A 15-country study of nuclear workers reported significantly increased radiation-related risks of all cancers excluding leukaemia, with Canadian data a major factor behind the pooled results. We analysed mortality (1956–1994) in the updated Canadian cohort and provided revised risk estimates. Methods: Employment records were searched to verify and revise exposure data and to restore missing socioeconomic status. Excess relative risks per sievert (ERR/Sv) of recorded radiation dose and 95% confidence intervals (CIs) were estimated using Poisson regression. Results: A significant heterogeneity of the dose–response for solid cancer was identified (P=0.02), with 3088 early (1956–1964) Atomic Energy of Canada Limited (AECL) workers having a significant increase (ERR/Sv=7.87, 95% CI: 1.88, 19.5), and no evidence of radiation risk for 42 228 workers employed by three nuclear power plant companies and post-1964 AECL (ERR/Sv=−1.20, 95% CI: workers and non-significantly increased in other workers. In analyses with separate terms for tritium and gamma doses, there was no evidence of increased risk from tritium exposure. All workers had mortality lower than the general population. Conclusion: Significantly increased risks for early AECL workers are most likely due to incomplete transfer of AECL dose records to the National Dose Registry. Analyses of the remainder of the Canadian nuclear workers (93.2%) provided no evidence of increased risk, but the risk estimate was compatible with estimates that form the basis of radiation protection standards. Study findings suggest that the revised Canadian cohort, with the exclusion of early AECL workers, would likely have an important effect on the 15-country pooled risk estimate of radiation-related risks of all cancer excluding leukaemia by substantially reducing the size of the point estimate and its significance. PMID:24231946

Conditioning and handling of tritiated wastes at Canadian nuclear power facilities

International Nuclear Information System (INIS)

Krochmalnek, L.S.; Krasznai, J.P.; Carney, M.

1987-04-01

Ontario Hydro operates a 10,000 MW capacity nuclear power system utilizing the CANDU pressurized heavy water reactor design. The use of D 2 O as moderator and coolant results in the production of about 2400 Ci of tritium per MWe-yr. As a result, there is significant Canadian experience in the treatment, handling, transport and storage of tritiated wastes. Ontario Hydro operates its own reactor waste storage site which includes systems for volume reduction, immobilization and packaging of wastes. In addition, a facility to remove tritium from heavy water is presently being commissioned at the Darlington nuclear site. This facility will generate tritiated liquid and solid waste that will have to be properly conditioned prior to storage or disposal. The nature of these various wastes and the processes/packaging required to meet storage/disposal criteria are judged to have relevance to investigations in fusion facility waste arisings. Experience to date, planned operational procedures and ongoing R and D in this area are described

Emergency Mitigating Equipments - Post Fukushima Actions at Canadian Nuclear Power Plants - Portable AC Power Sources

International Nuclear Information System (INIS)

Vucetic, Jasmina; Kameswaran, R.

2015-01-01

In response to the Fukushima Daiichi NPP accident in 2011, the Canadian Nuclear Safety Commission set up a Task Force to evaluate operational, technical and regulatory implications on Canadian NPPs. While accepting that the risk from beyond-design-basis accidents (BDBA) at Canadian NPPs is very low, the Task Force identified a number of areas where additional improvements or confirmatory assessments would further enhance safety. As a result, a set of 36 Fukushima Action Items (FAIs) were assigned to the licensees. This paper focuses on the FAI related to electrical power system enhancements to address a total loss of all AC Power leading to a possibility of loss of heat sinks (i.e. Station Blackout). This required the licensees to implement the following: - Additional back up power supplied by portable diesel generator(s) to allow key instrumentation and control equipment and key electrical loads to remain operable; - Provisions for a storage and timely transportation and connection of the portable generator(s) to the applicable units; - Provisions for testing of the portable generator; - Provisions for fuelling of portable generators; - Provisions such as panels, receptacles, and connectors to quickly deploy the portable generators to plant system, and separate feeder cables route to avoid a common mode failure; - Load shedding strategy to extend the existing station's battery life to ensure that the connection of portable generators can be completed before the batteries are depleted; - Provisions to supply water to steam generators and Irradiated Fuel Bay using portable pumps; The paper will also provide a brief description of Electrical power systems of the Canadian NPPs designed to satisfy the high safety and reliability requirements for nuclear systems, which are based on the following: - 2 group design philosophy (Group 1 and Group 2 Electrical Power Systems) - 2 separate groups of onsite emergency generators (Class III Standby generators and Emergency

Chemistry research for the Canadian nuclear fuel waste management program

International Nuclear Information System (INIS)

Vikis, A.C.; Garisto, F.; Lemire, R.J.; Paquette, J.; Sagert, N.H.; Saluja, P.P.S.; Sunder, S.; Taylor, P.

1988-01-01

This publication reviews chemical research in support of the Canadian Nuclear Fuel Waste Management Program. The overall objective of this research is to develop the fundamental understanding required to demonstrate the suitability of waste immobilization media and processes, and to develop the chemical information required to predict the long-term behaviour of radionuclides in the geosphere after the waste form and the various engineered barriers containing it have failed. Key studies towards the above objective include experimental and theoretical studies of uranium dioxide oxidation/dissolution; compilation of thermodynamic databases and an experimental program to determine unavailable thermodynamic data; studies of hydrothermal alteration of minerals and radionuclide interactions with such minerals; and a study examining actinide colloid formation, as well as sorption of actinides on groundwater colloids

Improved technical specifications and related improvements to safety in commercial Nuclear power plants

International Nuclear Information System (INIS)

Hoffman, D.R.; Demitrack, T.; Schiele, R.; Jones, J.C.

2004-01-01

Many of the commercial nuclear power plants in the United States (US) have been converting a portion of the plant operating license known as the Technical Specifications (TS) in accordance with a document published by the US Nuclear Regulatory Commission (NRC). The TS prescribe commercial nuclear power plant operating requirements. There are several types of nuclear power plants in the US, based on the technology of different vendors, and there is an NRC document that supports each of the five different vendor designs. The NRC documents are known as the Improved Standard Technical Specifications (ISTS) and are contained in a separate document (NUREG series) for each one of the designs. EXCEL Services Corporation (hereinafter EXCEL) has played a major role in the development of the ISTS and in the development, licensing, and implementation of the plant specific Improved Technical Specifications (ITS) (which is based on the ISTS) for the commercial nuclear power plants in the US that have elected to make this conversion. There are currently 103 operating commercial nuclear power plants in the US and 68 of them have successfully completed the conversion to the ITS and are now operating in accordance with their plant specific ITS. The ISTS is focused mainly on safety by ensuring the commercial nuclear reactors can safely shut down and mitigate the consequences of any postulated transient and accident. It accomplishes this function by including requirements directly associated with safety in a document structured systematically and taking into account some key human factors and technical initiatives. This paper discusses the ISTS including its format, content, and detail, the history of the ISTS, the ITS development, licensing, and implementation process, the safety improvements resulting from a plant conversion to ITS, and the importance of the ITS Project to the industry. (Author)

Improved technical specifications and related improvements to safety in commercial Nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Hoffman, D.R.; Demitrack, T.; Schiele, R.; Jones, J.C. [EXCEL Services Corporation, 11921 Rockville Pike, Suite 100, Rockville, MD 20852 (United States)]. e-mail: donaldh@excelservices.com

2004-07-01

Many of the commercial nuclear power plants in the United States (US) have been converting a portion of the plant operating license known as the Technical Specifications (TS) in accordance with a document published by the US Nuclear Regulatory Commission (NRC). The TS prescribe commercial nuclear power plant operating requirements. There are several types of nuclear power plants in the US, based on the technology of different vendors, and there is an NRC document that supports each of the five different vendor designs. The NRC documents are known as the Improved Standard Technical Specifications (ISTS) and are contained in a separate document (NUREG series) for each one of the designs. EXCEL Services Corporation (hereinafter EXCEL) has played a major role in the development of the ISTS and in the development, licensing, and implementation of the plant specific Improved Technical Specifications (ITS) (which is based on the ISTS) for the commercial nuclear power plants in the US that have elected to make this conversion. There are currently 103 operating commercial nuclear power plants in the US and 68 of them have successfully completed the conversion to the ITS and are now operating in accordance with their plant specific ITS. The ISTS is focused mainly on safety by ensuring the commercial nuclear reactors can safely shut down and mitigate the consequences of any postulated transient and accident. It accomplishes this function by including requirements directly associated with safety in a document structured systematically and taking into account some key human factors and technical initiatives. This paper discusses the ISTS including its format, content, and detail, the history of the ISTS, the ITS development, licensing, and implementation process, the safety improvements resulting from a plant conversion to ITS, and the importance of the ITS Project to the industry. (Author)

Decommissioning commercial nuclear facilities: a review and analysis of current regulations

International Nuclear Information System (INIS)

Schilling, A.H.; Lippek, H.E.; Tegeler, P.D.; Easterling, J.D.

1979-08-01

This report describes and analyzes the regulatory requirements and guidelines applicable to the decommissioning of commercial light water reactors, other commercial nuclear fuel cycle facilities, and byproduct utilization facilities, as contained principally in the United States Code, the United States Code of Federal Regulations, and the United States Nuclear Regulatory Commission's Regulatory Guides. State requirements are discussed where appropriate. The report provides general background informaion to license applicants and to other interested parties. Included is an outline of procedural steps required of an applicant to comply with decommissioning regulatory requiremets

The regulatory evaluation of radiation protection training programmes at Canadian nuclear power plants

International Nuclear Information System (INIS)

Legare, M.; Tennant, D.

1996-01-01

The responsibility for providing the necessary assurance that the use of nuclear energy in Canada does not pose undue risk to health, safety, security and the environment is vested with the Atomic Energy Control Board (AECB). This responsibility has led the Operator Certification Division of the AECB to develop methods to obtain assurance that nuclear power plant operations personnel are well trained and adequately competent to perform their duties. The features of the AECB approach to evaluation of training programmes based on a systematic approach to training is described. An overview of the Canadian nuclear power plants' radiation protection qualification levels is given. The developing evaluation process is contributing to the improvement of licensee radiation protection training programmes. This is making possible the transfer of part of the responsibility for licensed personnel radiation protection qualification assessment to the licensees, thus enabling a reduction in the operator certification division formal qualification activities. (author)

Fuel alternatives for oil sands development - the nuclear option

Energy Technology Data Exchange (ETDEWEB)

Bock, D [Atomic Energy of Canada Ltd., Mississauga, ON (Canada); Donnelly, J K

1996-12-31

Currently natural gas is the fuel of choice in all oil sand developments. Alberta sources of hydrocarbon based fuels are large but limited. Canadian nuclear technology was studied as a possible alternative for providing steam for the deep commercial in situ oil sand projects which were initiated over ten years ago. Because the in situ technology of that time required steam at pressures in excess of 10 MPa, the nuclear option required the development of new reactor technology, or the use of steam compressors, which was not economical. The current SAGD (steam assisted gravity drainage) technology requires steam at pressures of less than 5 MPa, which is in the reach of existing Canadian nuclear technology. The cost of supplying steam for a SAGD in situ project using a CANDU 3 nuclear reactor was developed. The study indicates that for gas prices in excess of $2.50 per gigajoule, replacing natural gas fuel with a nuclear reactor is economically feasible for in situ projects in excess of 123 thousand barrels per day. (author). 9 refs., 3 tabs., 12 figs.

Fuel alternatives for oil sands development - the nuclear option

International Nuclear Information System (INIS)

Bock, D.; Donnelly, J.K.

1995-01-01

Currently natural gas is the fuel of choice in all oil sand developments. Alberta sources of hydrocarbon based fuels are large but limited. Canadian nuclear technology was studied as a possible alternative for providing steam for the deep commercial in situ oil sand projects which were initiated over ten years ago. Because the in situ technology of that time required steam at pressures in excess of 10 MPa, the nuclear option required the development of new reactor technology, or the use of steam compressors, which was not economical. The current SAGD (steam assisted gravity drainage) technology requires steam at pressures of less than 5 MPa, which is in the reach of existing Canadian nuclear technology. The cost of supplying steam for a SAGD in situ project using a CANDU 3 nuclear reactor was developed. The study indicates that for gas prices in excess of $2.50 per gigajoule, replacing natural gas fuel with a nuclear reactor is economically feasible for in situ projects in excess of 123 thousand barrels per day. (author). 9 refs., 3 tabs., 12 figs

Decommissioning project of commercial nuclear power plant

International Nuclear Information System (INIS)

Karigome, S.

2008-01-01

Decommissioning project of commercial nuclear power plant in Japan was outlined. It is expected that the land, after the decommissioning of commercial nuclear power plants, will serve as sites for new plants. Steps will be taken to reduce the amount of wastes generated and to recycle/reuse them. Wastes with a radioactivity concentration below the 'clearance level' need not be dealt with as radioactive material, and may be handled in the same way as conventional wastes. The Tokai-1 power station, a 166 MWe carbon dioxide cooled reactor which closed down in 1998, is being decommissioned and the first ten years as 'safe storage' to allow radioactivity to decay. Non-reactor grade components such as turbines were already removed, heat exchanger dismantling started and the reactor will be dismantled, the buildings demolished and the site left ready for reuse. All radioactive wastes will be classified as low-level wastes in three categories and will be buried under the ground. The total cost will be 88.5 billion yen -34.7 billion for dismantling and 53.8 billion for waste treatment including the graphite moderator. (T. Tanaka)

Guideline on evaluation and acceptance of commercial grade digital equipment for nuclear safety applications

International Nuclear Information System (INIS)

1996-10-01

Nuclear power plants are increasingly upgrading their instrumentation and control (I ampersand C) systems with commercial digital equipment, which allows them to continue meeting safety and reliability requirements while controlling operating costs. However, the use of commercial software-based devices for safety related applications has raised new issues that impact design, procurement, and licensing activities. This guideline describes a consistent, comprehensive approach for the evaluation and acceptance of commercial digital equipment for nuclear safety systems

An experimental study on the effect of TV commercials on the attitudes towards nuclear power generation

International Nuclear Information System (INIS)

Tada, Yasuyuki

1999-01-01

The present study is about the effect TV commercials have on the subjects' attitudes towards nuclear power generation. A number of 191 female students participated in the experiment. It was hypothesized that TV commercials would have a positive effect on the viewer's attitude towards nuclear power generation. The main results of the study supported this hypothesis, demonstrating that TV commercials constitute an effective means for changing people's perception of nuclear power generation. (author)

Radiocarbon dispersion around Canadian nuclear facilities

International Nuclear Information System (INIS)

Milton, G.M.; Kramer, S.J.; Brown, R.M.; Repta, C.J.W.; King, K.J.; Rao, R.R.

1995-01-01

Canadian deuterium uranium (CANDU) pressurized heavy-water reactors produce 14 C by neutron activation of trace quantities of nitrogen in annular gas and reactor components ( 14 N(n,p) 14 C), and from 17 O in the heavy water moderator by ( 17 O(n,α) 14 C). The radiocarbon produced in the moderator is removed on ion exchange resins incorporated in the water purification systems; however, a much smaller gaseous portion is vented from reactor stacks at activity levels considerably below 1% of permissible derived emission limits. Early measurements of the carbon speciation indicated that >90% of the 14 C emitted was in the form of CO 2 .We conducted surveys of the atmospheric dispersion of 14 CO 2 at the Chalk River Laboratories and at the Pickering Nuclear Generating Station. We analyzed air, vegetation, soils and tree rings to add to the historical record of 14 C emissions at these sites, and to gain an understanding of the relative importance of the various carbon pools that act as sources/sinks within the total 14 C budget. Better model parameters than those currently available for calculating the dose to the critical group can be obtained in this manner. Global dose estimates may require the development of techniques for estimating emissions occurring outside the growing season. (author)

Progress in welding studies for Canadian nuclear fuel waste disposal containers

International Nuclear Information System (INIS)

Maak, P.Y.Y.

1985-11-01

This report describes the progress in the development of closure-welding technology for Canadian nuclear fuel waste disposal containers. Titanium, copper and Inconel 625 are being investigated as candidate materials for fabrication of these containers. Gas-tungsten-arc welding, gas metal-arc-welding, resistance-heated diffusion bonding and electron beam welding have been evaluated as candidate closure welding processes. Characteristic weldment properties, relative merits of welding techniques, suitable weld joint configurations and fit-up tolerances, and welding parameter control ranges have been identified for various container designs. Furthermore, the automation requirements for candidate welding processes have been assessed. Progress in the development of a computer-controlled remote gas-shielded arc welding system is described

Design and safety features of commercial nuclear power plants in Japan, 1976 edition

International Nuclear Information System (INIS)

Izumi, Fumio; Harayama, Yasuo

1976-10-01

The December 1975 edition (JAERI-M 5959) contained design particulars and safety features of 20 commercial nuclear power plants in Japan as of December 1974. Subsequently new plants have been put into operation and some plants under construction have undergone design modifications. The present edition presents similar data of the commercial nuclear power plants in Japan up to June 1976, compiled by computer processing. (auth.)

Final argument relating to the Canadian nuclear power program

International Nuclear Information System (INIS)

Robertson, J.A.L.

1978-05-01

This report is the second brief, and one of a number of documents, submitted by Atomic Energy of Canada Limited (AECL) to the Ontario Royal Commission on Electric Power Planning. It is intended to update the original brief (AECL--5800) with respect to those matters that emerged during the course of the hearings and which had not been fully anticipated in that brief, as well as to summarize the AECL position on the various issues. To enable it to qualify as a ''final argument'' it contains only evidence or material that has been presented to the Royal Commission and is provided with marginal notations identifying the source of each section. It is AECL's position that the Canadian nuclear power program provides a safe, proven and efficient means of making a needed contribution to electricity supply, while strengthening the economy through the deployment of indigenous technology and resources. (author)

Radioactive waste disposal - ethical and environmental considerations - A Canadian perspective

International Nuclear Information System (INIS)

Roots, F.

1994-01-01

This work deals with ethical and environmental considerations of radioactive waste disposal in Canada. It begins with the canadian attitudes toward nature and environment. Then are given the canadian institutions which reflect an environmental ethic, the development of a canadian radioactive waste management policy, the establishment of formal assessment and review process for a nuclear fuel waste disposal facility, some studies of the ethical and risk dimensions of nuclear waste decisions, the canadian societal response to issues of radioactive wastes, the analysis of risks associated with fuel waste disposal, the influence of other energy related environmental assessments and some common ground and possible accommodation between the different views. (O.L.). 50 refs

Supply and cost factors for metals in the Canadian nuclear fuel waste immobilization program

International Nuclear Information System (INIS)

McConnell, D.B.

1982-11-01

Estimates have been made of the demand for immobilization containers to accommodate the irradiated fuel bundles arising from Canadian nuclear generating stations to the year 2020. The resulting estimates for container shells and container-filling alloys were compared to estimates for Canadian and Western World production of the candiate metals. The results indicate that, among the container shell metals, supply difficulties might arise only for Grade 7 titanium. Among the filling metals, only lead-antimony alloy might present supply problems. Current cost figures for plate made of each shell metal, and bulk quantities of filling metals, were compared. Materials costs would be least for a supported shell of stainless steel, followed by copper, titanium alloys Grades 2, 12 and 7, and Inconel 625. Aluminum-silicon is the lowest-cost filling matrix, followed by zinc, lead, and lead-antimony. Container durability, vault conditions, groundwater composition and other factors may play an overriding role in the final selection of materials for container construction

An experimental study on the effect of TV commercials on the attitudes towards nuclear power generation

Energy Technology Data Exchange (ETDEWEB)

Tada, Yasuyuki [Institute of Nuclear Safety System Inc., Seika, Kyoto (Japan)

1999-09-01

The present study is about the effect TV commercials have on the subjects' attitudes towards nuclear power generation. A number of 191 female students participated in the experiment. It was hypothesized that TV commercials would have a positive effect on the viewer's attitude towards nuclear power generation. The main results of the study supported this hypothesis, demonstrating that TV commercials constitute an effective means for changing people's perception of nuclear power generation. (author)

Corrosion of copper under Canadian nuclear fuel waste disposal conditions

International Nuclear Information System (INIS)

King, F.; Litke, C.D.

1990-01-01

The corrosion of copper was studied under Canadian nuclear fuel waste disposal conditions. The groundwater in a Canadian waste vault is expected to be saline, with chloride concentrations from 0.1 to 1.0 mol/l. The container would be packed in a sand/clay buffer, and the maximum temperature on the copper surface would be 100C; tests were performed up to 150C. Radiation fields will initially be around 500 rad/h, and conditions will be oxidizing. Sulfides may be present. The minimum design lifetime for the container is 500 years. Most work has been done on uniform corrosion, although pitting has been considered. It was found that the rate of uniform corrosion in aerated NaCl at room temperature is limited by the rate of the anodic reaction, which is controlled mainly by the rate of transport of dissolved metal species away from the copper surface. The rate of corrosion should become controlled by the transport of oxygen to the copper surface only at very low oxygen concentrations. In the presence of gamma radiation the corrosion rate may never become cathodically transport limited. In compacted buffer material, the corrosion rate appears to be limited by the rate of transport of copper species away from the corroding surface. The authors recommend that long-term predictions of container lifetime should be based on the known rate-determining step for the overall corrosion process. 8 refs

Issues related to the construction and operation of a geological disposal facility for nuclear fuel waste in crystalline rock - the Canadian experience

Energy Technology Data Exchange (ETDEWEB)

Allan, C.J.; Baumgartner, P.; Ohta, M.M.; Simmons, G.R.; Whitaker, S.H. [Atomic Energy of Canada Ltd., Pinawa, MB (Canada). Whiteshell Labs

1997-12-31

This paper covers the overview of the Canadian nuclear fuel waste management program, the general approach to the siting, design, construction, operation and closure of a geological disposal facility, the implementing disposal, and the public involvement in implementing geological disposal of nuclear fuel waste. And two appendices are included. 45 refs., 5 tabs., 10 figs.

Issues related to the construction and operation of a geological disposal facility for nuclear fuel waste in crystalline rock - the Canadian experience

International Nuclear Information System (INIS)

Allan, C.J.; Baumgartner, P.; Ohta, M.M.; Simmons, G.R.; Whitaker, S.H.

1997-01-01

This paper covers the overview of the Canadian nuclear fuel waste management program, the general approach to the siting, design, construction, operation and closure of a geological disposal facility, the implementing disposal, and the public involvement in implementing geological disposal of nuclear fuel waste. And two appendices are included. 45 refs., 5 tabs., 10 figs

Commercialization, Altruism, Clinical Practice: Seeking Explanation for Similarities and Differences in Californian and Canadian Gestational Surrogacy Outcomes.

Science.gov (United States)

White, Pamela M

Surrogacy is growing worldwide. Although recently some countries have sought to ban it, between 2010 and 2014 the number of babies born to gestational surrogates having in vitro fertilization treatment in California doubled, and in Canada it grew by 35%. This work seeks to fill identified knowledge gaps about the similarities and differences in the practices and outcomes of gestational surrogacy, which in California operates on a commercial basis, whereas in Canada it is illegal to pay a surrogate. The paper focusses on the period from 2010 to 2014, for which comparable American and Canadian national assisted reproduction technology information exist. A retrospective data analysis was performed using information on gestational surrogate multiple births obtained from the Centers for Disease Control and Prevention National Assisted Reproductive Technology Surveillance System (NASS) and Canada's Assisted Reproduction Registry-Better Outcomes Registry and Network (CARTR-BORN). Multiple birth rates and transfers of multiple embryos were compared using relative risk analysis. Adherence to voluntary American Society for Reproductive Medicine-Society for Assisted Reproductive Technology and Canadian Fertility and Andrology Society embryo transfer guidelines was modelled. Among gestational surrogates, when donor ova embryos obtained from women aged less than 35 years were used, embryo transfer guideline adherence was 42% in California and 48% in Canada. Regardless of where on the commercial/noncommercial boundary North American surrogates reside, they are more likely to receive more donor ova embryos per in vitro fertilization transfer than other in vitro fertilization patients. An altruistic desire to assist childless couples and individuals create families along with clinic practices seem to play major roles in treatment decisions privileging the transfer two or more embryos. Copyright © 2018 Jacobs Institute of Women's Health. Published by Elsevier Inc. All rights

Organizational learning in commercial nuclear power plant safety: An empirical analysis

International Nuclear Information System (INIS)

Marcus, A.A.; Bromiley, P.; Nichols, M.L.

1989-01-01

The need for knowledge in organizations that manage and run high risk technologies is very high. The acquisition of useful knowledge is referred to as organizational learning. The theoretical roots of this concept are well established in the academic literature and in practice, especially in manufacturing industries. This paper focuses on organizational problem solving and learning as it relates to the safe and efficient management of commercial nuclear power plants. The authors are co-investigators on a larger team working under contract with the Nuclear Regulatory Commission to develop a logical framework that enables systematic examination of potential linkages between management and organizational factors and safety in nuclear power plant performance. Management and organizational factors that facilitate or impede organizational learning are only a part of the larger study, but are the major focus of this paper. In this paper, the theoretical roots of the concept of organizational learning are discussed, relationships to measures of safety and efficiency of commercial nuclear power plants are hypothesized, and empirical findings which provide partial tests of the hypotheses are discussed. This line of research appears promising; implications for further research, regulatory application, and nuclear power plant management are described

Costs and results of federal incentives for commercial nuclear energy

International Nuclear Information System (INIS)

Bezdek, R.H.; Wendling, R.M.

1991-01-01

This paper (1) estimates the total costs of federal expenditures in support of incentives for the development of commercial nuclear energy through 1988, and (2) analyzes the results and benefits to the nation of this federal investment. The federal incentives analyzed include research and development, regulation of commercial nuclear energy, tax incentives, waste management and disposal, enrichment plants, liability insurance, the uranium mining industry, and all other federal support activities. The authors estimate that net federal incentives totaled about $45-50 billion (1988 dollars). They estimate the results of the federal incentives, focusing on six categories, namely, electric energy produced, the total (direct plus indirect) economic benefits of the industry created, R and D program benefits, value of energy imports displaced, environmental effects, and health, safety, and risk effects. The results total $1.9 trillion, with approximately $250-300 billion identified as net benefits. The authors conclude that the high return on the investment justified federal incentives for nuclear energy development over the past four decades and that the federal government and the nation have received a significant return on the incentives investment

Commercial nuclear waste repository in basalt

International Nuclear Information System (INIS)

Hardy, M.P.; Patricio, J.G.; Heley, W.H.

1980-06-01

The Basalt Waste Isolation Project (BWIP) is an ongoing research and engineering effort being conducted by Rockwell Hanford Operations (Rockwell), which is under contract to the US Department of Energy. The objectives of this program are to assess the feasibility of and to provide the technology needed to design and construct a licensed commercial nuclear waste repository in the deep basalt formations underlying the Hanford Site. An extensive preconceptual design effort was undertaken during 1979 to develop a feasible concept that could serve as a reference design for both surface and underground facilities. The preconceptual design utilized existing technology to the greatest extent possible to offer a system design that could be utilized in establishing schedule and cost baseline data, recommend alternatives that require additional study, and develop basic design requirements that would allow evolution of the design process prior to the existence of legislated criteria. This paper provides a description of the concept developed for the subsurface aspects of this nuclear waste repository

Canada's regulatory framework: The Canadian Nuclear Safety Commission's regulatory framework

International Nuclear Information System (INIS)

Howard, D.

2011-01-01

This paper will discuss the Canadian Nuclear Safety Commission and Canada's Regulatory Framework with respect to Low- and Intermediate-Level Radioactive Waste. The management of low and intermediate level radioactive waste must be ensured in a consistent, environmentally responsible and economical manner throughout its lifecycle -- from its production to the final disposal option. Radioactive waste has been produced in Canada since the early 1930s when the first radium/uranium mine began operating at Port Radium in the Northwest Territories. Pitchblende ore was transported from the Port Radium mine to Port Hope, Ontario where it was refined to produce radium for medical purposes. At present, radioactive waste is generated in Canada from the various stages and uses associated with the nuclear fuel cycle from uranium mining/milling to nuclear reactor operations to radioisotope manufacture and use. The Canadian Nuclear Safety Commission (CNSC regulates the use of nuclear energy and materials to protect the health, safety and security of Canadians and the environment; and to implement Canada's international commitments on the peaceful use of nuclear energy. The CNSC was established in 2000 under the Nuclear Safety and Control Act and reports to Parliament through the Minister of Natural Resources. The CNSC was created to replace the former Atomic Energy Control Board (AECB), which was founded in 1946. Under the Nuclear Safety and Control Act, CNSC's mandate involves four major areas: regulation of the development, production and use of nuclear energy in Canada to protect health, safety and the environment; regulation of the production, possession, use and transport of nuclear substances, and the production, possession and use of prescribed equipment and prescribed information; implementation of measures respecting international control of the development, production, transport and use of nuclear energy and substances, including measures respecting the

Analysis of public costs and risks in the Canadian nuclear industry

International Nuclear Information System (INIS)

Cantor, R.A.

1985-01-01

This dissertation evaluates selected aspects of the Canadian nuclear program in terms of their contribution to economic welfare. It concentrates on the diffusion of nuclear power in Canada, and measures the welfare implications within an ex post benefit-cost framework of the current generation of operating plants. This approach differs most significantly from prior research by focusing on the investment of public resources to pursue the management of the technological change and the importance of specific areas of uncertainty associated with the use of the technology. These areas of uncertainty are important for the understanding of policy actions which have altered the distribution of costs and risks in the industry, and would affect the relevance of the policies in another economic environment. The results of the benefit-cost analysis indicate that while the program has produced some possible regulatory outcomes, the social opportunity costs of the public investment have not been balanced by social benefits in the form of lower energy costs. Even under the most favorable assumptions used regarding the nuclear plants, the net social costs of the program are shown to be $10 billion in constant 1978 dollars and it is unlikely that the net benefits that have not been included in the analysis will yield a positive social gain in a welfare sense

Prospects for the Canadian uranium industry

International Nuclear Information System (INIS)

Runnalls, O.J.C.

1988-01-01

Canada became the world's largest uranium producer in 1984. That leadership position is likely to be maintained for many years into the future because of a firm production base, many undeveloped known deposits with commercial promise, and a large geological potential for new discoveries. There are some uncertainties on the horizon, principally because of restrictive actions in process within the USA, which are aimed at preserving a deteriorating domestic uranium industry. Should such actions result in import restriction, for example, there would be a negative effect on foreign producers at least in the short term. Canada may avoid such difficulties under a tentative U.S.-Canada free-trade agreement where restrictions on the import of Canadian uranium into the United States would be eliminated. Over the longer term, demand for Canada's uranium resources will grow because of the foreseen growth in the world's installed nuclear power capacity

Seminar on the organization and management of a commercial nuclear power project

International Nuclear Information System (INIS)

Peddicord, K.L.; Alvis, J.M.; Chitkara, K.K.

1986-01-01

A main function of student branches of the American Nuclear Society (ANS) is to identify activities that contribute to the professional development and growth of its student members. Over the past several years, the ANS student branch at Texas A and M University has toured the construction site of the South Texas Nuclear Project (STNP), which is jointly owned by the Houston Lighting and Power Company (HL and P), the City of San Antonio, the Central Power and Light Company, and the City of Austin. This year, student branch organizers recognized that another aspect of a commercial nuclear power plant was not being covered either in the academic course work or the plant tours. This facet includes the organization and management required to undertake a major nuclear power project. To fill this gap, HL and P sponsored a one-day seminar that covered the various managerial functions for STNP. The seminar on the Organization and Management at a Commercial Nuclear Power Project was very interesting and beneficial. Other ANS branches and utilities may find this to be a useful model for future activities

Decommissioning situation and research and development for the decommissioning of the commercial nuclear power station in Japan

International Nuclear Information System (INIS)

Yamamoto, Tatsumi.

1996-01-01

There are 48 commercial nuclear power stations in operation in Japan as of January 1, 1995, which supplies about 28% (2.2 x 10 8 MWh) of total annual electricity generation in FY 1992. Accordingly, as the nuclear power contributes so much in electricity generation, there is a growing concern in the public toward the safety on decommissioning nuclear power station. It is gravely important to secure the safety throughout the decommissioning. This paper discusses: the decommissioning situation in Japan; the Japanese national policy for decommissioning of commercial nuclear power stations; R and D for decommissioning of commercial nuclear power stations in Japan; and the present conditions of low-level radioactive wastes disposal in Japan

Commercial nuclear power: prospects for the United States and the world

International Nuclear Information System (INIS)

1986-01-01

This analysis report presents the current status and outlook for commercial nuclear power reactors for all countries in the world outside centrally planned economic areas (WOCA). Information regarding operable reactors in countries with centrally planned economies is presented in an appendix. The report provides documentation of the US nuclear capacity and generation projections through 1995. Projections for US nuclear capacity and generation through 2020 are presented for various nuclear power supply scenarios. These long-term projections are provided in support of the Department of Energy's activities pertaining to the Nuclear Waste Policy Act of 1982 and are used to produce the projections of fuel cycle requirements and spent fuel discharges

Canadian hydrogen safety program

International Nuclear Information System (INIS)

MacIntyre, I.; Tchouvelev, A.V.; Hay, D.R.; Wong, J.; Grant, J.; Benard, P.

2007-01-01

The Canadian hydrogen safety program (CHSP) is a project initiative of the Codes and Standards Working Group of the Canadian transportation fuel cell alliance (CTFCA) that represents industry, academia, government, and regulators. The Program rationale, structure and contents contribute to acceptance of the products, services and systems of the Canadian Hydrogen Industry into the Canadian hydrogen stakeholder community. It facilitates trade through fair insurance policies and rates, effective and efficient regulatory approval procedures and accommodation of the interests of the general public. The Program integrates a consistent quantitative risk assessment methodology with experimental (destructive and non-destructive) failure rates and consequence-of-release data for key hydrogen components and systems into risk assessment of commercial application scenarios. Its current and past six projects include Intelligent Virtual Hydrogen Filling Station (IVHFS), Hydrogen clearance distances, comparative quantitative risk comparison of hydrogen and compressed natural gas (CNG) refuelling options; computational fluid dynamics (CFD) modeling validation, calibration and enhancement; enhancement of frequency and probability analysis, and Consequence analysis of key component failures of hydrogen systems; and fuel cell oxidant outlet hydrogen sensor project. The Program projects are tightly linked with the content of the International Energy Agency (IEA) Task 19 Hydrogen Safety. (author)

The Canadian safeguards program

International Nuclear Information System (INIS)

Zarecki, C.W.; Smith, R.M.

1981-12-01

In support of the Treaty on the Non-Proliferation of Nuclear Weapons Canada provides technical support to the International Atomic Energy Agency for the development of safeguards relevant to Canadian designed and built nuclear facilities. Some details of this program are discussed, including the philosophy and development of CANDU safeguards systems; the unique equipment developed for these systems; the provision of technical experts; training programs; liaison with other technical organizations; research and development; implementation of safeguards systems at various nuclear facilities; and the anticipated future direction of the safeguards program

The role of long-term geologic changes in the regulation of the Canadian nuclear fuel waste management program

International Nuclear Information System (INIS)

Flavelle, P.

1996-01-01

It is recognized that the geosphere is a dynamic system over the long time frames of nuclear fuel waste disposal. This paper describes how consideration of a dynamic geosphere has impacted upon the evolving regulatory environment in Canada, and how the approach taken to comply with the regulatory requirements can affect the evaluation of long-term geologic changes. AECB staff opinion is that if the maximum possible effect of geologic changes can be demonstrated to have negligible impact on the safety of a nuclear fuel waste repository, then further consideration of a dynamic geosphere is unnecessary for the current review of the Canadian Nuclear Fuel Waste Management Program. (authors). 7 refs., 4 figs

Development of Canadian seismic design approach and overview of seismic standards

Energy Technology Data Exchange (ETDEWEB)

Usmani, A. [Amec Foster Wheeler, Toronto, ON (Canada); Aziz, T. [TSAziz Consulting Inc., Mississauga, ON (Canada)

2015-07-01

Historically the Canadian seismic design approaches have evolved for CANDU® nuclear power plants to ensure that they are designed to withstand a design basis earthquake (DBE) and have margins to meet the safety requirements of beyond DBE (BDBE). While the Canadian approach differs from others, it is comparable and in some cases more conservative. The seismic requirements are captured in five CSA nuclear standards which are kept up to date and incorporate lessons learnt from recent seismic events. This paper describes the evolution of Canadian approach, comparison with others and provides an overview and salient features of CSA seismic standards. (author)

Detection of Enterovirus D68 in Canadian Laboratories

Science.gov (United States)

Hatchette, Todd F.; Drews, Steven J.; Grudeski, Elsie; Booth, Tim; Martineau, Christine; Dust, Kerry; Garceau, Richard; Gubbay, Jonathan; Karnauchow, Tim; Krajden, Mel; Levett, Paul N.; Mazzulli, Tony; McDonald, Ryan R.; McNabb, Alan; Mubareka, Samira; Needle, Robert; Petrich, Astrid; Richardson, Susan; Rutherford, Candy; Smieja, Marek; Tellier, Raymond; Tipples, Graham

2015-01-01

The recent emergence of a severe respiratory disease caused by enterovirus D68 prompted investigation into whether Canadian hospital and provincial laboratories can detect this virus using commercial and laboratory-developed assays. This study demonstrated analytical sensitivity differences between commercial and laboratory-developed assays for the detection of enterovirus D68. PMID:25740765

Human health considerations in the assessment of Canadian concept for the disposal of nuclear fuel wastes

International Nuclear Information System (INIS)

Baweja, A.S.; Tracy, B.L.; Ahier, B.; Bartlett, S.

1996-01-01

In 1978, AECL was mandated by the government of Ontario and the federal government to find a permanent disposal solution for spent nuclear fuels. Canada opted for disposal in plutonic rocks of the Canadian shield. The Canadian concept calls for disposal in crystalline rocks at a depth of 500 to 1000 m below the surface. The spent fuel would be contained in a canister, the canister would be emplaced in a vault containing clay-based buffer materials, and the cavity would be backfilled and sealed with natural materials. A Federal Environmental Assessment Review Panel was formed in 1992 to assess the concept for disposal of the spent fuel. In this paper a brief discussion of the human health impacts of the proposed concept is presented. Our assessment is based on the information provided by AECL, namely, the main EIS document, a summary and nine other supporting documents

Guide to Canadian Aerospace-Related Industries

Science.gov (United States)

1990-08-01

EXPERIENCE: Present customers include Canadian Forces, Boeing Commercial Airplane Company, Boeing Helicopter Company. ADDRESS: Baskin Drive East REVISED...University Tel: (604) 946-4900 of British Columbia, Robbins Company, Lockheed Petroleum Services Fax: (604) 946-4671 and McDonnell Douglas. KEYWORDS

Neutron dosimetry at commercial nuclear plants. Final report of Subtask B: dosimeter response

Energy Technology Data Exchange (ETDEWEB)

Cummings, F.M.; Endres, G.W.R.; Brackenbush, L.W.

1983-03-01

As part of a larger program to evaluate personnel neutron dosimetry at commercial nuclear power plants, this study was designed to characterize neutron dosimeter responses inside the containment structure of commercial nuclear plants. In order to characterize those responses, dosimeters were irradiated inside containment at 2 pressurized water reactors and at pipe penetrations outside the biological shield at two boiling water reactors. The reactors were operating at full power during the irradiations. Measurements were also performed with electronic instruments, the tissue equivalent proportional counter (TEPC), and portable remmeters, SNOOPY, RASCAL and PNR-4.

Neutron dosimetry at commercial nuclear plants. Final report of Subtask B: dosimeter response

International Nuclear Information System (INIS)

Cummings, F.M.; Endres, G.W.R.; Brackenbush, L.W.

1983-03-01

As part of a larger program to evaluate personnel neutron dosimetry at commercial nuclear power plants, this study was designed to characterize neutron dosimeter responses inside the containment structure of commercial nuclear plants. In order to characterize those responses, dosimeters were irradiated inside containment at 2 pressurized water reactors and at pipe penetrations outside the biological shield at two boiling water reactors. The reactors were operating at full power during the irradiations. Measurements were also performed with electronic instruments, the tissue equivalent proportional counter (TEPC), and portable remmeters, SNOOPY, RASCAL and PNR-4

Characterization of Canadian coals by nuclear magnetic resonance spectroscopy

Energy Technology Data Exchange (ETDEWEB)

Furimsky, E.; Ripmeester, J.

1983-06-01

Apparent aromaticities of a series of Canadian coals of different rank were estimated by solid state nuclear magnetic resonance spectroscopy. The aromaticities varied from 0.57 for a lignite up to 0.86 for a semi-anthracite coal. The aromaticities correlated well with fixed carbon and oxygen content of the coals as well as with the mean reflectance of the coals. Correlations were also established between aromaticities and the H/C and H/SUB/a/SUB/r/SUB/u/C/SUB/a/SUB/r ratios of the coals. Uncertainties in calculation of the hypothetical H/SUB/a/SUB/r/SUB/u/C/SUB/a/SUB/r ratios, from experimental data were pointed out. Structural parameters of the chars derived from the coals by pyrolysis at 535 C were, also, estimated. The H/C and H/SUB/a/SUB/r/SUB/u/C/SUB/a/SUB/r ratios of the chars were markedly lower than those of coals. This was complemented by higher apparent aromaticities of the chars compared with the coals. (21 refs.)

A summary of the program and progress to 1984 December of the Canadian nuclear fuel waste management program

International Nuclear Information System (INIS)

Dixon, R.S.

1986-08-01

The Canadian Nuclear Fuel Waste Management Program involves research into the storage and transportation of used nuclear fuel, immobilization of fuel waste, and deep geological disposal of the immobilized waste. The program is now in the fifth year of a ten-year generic research and development phase. The objective of this phase of the program is to assess the safety and environmental aspects of the deep underground disposal of immobilized fuel waste in plutonic rock. The objectives of the research for each component of the program and the progress made to the end of 1984 are described in this report. 74 refs

Sustainable development through nuclear technology : 29th annual conference of the Canadian Nuclear Society and 32nd CNS/CNA student conference

International Nuclear Information System (INIS)

2008-01-01

The 29th Annual Conference of the Canadian Nuclear Society and 32nd CNS/CNA Student Conference on Sustainable Development through Nuclear Technology was held on June 1-4, 2008 in Toronto, Ontario, Canada. The theme of the conference was 'Nuclear Sustainability'. The central objective of this conference was to provide a forum for exchange of views on how this technical enterprise can best serve the needs of humanity, now and in the future. The renewed global interest in nuclear technology is based on a recognition of its potential to meet economic and environmental targets more favourably than competing technologies. Although many of these attractions are short-term in nature, they stem from a broader potential of nuclear technology to drive all aspects of development (social, environmental, economic) in a sustainable in this area. (author) a terial in support of fuel resources themselves. The conference drew a record attendance of over 450 delegates. Over 100 technical papers were presented within 15 technical sessions, as well as over 30 student papers in 5 sessions. The following list of session titles indicates the diversity of the technical papers: advanced reactors; plant and components; process systems; thermalhydraulics; safety and licensing; hydrogen; human factors; physics; instrumentation and control; environment and waste management; and plant operation. (author)

Second interim assessment of the Canadian concept for nuclear fuel waste disposal. Volume 3

International Nuclear Information System (INIS)

Johansen, K.; Donnelly, K.J.; Gee, J.H.; Green, B.J.; Nathwani, J.S.; Quinn, A.M.; Rogers, B.G.; Stevenson, M.A.; Dunford, W.E.; Tamm, J.A.

1985-12-01

The nuclear fuel waste disposal concept chosen for development and assessment in Canada involves the isolation of corrosion-resistant containers of waste in a vault located deep in plutonic rock. As the concept and the assessment tools are developed, periodic assessments are performed to permit evaluation of the methodology and provide feedback to those developing the concept. The ultimate goal of these assessments is to predict what impact the disposal system would have on man and the environment if the concept were implemented. The second such assessment was completed in 1984 and is documented in the Second Interim Assessment of the Canadian Concept for Nuclear Fuel Waste Disposal - Volumes 1-4. This, the third volume of the report, summarizes the pre-closure environmental and safety assessments completed by Ontario Hydro for Atomic Energy of Canada Limited. The preliminary results and their sigificance are discussed. 85 refs

Second interim assessment of the Canadian concept for nuclear fuel waste disposal. Volume 4

International Nuclear Information System (INIS)

Wuschke, D.M.; Gillespie, P.A.; Mehta, K.K.; Henrich, W.F.; LeNeveu, D.M.; Guvanasen, V.M.; Sherman, G.R.; Donahue, D.C.; Goodwin, B.W.; Andres, T.H.

1985-12-01

The nuclear fuel waste disposal concept chosen for development and assessment in Canada involves the isolation of corrosion-resistant containers of waste in a vault located deep in plutonic rock. As the concept and the assessment tools are developed, periodic assessments are performed to permit evaluation of the methodology and provide feedback to those developing the concept. The ultimate goal of these assessments is to predict what impact the disposal system would have on man and the environment if the concept were implemented. The second such assessment was performed in 1984 and is documented in the Second Interim Assessment of the Canadian Concept for Nuclear Fuel Waste Disposal - Volumes 1-4. This volume, entitled Post-Closure Assessment, describes the methods, models and data used to perform the second post-closure assessment. The results are presented and their significance is discussed. Conclusions and planned improvements are listed. 72 refs

Canisters and nonfuel components at commercial nuclear reactors

International Nuclear Information System (INIS)

Gibbard, K.; Disbrow, J.

1994-01-01

This paper discusses detailed data on canisters and nonfuel components (NFC) at US commercial nuclear power reactors. A wide variety of NFC have been reported on the Form RW-859, open-quotes Nuclear Fuel Dataclose quotes survey. They may have been integral with an assembly, noncanistered in baskets, destined for disposal as low-level radioactive waste, or stored in canisters. Similarly, data on the family of canistered spent nuclear fuel (SNF) in storage pools was compiled. Approximately 85 percent of the 40,194 pieces of nonfuel assembly (NFA) hardware reported were integral with an assembly. This represents data submitted by 95 of the 107 reactors in 10 generic assembly classes. In addition, a total of 286 canisters have been reported as being in storage pools as of December 31, 1992. However, an additional 264 open baskets were also reported to contain miscellaneous SNF and nonfuel materials, garbage and debris. All of these 286 canisters meet the dimensional envelope requirements specified for disposal for open-quotes standard fuelclose quotes under the Standard Contract for Disposal of Spent Nuclear Fuel and/or High-Level Radioactive Waste (10 CFR 961); most of the baskets do not

Commercial nuclear power: prospects for the United States and the world

International Nuclear Information System (INIS)

Mayes, F.; Gielecki, M.; Diedrich, R.; Hewlett, J.; Murphy, T.

1985-01-01

This analysis report presents the current status and outlook for commercial nuclear power reactors for all countries in the world outside centrally planned economic areas (WOCA). Information regarding operable reactors in countries with centrally planned economies is also presented. The report provides documentation of the US middle-case nuclear capacity and generation projections through 1995 that are presented in the Annual Energy Outlook 1984. Additionally, US nuclear capacity and generation projections through 2020 are presented for various nuclear power supply scenarios. These long-term projections are provided in support of the Department of Energy's activities pertaining to the Nuclear Waste Policy Act of 1982. The projections for foreign nuclear capacity through 1990 supplant the preliminary foreign WOCA projections presented in the Annual Energy Outlook 1984 and are supplemented by WOCA country-specific projections through the year 2000

Commercial nuclear fuel from U.S. and Russian surplus defense inventories: Materials, policies, and market effects

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-05-01

Nuclear materials declared by the US and Russian governments as surplus to defense programs are being converted into fuel for commercial nuclear reactors. This report presents the results of an analysis estimating the market effects that would likely result from current plans to commercialize surplus defense inventories. The analysis focuses on two key issues: (1) the extent by which traditional sources of supply, such as production from uranium mines and enrichment plants, would be displaced by the commercialization of surplus defense inventories or, conversely, would be required in the event of disruptions to planned commercialization, and (2) the future price of uranium considering the potential availability of surplus defense inventories. Finally, the report provides an estimate of the savings in uranium procurement costs that could be realized by US nuclear power generating companies with access to competitively priced uranium supplied from surplus defense inventories.

Commercial nuclear fuel from U.S. and Russian surplus defense inventories: Materials, policies, and market effects

International Nuclear Information System (INIS)

1998-05-01

Nuclear materials declared by the US and Russian governments as surplus to defense programs are being converted into fuel for commercial nuclear reactors. This report presents the results of an analysis estimating the market effects that would likely result from current plans to commercialize surplus defense inventories. The analysis focuses on two key issues: (1) the extent by which traditional sources of supply, such as production from uranium mines and enrichment plants, would be displaced by the commercialization of surplus defense inventories or, conversely, would be required in the event of disruptions to planned commercialization, and (2) the future price of uranium considering the potential availability of surplus defense inventories. Finally, the report provides an estimate of the savings in uranium procurement costs that could be realized by US nuclear power generating companies with access to competitively priced uranium supplied from surplus defense inventories

The task ahead: a Canadian federal regulator's perspective

International Nuclear Information System (INIS)

Brooks, F.F.

1983-06-01

The author discusses the role of the Canadian National Energy Board (NEB) in any possible future exports of nuclear-generated electric power. The federal government has already indicated that it would support New Brunswick Power in its efforts to develop a second reactor at Point Lepreau dedicated to power export, and that similar support would be extended to other utilities. The NEB Act requires that a proposed energy export be surplus to reasonable foreseeable Canadian requirements and that the price be just and reasonable. The output of a plant built for power exports would be surplus to Canadian needs, but the problem comes in determining if producing that surplus would result in a net benefit to Canadians. Negotiating sales contracts will not be easy; purchase of Canadian firm power is only one option among others available to US utilities. However, the Canadian policy framework exists and the NEB is ready to receive applications for export licences

A Study on the Use of Commercial Satellite Imagery for Monitoring of Yongbyon Nuclear Activities

Energy Technology Data Exchange (ETDEWEB)

Lee, Jung Hyun; Kim, Min Soo [Korea Institute of Nuclear Nonproliferation and Control Daejeon (Korea, Republic of)

2014-10-15

It is particularly useful for the areas that are hard to access, such as the DPRK. On April 2009, North Korea expelled IAEA inspectors and USA disabling team at Yongbyon. Since then, there is not much left except for satellite imagery analysis. In this paper, we focused on the growing role and importance of commercial satellite imagery analysis for detecting and identifying nuclear activities at Yongbyon. For this, we examined monitoring capability of commercial satellite imagery status of commercial satellite imagery analysis to monitor the Yongbyon nuclear site. And we suggested several recommendations for enhancing the monitoring and analyzing capability. Current commercial satellite imagery has proven effective in monitoring for Yongbyon nuclear activities, especially change detection including the new construction activities. But identification and technical analysis of the operation status is still limited. In case of North Korea, operation status of 5 MWe reactor should be clearly identified to assess its plutonium production capability and to set up the negotiation strategy. To enhance the monitoring capability, we need much more thermal infrared imagery and radar imagery.

Commercial nuclear power 1988: Prospects for the United States and the world

International Nuclear Information System (INIS)

1988-01-01

This report presents historical data on commercial nuclear power in the United States, with projections of domestic nuclear capacity and generation through the year 2020. The report also gives country-specific projections of nuclear capacity and generation through the year 2010 for other countries in the world outside centrally planned economic areas (WOCA). Information is also presented regarding operable reactors and those under construction in countries with centrally planned economies. This report presents three different nuclear supply scenarios. The Optimistic-case scenario, included in previous issues of this report, has been deleted. 7 figs; 36 tabs

Strategies for the Canadian Smallsat Program

Science.gov (United States)

Symonds, M. D.

1993-11-01

Canadian industry working together with government representatives have evolved a strategic approach to defining a proposed Canadian Smallsat Program. The strategy is outlined and a framework is established for subsequent papers on industrial infrastructure and specific missions. The strategic objective is to establish a national capability, providing international leadership, and being a low-cost fast-response supplier in providing total system solutions. A major element of the strategy is a vertically integrated, low cost, team approach combining the expertise of various centers of excellence to provide an end-to-end systems capability. This expertise will address Canadian needs but will be export focused. It is proposed that Canada support a series of missions to establish the industrial infrastructure and demonstrate these capabilities. In selecting the missions, consideration is given to the commercial market factors, but scientific interest in smallsats is also recognized.

Establishing and Advancing Electronic Nuclear Material Accounting Capabilities: A Canadian Perspective

International Nuclear Information System (INIS)

Sample, J.

2015-01-01

Under safeguards agreements that the Government of Canada has with the International Atomic Energy Agency (IAEA), and nuclear cooperation agreements with other states, the Canadian Nuclear Safety Commission (CNSC) is required to track the inventory and movement of all safeguarded material. As safeguards programmes evolve, including the implementation of Integrated Safeguards, the scope of the reporting requirements for facilities within Canada has also increased. At the same time, ensuring the secure transmission of the associated data continues to be an overarching factor. The changes that are occurring in the nuclear material accounting (NMA) landscape have necessitated a modernization of Canada's accounting and reporting system, with the objective of creating a more effective and efficient system, while at the same time maintaining the security of prescribed information. After a review of the environment, the CNSC embarked on a project that would encourage facilities to transition away from traditional modes of NMA reporting and adopt an electronic approach. This paper will discuss how the changes to Canada's NMA infrastructure were identified and implemented internally to allow for optimized electronic reporting. Improvements included the development of the regulatory and guidance documents, the overhaul of the reporting forms, the upgrade of the CNSC's NMA database, and the development of an electronic reporting platform that leveraged existing technologies. The paper will also discuss the logistics of engaging stakeholders throughout the process, launching the system and soliciting feedback for future system improvements. Special consideration will be given to the benefits realized by both the CNSC and facilities who have voluntarily embraced electronic reporting. The final objective of this paper will be to identify the challenges that were faced by the CNSC and the nuclear industry as the system changes were implemented and to highlight how

Development situation about the Canadian CANDU Nuclear Power Generating Stations

Energy Technology Data Exchange (ETDEWEB)

Jeon, Yu Mi; Kim, Yong Hee; Park, Joo Hwan

2009-07-15

The CANDU reactor is the most versatile commercial power reactor in the world. The acronym 'CANDU', a registered trademark of Atomic Energy of Canada Limited, stands for 'CANada Deuterium Uranium'. CANDU uses heavy water as moderator and uranium (originally, natural uranium) as fuel. All current power reactors in Canada are of the CANDU type. Canada exports CANDU type reactor in abroad. CANDU type is used as the nuclear power plants to produce electrical. Today, there are 41 CANDU reactors in use around the world, and the design has continuously evolved to maintain into unique technology and performance. The CANDU-6 power reactor offers a combination of proven, superior and state-of-the-art technology. CANDU-6 was designed specifically for electricity production, unlike other major reactor types. One of its characteristics is a very high operating and fuel efficiency. Canada Nuclear Power Generating Stations were succeeded in a commercial reactor of which the successful application of heavy water reactor, natural uranium method and that on-power fuelling could be achieved. It was achieved through the joint development of a major project by strong support of the federal government, public utilities and private enterprises. The potential for customization to any country's needs, with competitive development and within any level of domestic industrial infrastructure, gives CANDU technology strategic importance in the 21st century.

Development situation about the Canadian CANDU Nuclear Power Generating Stations

International Nuclear Information System (INIS)

Jeon, Yu Mi; Kim, Yong Hee; Park, Joo Hwan

2009-07-01

The CANDU reactor is the most versatile commercial power reactor in the world. The acronym 'CANDU', a registered trademark of Atomic Energy of Canada Limited, stands for 'CANada Deuterium Uranium'. CANDU uses heavy water as moderator and uranium (originally, natural uranium) as fuel. All current power reactors in Canada are of the CANDU type. Canada exports CANDU type reactor in abroad. CANDU type is used as the nuclear power plants to produce electrical. Today, there are 41 CANDU reactors in use around the world, and the design has continuously evolved to maintain into unique technology and performance. The CANDU-6 power reactor offers a combination of proven, superior and state-of-the-art technology. CANDU-6 was designed specifically for electricity production, unlike other major reactor types. One of its characteristics is a very high operating and fuel efficiency. Canada Nuclear Power Generating Stations were succeeded in a commercial reactor of which the successful application of heavy water reactor, natural uranium method and that on-power fuelling could be achieved. It was achieved through the joint development of a major project by strong support of the federal government, public utilities and private enterprises. The potential for customization to any country's needs, with competitive development and within any level of domestic industrial infrastructure, gives CANDU technology strategic importance in the 21st century

Evaluation Of Electricity Production Cost Of Commercial Nuclear Power Plant Models

OpenAIRE

DÖNER, Nimeti

2017-01-01

The level of the development of countries is being measured by thecountry’s quantity of production and consumption energy. Concerning Turkey,according to an energy report of The World Energy Council Turkish NationalCommittee in order to meet the electricity needs of the country in 2010, there should befounded a 2000 MW(e) capacity nuclear power plant. For the nuclear electric powerplant considered to be founded in Turkey, three types of commercial reactor models,that are Pressiued Water React...

Incorporation of safety interlocks in commercial robotics for handling of nuclear materials

International Nuclear Information System (INIS)

Moore, F.W.

1986-01-01

Current robotic systems have been developed primarily for the automotive and electronic industry. The adaptation of these commercial robotic systems to applications in the manufacturing of nuclear fuel requires the addition of safety interlocks as to the handling and accountability of nuclear materials. Also, additional safety interlocks are required when the robots are operated in containment enclosures that are environmentally sealed. Interlocks have been incorporated into a commercial robot. The robotic system has been installed in the containment enclosure as part of the pellet storage subsystem into the Secure Automated Fabrication (SAF) facility currently being built by Westinghouse Hanford Company (WHC) for the US Department of Energy (DOE). The system has been installed in the Fuel Cycle Plant and is scheduled for initial operational testing in 1986

Incorporation of safety interlocks in commercial robotics for handling of nuclear materials

International Nuclear Information System (INIS)

Moore, F.W.

1986-01-01

The adaptation of commercial robotic systems to applications in the manufacturing of nuclear fuel has required the addition of safety interlocks as to the handling and accountability of nuclear materials. Also, additional safety interlocks are required when the robots are operated in containment enclosures that are environmentally sealed. Interlocks have been incorporated in a commercial robot which was modified and with additional interlocks into the existing robotic control system. The robotic system has been installed in the containment enclosure as part of the pellet storage subsystem in the Secure Automated Fabrication facility currently being built by Westinghouse Hanford Company for the US Department of Energy. The system has been installed in the Fuel Cycle Plant and is scheduled for initial operational testing in 1986

Potential effects of climatic change on radiological doses from disposal of Canadian nuclear fuel waste

International Nuclear Information System (INIS)

Amiro, B.D.

1997-01-01

The environmental assessment of deep geologic disposal of Canadian nuclear fuel waste considers many processes that could affect radionuclide transport to humans over thousands of years. Climatic change is an important feature that will occur over these long times. Glaciation will likely occur within the next 100,000 years over much of Canada, and its impact on radiological doses has been assessed previously. In the present study, we investigate the potential effect of short- term climatic change, usually associated with global warming caused by increases in atmospheric trace gases. We study the main biosphere transport pathways causing a radiological dose to humans from 129 I, which is the most important radionuclide in disposal of Canadian used nuclear fuel. Irrigation of a garden with contaminated well water is the main pathway and it can be affected by changes in temperature and precipitation. A cold, wet climate decreases the need for irrigation, and this decreases the radiological dose. A drastic climatic change, such as an increase in temperature from 10 to 20 degrees C and decrease in precipitation from 0.3 to 0.2 m during the growing season, is estimated to increase the dose by a factor of four. This is a relatively small change compared to the range of doses that arise from the variability and uncertainty in many of the parameters used in the environmental assessment models. Therefore, it is likely that the results of probabilistic dose assessment models can include the consequences of short-term climatic change. 39 refs., 3 figs

Fire protection of safe shutdown capability at commercial nuclear power plants

International Nuclear Information System (INIS)

Sullivan, K.

1993-01-01

The comprehensive industrial safety standards and codes that exist today have evolved from lessons learned through past experience, research results, and improvements in technological capabilities. The current requirements for fire safety features of commercial nuclear power stations operated in the US are a notable example of this practice. Although fire protection has always been an important design requirement, from the aftermath of a serious fire that occurred in 1975 at the Browns Ferry plant, it was learned that the life safety and property protection concerns of the major fire insurance underwriters may not sufficiently encompass nuclear safety issues, particularly with regard to the potential for fire damage to result in the common mode failure of redundant trains of systems, and components important to the safe shutdown of the reactor. Following its investigations into the Browns Ferry fire, the Nuclear Regulatory Commission (NRC) promulgated guidance documents, which ultimately developed into mandatory regulations, necessary to assure the implementation of a fire protection program that would address nuclear safety concerns. The new criteria that evolved, contain prescriptive design features, as well as personnel and administrative requirements the Commission determined to be necessary to provide a defense-in-depth level of protection against the hazards of fire and its associated effects on safety related equipment. These criteria are primarily contained in Appendix R of Title 10 to the Code of Federal Regulations (10 CFR 50). Since 1983, various members of the Department of Nuclear Energy (DNE) at Brookhaven National Laboratory (BNL) have provided technical assistance to the Nuclear Regulatory Commission (NRC) in support of its evaluations of fire protection features implemented at commercial nuclear power stations operated in the US. This paper presents a discussion of the insights gained by the author during his active participation in this area

Nuclear power in Canada

International Nuclear Information System (INIS)

1980-01-01

The Canadian Nuclear Association believes that the CANDU nuclear power generation system can play a major role in achieving energy self-sufficiency in Canada. The benefits of nuclear power, factors affecting projections of electric power demand, risks and benefits relative to other conventional and non-conventional energy sources, power economics, and uranium supply are discussed from a Canadian perspective. (LL)

Natural analogs in support of the Canadian concept for nuclear fuel waste disposal

International Nuclear Information System (INIS)

Cramer, Jan.

1994-08-01

The assessment of the long-term safety and performance of the Canadian concept for disposal of nuclear fuel waste is a unique and challenging undertaking, because the predictions have to be made for time periods in the range of 10 4 to 10 6 a into the future. The data used for the assessment modelling is in large part based on observations from short-term laboratory and field experiments. Natural analogs can provide a reference for the safety assessment, providing both useful data and a qualitative illustration of the interaction of processes and materials in complex natural systems. This report reviews the available natural analog information used in support of the Canadian concept, with particular emphasis on the disposal of used CANDU (CANada Deuterium Uranium) fuel. The introduction gives a definition of natural analogs and an overview of the various types of analogs and analog studies. The review is broken down into sections pertaining to the major components of the disposal system: the vault, the geosphere and the biosphere. Specific examples are given for each. In addition, a section deals with several comprehensive natural systems that contain a number of features and processes similar to the disposal concept and that are under study by a number of countries as part of their waste management programs. (author). 224 refs., 11 tabs., 2 figs

Natural analogs in support of the Canadian concept for nuclear fuel waste disposal

Energy Technology Data Exchange (ETDEWEB)

Cramer, Jan

1994-08-01

The assessment of the long-term safety and performance of the Canadian concept for disposal of nuclear fuel waste is a unique and challenging undertaking, because the predictions have to be made for time periods in the range of 10{sup 4} to 10{sup 6} a into the future. The data used for the assessment modelling is in large part based on observations from short-term laboratory and field experiments. Natural analogs can provide a reference for the safety assessment, providing both useful data and a qualitative illustration of the interaction of processes and materials in complex natural systems. This report reviews the available natural analog information used in support of the Canadian concept, with particular emphasis on the disposal of used CANDU (CANada Deuterium Uranium) fuel. The introduction gives a definition of natural analogs and an overview of the various types of analogs and analog studies. The review is broken down into sections pertaining to the major components of the disposal system: the vault, the geosphere and the biosphere. Specific examples are given for each. In addition, a section deals with several comprehensive natural systems that contain a number of features and processes similar to the disposal concept and that are under study by a number of countries as part of their waste management programs. (author). 224 refs., 11 tabs., 2 figs.

Outreach at the Canadian Nuclear Safety Commission - An Aboriginal Peoples' Perspective

International Nuclear Information System (INIS)

Lojk, R.; Ben Belfakhel, M.

2006-01-01

Established by the Nuclear Safety and Control Act (NSCA) that came into force in May 2000, the Canadian Nuclear Safety Commission (CNSC) is an independent federal agency that reports to Parliament through the Minister of Natural Resources. The CNSC regulates all uses of nuclear energy and nuclear materials from the production, to use, to the final disposition of any nuclear substances. Under the NSCA, the CNSC has the mandate to: - Regulate the development, production and use of nuclear energy and materials to protect the health, safety, security and environment; - Regulate production, possession and use of nuclear substances, prescribed equipment and prescribed information; - Implement measures respecting international commitments on the peaceful use of nuclear energy and substances; - Disseminate scientific, technical and regulatory information concerning CNSC activities. The main regulatory activities include setting regulatory standards, issuing licenses, verifying compliance and communicating with stakeholders and the public. These activities are accomplished by the work of two independent entities: a commission of up to seven members and a staff of about 500 employees. The Commission is an independent, quasi-judicial tribunal that provides licensing decisions on nuclear-related activities in a public forum. The President of the tribunal is the CEO of the CNSC staff organization. CNSC's regulatory philosophy is based on two principles: - Those persons and organizations subject to the NSCA and its Regulations are directly responsible for ensuring that the regulated activities that they engage in are managed so as to protect health, safety, security and the environment and to respect Canada's international commitments on the peaceful use of nuclear energy. - The CNSC is responsible to the public for regulating persons and organisations subject to the Nuclear Safety and Control Act and regulations to assure that they are properly discharging their obligations

Technoeconomic analysis of biojet fuel production from camelina at commercial scale: Case of Canadian Prairies.

Science.gov (United States)

Li, Xue; Mupondwa, Edmund; Tabil, Lope

2018-02-01

This study undertakes technoeconomic analysis of commercial production of hydro-processed renewable jet (HRJ) fuel from camelina oil in the Canadian Prairies. An engineering economic model designed in SuperPro Designer® investigated capital investment, scale, and profitability of producing HRJ and co-products (biodiesel, naphtha, LPG, and propane) based on biorefinery plant sizes of 112.5-675 million L annum -1 . Under base case scenario, the minimum selling price (MSP) of HRJ was $1.06 L -1 for a biorefinery plant with size of 225 million L. However, it could range from $0.40 to $1.71 L -1 given variations in plant capacity, feedstock cost, and co-product credits. MSP is highly sensitive to camelina feedstock cost and co-product credits, with little sensitivity to capital cost, discount rate, plant capacity, and hydrogen cost. Marginal and average cost curves suggest the region could support an HRJ plant capacity of up to 675 million L annum -1 (capital investment of $167 million). Crown Copyright © 2017. Published by Elsevier Ltd. All rights reserved.

Nuclear data sensitivity and uncertainty for the Canadian supercritical water-cooled reactor II: Full core analysis

International Nuclear Information System (INIS)

Langton, S.E.; Buijs, A.; Pencer, J.

2015-01-01

Highlights: • H-2, Pu-239, and Th-232 make large contributions to SCWR modelling sensitivity. • H-2, Pu-239, and Th-232 make large contributions to SCWR modelling uncertainty. • Isotopes of Zr make large contributions to SCWR modelling uncertainty. - Abstract: Uncertainties in nuclear data are a fundamental source of uncertainty in reactor physics calculations. To determine their contribution to uncertainties in calculated reactor physics parameters, a nuclear data sensitivity and uncertainty study is performed on the Canadian supercritical water reactor (SCWR) concept. The nuclear data uncertainty contributions to the neutron multiplication factor k eff are 6.31 mk for the SCWR at the beginning of cycle (BOC) and 6.99 mk at the end of cycle (EOC). Both of these uncertainties have a statistical uncertainty of 0.02 mk. The nuclear data uncertainty contributions to Coolant Void Reactivity (CVR) are 1.0 mk and 0.9 mk for BOC and EOC, respectively, both with statistical uncertainties of 0.1 mk. The nuclear data uncertainty contributions to other reactivity parameters range from as low as 3% of to as high as ten times the values of the reactivity coefficients. The largest contributors to the uncertainties in the reactor physics parameters are Pu-239, Th-232, H-2, and isotopes of zirconium

The changing structure of the international commercial nuclear power reactor industry

International Nuclear Information System (INIS)

Forsberg, C.W.; Hill, L.J.; Reich, W.J.; Rowan, W.J.

1992-12-01

The objective of this report is to provide an understanding of the international commercial nuclear power industry today and how the industry is evolving. This industry includes reactor vendors, product lines, and utility customers. The evolving structure of the international nuclear power reactor industry implies different organizations making decisions within the nuclear power industry, different outside constraints on those decisions, and different priorities than with the previous structure. At the same time, cultural factors, technical constraints, and historical business relationships allow for an understanding of the organization of the industry, what is likely, and what is unlikely. With such a frame of reference, current trends and future directions can be more readily understood

The House of Commons of Canada, Bill C-23 : An act to establish the Canadian Nuclear Safety Commission and to make consequential amendments to other acts

International Nuclear Information System (INIS)

1996-01-01

This enactment replaces the Atomic Energy Control Act with a modern statute to provide for more explicit and effective regulation of nuclear energy. While the existing Act encompasses both the regulatory and developmental aspects of nuclear activities, this enactment disconnects the two functions and provides a distinct identity to the regulatory agency. It replaces the Atomic Energy Control Board with the Canadian Nuclear Safety Commission, underlining its separate role from that of Atomic Energy of Canada Ltd., the federal research, development and marketing organization for nuclear energy

Violence in the massage parlor industry: experiences of Canadian-born and immigrant women.

Science.gov (United States)

Bungay, Vicky; Halpin, Michael; Halpin, Peter F; Johnston, Caitlin; Patrick, David M

2012-01-01

We examined and contrasted 129 Canadian-born and immigrant women's experiences of violence and associated structural and interpersonal factors within indoor commercial sex venues. The majority experienced at least one form of structural, interpersonal, or both types of violence, with the attempted removal of a condom during sexual services being cited most frequently. Canadian-born women reported more frequent violent assaults in the survey data. The women's qualitative narratives illustrated that perceptions of violence differed significantly among Canadian versus non-Canadian born women. Findings concerning racialization and gendered relations of power have important implications for prevention and interventions to support victims of abuse.

Assessment of the feasibility of indefinite containment of canadian nuclear fuel wastes; Evaluation de la faisabilite du confinement illimite des dechets de combustible nucleaire canadiens

Energy Technology Data Exchange (ETDEWEB)

Shoesmith, D.W.; King, F.; Ikeda, B.M.

1995-05-01

This report presents an analysis of the expected corrosion behavior of nuclear fuel waste containers in a conceptual Canadian disposal vault. The container materials considered are dilute Ti alloys (Grades-2, -12 and -16) and oxygen-free copper.

Korean system of export control to support the commercial nuclear transfer to UAE

International Nuclear Information System (INIS)

Cho, Young Ho

2011-01-01

In December 2009, the Republic of Korea won the contract to build 4 1,400 MW nuclear power reactors worth USD 20 billion in the UAE. The states-owned KEPCO will complete the turnkey project to the UAE including design, engineering, construction, nuclear fuel, operations, maintenance and technical support. Since sensitive nuclear technologies convertible to military purpose can be spread by the transfer of commercial nuclear power plant, it is essential prerequisite to implement nuclear export control tenaciously and effectively. About twenty years have passed since the Republic of Korea introduced export control system in domestic laws and regulations. Marking a major historical milestone in 2009 by ranking among global nuclear suppliers, the Korean government made a major step forward in export control framework to support its next nuclear export goal. (orig.)

Managing culture change in the commercial nuclear industry and the DOE weapons complex

International Nuclear Information System (INIS)

Buhl, A.R.

1992-01-01

Culture is the basic pattern of shared beliefs, behaviors, and assumptions acquired over time by the people in the organization. Culture is learned and can be modified over time. Many failures in managing change in recent years in the commercial nuclear industry and in the DOE weapons complex can be attributed to not accepting the central axiom of safety, health, and environmental matters. This paper presents specific lessons learned from experiences in commercial nuclear power and US Department of Energy weapons facilities restarts: (1) the attributes of problem plants and symptoms that predict impending regulatory doom; (2) the root causes of plant shutdown by regulators; (3) management infrastructure problems; and (4) actions required by management to effect the culture shift necessary to resume operations

The potential for stress corrosion cracking of copper containers in a Canadian nuclear fuel waste disposal vault

International Nuclear Information System (INIS)

King, F.

1996-09-01

The potential for stress corrosion cracking (SCC) of copper nuclear fuel waste containers in a conceptual Canadian disposal vault has been assessed through a review of the literature and comparison of those environmental factors that cause SCC with the expected disposal environment. Stress-corrosion cracking appears to be an unlikely failure mode for Cu containers in a Canadian disposal vault because of a combination of environmental factors. Most importantly, there is only a relatively short period during which the containers will be undergoing strain when cracking should be possible at all, and then cracking is not expected because of the absence of known SCC agents, such as NH 3 , NO 2 - or organic acids. In addition, other environmental factors will mitigate SCC, namely, the presence of C1 - and its effect on film properties and the limited supply of oxidants. These arguments, to greater or lesser extent, apply to the three major mechanisms proposed for SCC of Cu alloys in aqueous solutions: film-rupture/anodic dissolution, tarnish rupture and film-induced cleavage. Detailed reviews of the SCC literature are presented as Appendices. The literature on the SCC of Cu (>99 wt.% Cu) is reviewed, including studies carried out in a number of countries under nuclear waste disposal conditions. Because of similarities with the behaviour of Cu, the more extensive literature on the SCC of α-brass in ammonia solutions is also reviewed. (author). 140 refs., 3 tabs., 25 figs

The objectives and activities of the Canadian Radiation Protection Association

International Nuclear Information System (INIS)

Haynes, M.J.

1998-01-01

The Canadian Nuclear Society and the Canadian Radiation Protection Association are working to develop an agreement between the organizations to facilitate working together on issues of common interest. This paper will present the objectives, the organizational structure and major areas of activity of the Canadian Radiation Protection Association. It is a reciprocal presentation of one given earlier this year by Mr. Fred Boyd of the CNS to the CRPA annual conference. The intent is to help the membership of each organization better understand the objectives and interests of the other. (author)

Licensing operators for commercial nuclear power plants

International Nuclear Information System (INIS)

Hannon, J.N.

1988-01-01

The human element in the operation of commercial nuclear power plants is of utmost importance. Not only must the operators be technically competent in the execution of numerous complicated tasks, they must be capable of working together as a team to diagnose dynamic plant conditions to ensure that their plants are operated safely. The significance of human interaction skills and crew communications has been demonstrated most vividly in TMI and Chernobyl. It follows that the NRC must retain its high standards for licensing operators. This paper discusses activities and initiatives being employed by the NRC to enhance the reliability of its licensing examinations, and to build a highly qualified examiner work force

Licensing issues associated with the use of mixed-oxide fuel in U.S. commercial nuclear reactors

International Nuclear Information System (INIS)

Williams, D.L. Jr.

1997-04-01

On January 14, 1997, the Department of Energy, as part of its Record of Decision on the storage and disposition of surplus nuclear weapons materials, committed to pursue the use of excess weapons-usable plutonium in the fabrication of mixed-oxide (MOX) fuel for consumption in existing commercial nuclear power plants. Domestic use of MOX fuel has been deferred since the late 1970s, principally due to nuclear proliferation concerns. This report documents a review of past and present literature (i.e., correspondence, reports, etc.) on the domestic use of MOX fuel and provides discussion on the technical and regulatory issues that must be addressed by DOE (and the utility/consortia selected by DOE to effect the MOX fuel consumption strategy) in obtaining approval from the Nuclear Regulatory Commission to use MOX fuel in one or a group of existing commercial nuclear power plants

A study of commercially-available polyethylene terephthalate (PET) and polycarbonate as nuclear track detector materials

Science.gov (United States)

Espinosa, G.; Golzarri, J. I.; Vazquez-Lopez, C.; Trejo, R.; Lopez, K.; Rickards, J.

2014-07-01

In the study of the sensitivity of materials to be used as nuclear track detectors, it was found that commercial polyethylene terephthalate (PET) from Ciel® water bottles, commercial roof cover polycarbonate, and recycled packaging strips (recycled PET), can be used as nuclear track detectors. These three commercial materials present nuclear tracks when bombarded by 2.27 MeV nitrogen ions produced in a Pelletron particle accelerator, and by fission fragments from a 252Cf source (79.4 and 103.8 MeV), after a chemical etching with a 6.25M KOH solution, or with a 6.25M KOH solution with 20% methanol, both solutions at 60±1°C. As an example, the nitrogen ions deposit approximately 1 keV/nm in the form of ionization and excitation at the surface of PET, as calculated using the SRIM code. The fission fragments deposit up to 9 keV/nm at the surface, in both cases generating sufficient free radicals to initiate the track formation process. However, 5 MeV alpha particles, typical of radon (222Rn) emissions, deposit only 0.12 keV/nm, do not present tracks after the chemical etching process. This valuable information could be very useful for further studies of new materials in nuclear track methodology.

Improving Safety, Economic, Substantiality, and Security of Nuclear Energy with Canadian Super-Critical Water-cooled Reactor Concept

International Nuclear Information System (INIS)

Hamilton, Holly; Pencer, Jeremy; Yetisir, Metin; Leung, Laurence

2012-01-01

Super-Critical Water-cooled Reactor is one of the six design concepts being developed under the Generation IV International Forum. It is the only concept evolving from the water-cooled reactors and taking advantages of the balance-of-plant design and operation experience of the fossil-power plants. Canada is developing the SCR concept from the well-established pressure-tube reactor technology. The Canadian SCWR maintains modular design approach using relative small fuel channels with the separation of coolant and moderator. It is equipped with an advanced fuel channel design that is capable to transfer decay heat from the fuel to the moderator under the long-term cooling stage. Coupled with the advanced passive-moderator cooling system, cooling of fuel and fuel channel is continuous even without external power or operator intervention. The Canadian SCWR is operating at a pressure of 25 MPa with a core outlet temperature of 625 deg. C. This has led to a drastic increase in thermal efficiency to 48% from 34% of the current fleet of reactors (a 40% rise in relative efficiency). With the high core outlet temperature, a direct thermal cycle has been adopted and has led to simplification in plant design attributing to the cost reduction compared to the current reactor designs. The Canadian SCWR adopts the advanced Thorium fuel cycle to enhance the substantiality, economic, and security. than uranium in the world (estimated to be three times more). This provides the long-term fuel supply. Thorium's price is stable compared to uranium and is consistently lower than uranium. This would maintain the predictability and economic of fuel supply. Thorium itself is a non-fissile material and once irradiated requires special handling. This improves proliferative resistance. The objective of this paper is to highlight these improvements in generating nuclear energy with the Canadian SCWR

Marginalization and challenge: the production of knowledge and landscape in Canadian nuclear waste management policy making

International Nuclear Information System (INIS)

Stanley, A.E.

2006-01-01

Aboriginal peoples have recently become politically significant in Canadian nuclear fuel waste (NFW) management policy making. Their newfound significance comes on the heels of an important challenge to the knowledge and authority of the nuclear industry with respect to its plans for NFW lead by a number of public groups and Aboriginal peoples from across Canada, including the Serpent River First Nation. This dissertation examines the relationships between the discourses of the Serpent River First Nation (SRFN) about their experiences of the nuclear fuel chain and the discourses of the Nuclear Waste Management Organization (NWMO) about the management of NFW. Two trends are found to characterize these relationships: marginalization and challenge. The discourses of the NWMO marginalize the SRFN, excluding their experiences of the nuclear fuel chain, radioactivity, and the effects of nuclear industries from the policy making process. The discourses of the SRFN challenge the claims of the NWMO about the effects of nuclear wastes and radioactivity, as well as about the safe and beneficial development of the nuclear fuel chain. I identify discourses of 'modern risk' and 'citizenship' found in the work of the NWMO as instrumental for maintaining the nuclear industry's control over the production of knowledge about NFW and its effects and subjugating the knowledge of the SRFN. I also identify discourses of identity, oppression, and 'situated knowledge' as important challenges to the content, method and premises of the claims of the nuclear industry about the management of NFW. While I conclude that the NWMO's discourses of risk and citizenship constitute a colonial politics of exclusion, I note that their discourses are contingent on the exclusion of the experiences of the SRFN with the fuel chain. For their accounts to be coherent, the NWMO need to maintain a strategic silence on the overwhelming implication Aboriginal peoples, as a category, in the nuclear fuel chain

Canisters and nonfuel components at commercial nuclear reactors

International Nuclear Information System (INIS)

Gibbard, K.; Thorpe, J.; Moore, R.S.

1995-01-01

The Energy Information Administration of the U.S. Department of Energy (DOE) collects data annually from commercial nuclear power reactors via the Nuclear Fuel Data survey, Form RW-859. Over the past three years, the survey has collected data on the quantities and types of nonfuel components and on the quantities and contents of canisters in storage at reactor sites. This paper focuses on the annual changes in the data, specific implications of these changes, and lessons that should be applied to future revisions of the study. The total number of canisters reported by utilities for each year from 1986 to 1993 is listed. Changes in the quantities of nonfuel components report by General Reactors from 1992 to 1993 are also provided. Comparisons of canister and nonfuel components components data from year to year and from reactor to reactor point out that survey questions on these topics have been interpreted differently by reactor personnel

The nuclear option in Canada - why it is gaining ground

International Nuclear Information System (INIS)

Hopwood, J.M.; Alizadeh, A.; Hedges, K.R.; Tighe, P.

2005-01-01

Over the last five years, the nuclear option in Canada has gone from 'off-the-radar' to an essential part of the energy debate. In Ontario, in particular, building new nuclear plants, along with life-extension of existing plants, has been recommended by government commissions as one of the vital energy-supply options to be pursued. Both life-extension and introduction of new nuclear power plants are complicated by uncertainties in the energy market, and by changes in the organizational and policy environment. Public and policy-maker recognition of the nuclear role are steadily growing, but commercial conditions to support nuclear projects are still difficult to define and obtain. In Canada, as in many OECD countries, the need to add to electricity infrastructure is becoming apparent. Life-extension of existing nuclear units, and projects to build new unit, are being planned. The key challenges, once energy policy issues have been addressed, are mainly commercial. Based on its successful experience with overseas projects such as Quinshan, and on its evolutionary approach to design of new, advanced power plants, AECL is well placed to meet these challenges and launch a new round of nuclear projects. Overall, the Canadian perspective is towards increasing support for the nuclear option. Canada is poised to join the vanguard of the broadening nuclear power expansion. (orig.)

New state roles in the management and disposal of commercial nuclear waste

International Nuclear Information System (INIS)

Udall, M.K.

1977-01-01

Arguments are presented for the need for congressional action to clarify the respective regulatory responsibilities of the state and Federal Governments as they relate to commercial nuclear power. Three case studies in radioactive waste management and disposal are reviewed which are proported to illustrate the inadequacy of the existing regulatory framework to effectively manage and dispose of nuclear wastes. Examples of instances in which state legislatures have taken the initiative in the waste disposal problem are cited. It is concluded that regulatory reform should be in the direction of a dual system that provides states with new authority and leverage to control nuclear energy development patterns within their borders

Chemical and toxicological characterization of commercial smokeless tobacco products available on the Canadian market.

Science.gov (United States)

Rickert, W S; Joza, P J; Trivedi, A H; Momin, R A; Wagstaff, W G; Lauterbach, J H

2009-03-01

Some health experts are recommending that smokers who refuse to quit or refuse to use nicotine replacement therapy (NRT) such as nicotine-containing chewing gum switch to certain types of smokeless tobacco products (STP) such as Swedish snus. Other health experts disagree citing the uncertainty in the composition of commercially available STP, the lack of governmental regulations to ensure that STP advertised to meet certain standards (i.e., GothiaTek) do actually meet such standards, and the uncertainty that any STP can provide as safe as alternative to smoking as NRT. One reason for uncertainty is the dearth of detailed chemical and toxicological information on contemporary STP. Unlike the situation with cigarettes, there are few standardized methods for analytical and toxicological studies of STP. Consequently, the objective for this work was to characterize several types of STP available on the Canadian market using the modifications of the Official Health Canada chemical and toxicological methods developed for cigarettes. Moist snuff samples tested had TSNA and B[a]P levels somewhat above the GothiaTek standard while samples of Swedish snus, low-moisture snuff, and US-style chewing tobacco did not. Use of in vitro assays to assess STP toxicity was of limited utility in distinguishing product types.

Mutagenicity of smoke condensates from Canadian cigarettes with different design features.

Science.gov (United States)

Mladjenovic, Nemanja; Maertens, Rebecca M; White, Paul A; Soo, Evelyn C

2014-01-01

There is currently limited knowledge regarding the impact of different cigarette designs on the toxicological properties of cigarette smoke condensate (CSC). This study used the Salmonella Mutagenicity Assay to examine the mutagenic activity of mainstream CSCs from 11 commercial Canadian cigarette brands with different design features or tobacco blend. The brands were selected to include design features that are common for cigarettes sold in the Canadian market, as well as cigarettes with alternate filters (charcoal or MicroBlue™), the super slim design, and cigarettes containing mixed blends of different tobacco types. CSCs were obtained using the International Organization for Standardization (ISO) and Health Canada Intense (HCI) smoking regimes, and mutagenic activity was assessed using Salmonella strains TA98, YG1041 and YG5185. Comparisons of the commercial brands to the Kentucky 3R4F, the Canadian Monitor 8 reference and a Canadian best seller revealed no significant reduction in CSC mutagenicity for cigarettes with alternate filters. However, the super slim design did afford some reduction in mutagenic potency. Nevertheless, since the study did not attempt to evaluate the impact of the cigarette designs on human health at the individual or population level, the super slim cigarettes cannot be considered 'reduced-harm' cigarettes.

Nuclear science, technology and innovation in Canada - securing the future

Energy Technology Data Exchange (ETDEWEB)

Walker, R.S. [Atomic Energy of Canada Limited, Chalk River, ON (Canada)

2014-07-01

As a Tier 1 Nuclear Nation, Canada has a rich and proud history of achievement in nuclear Science, Technology and Innovation (ST&I) -- from commercializing the CANDU power system around the world, advancing fuel technology and nuclear safety, to protecting human health through nuclear medicine and cancer therapy technology. Today, the nuclear industry in Canada is actively working to secure its promising, long-term place in the world and is embracing the change necessary to fulfill the enormous potential for good of nuclear technology. For its part, the Canadian Government is taking a bold new public policy approach to nuclear ST&I, by restructuring its large, multi-faceted AECL Nuclear Laboratories. Through the restructuring, AECL, as Canada's premier nuclear science and technology organization, will be better positioned for success via an incentivized 'Government-owned-Contractor-operated', private-sector management model. The aim of this new approach is to enhance and grow high-value nuclear innovation for the marketplace, strengthen the competitiveness of Canada's nuclear sector, and reduce costs to the Government of Canada with time. This approach will play a key role in ensuring a bright future for the Canadian Nuclear Industry domestically and globally as it launches its 25-year Vision and Action Plan, where one of the priority action areas is support for a strong, forward-looking, nuclear ST&I agenda. As the new model for the Nuclear Laboratories is moved forward by the Government, with the support of AECL and industry, Canada's nuclear expertise and knowledge continue to be expanded and deepened through the work of the Laboratories' ten Centres of Excellence, where AECL's fundamental approach is guided by the reality that ST&I is needed in all aspects of the nuclear cycle, including decommissioning, waste management and environmental protection. (author)

Commercial spent nuclear fuel shipments in the United States, 1964--1987

International Nuclear Information System (INIS)

1990-12-01

This report provides an overview of US commercial light-water reactor spent-fuel shipments that have occurred from January, 1964 through December, 1987. A summary analysis was performed on these historical shipments, showing the amount of fuel that has been shipped to research facilities, reprocessing plants, away-from-reactor (AFR) storage sites, and other reactors. Also presented in this report is a listing of potential spent-fuel shipments to and/or from commercial nuclear plants. Table 1 provides the detailed listing of historical spent-fuel shipments. Table 2 is a summary of these shipments grouped by destination. Section IV discusses utility plans for future spent-fuel shipments. 2 tabs

Occupational radiation exposure at commercial nuclear power reactors, 1978

International Nuclear Information System (INIS)

Brooks, B.G.

1979-11-01

An updated compilation is presented of occupational radiation exposures at commercial nuclear power reactors for the years 1969 through 1978. Data received from the 64 light water cooled reactors (LWRs) that had completed at least one year of commercial operation as of December 31, 1978 are included. This represents an increase of seven reactors over the number contained in last year's report. The total number of personnel monitored at LWRs during 1978 increased by approximately 12% to 76,121. The number of workers that received measurable doses, however, increased only 8% to 45,978. The total collective dose for 1978 is estimated to be 31,806 man-rems, a small decrease from last year's value of 32,511, which results in the average dose per worker decreasing slightly to 0.69 rems. The average collective dose per reactor also decreased, by approximately 15%, to a value of 497 man-rems

Summary data for U.S. commercial nuclear power plants in the United States

International Nuclear Information System (INIS)

Heddleson, F.A.

1978-01-01

A compilation of data is presented for all United States commercial nuclear power plants for which a construction permit application was made through the Nuclear Regulatory Commission. The data are compiled in four separate tables with cross-referencing indexes: Table 1--General Data; Table 2--Reactor Data; Table 3--Site Data, and Table 4--Circulating-Water System Data. The power plants are listed in numerical order by docket number in all four tables

Commercial grade item (CGI) dedication of MDR relays for nuclear safety related applications

Science.gov (United States)

Das, Ranjit K.; Julka, Anil; Modi, Govind

1994-08-01

MDR relays manufactured by Potter & Brumfield (P&B) have been used in various safety related applications in commercial nuclear power plants. These include emergency safety features (ESF) actuation systems, emergency core cooling systems (ECCS) actuation, and reactor protection systems. The MDR relays manufactured prior to May 1990 showed signs of generic failure due to corrosion and outgassing of coil varnish. P&B has made design changes to correct these problems in relays manufactured after May 1990. However, P&B does not manufacture the relays under any 10CFR50 Appendix B quality assurance (QA) program. They manufacture the relays under their commercial QA program and supply these as commercial grade items. This necessitates CGI Dedication of these relays for use in nuclear-safety-related applications. This paper presents a CGI dedication program that has been used to dedicate the MDR relays manufactured after been used to dedicate the MDR relays manufactured after May 1990. The program is in compliance with current Nuclear Regulatory Commission (NRC) and Electric Power Research Institute (EPRI) guidelines and applicable industry standards; it specifies the critical characteristics of the relays, provides the tests and analysis required to verify the critical characteristics, the acceptance criteria for the test results, performs source verification to quality P&B for its control of the critical characteristics, and provides documentation. The program provides reasonable assurance that the new MDR relays will perform their intended safety functions.

Discussion on the impact of large commercial airplane to nuclear power plant

International Nuclear Information System (INIS)

Tang Bo

2010-01-01

Briefly introducing the 10CFR50.150, draft guide and technical document of United States which is issued recently by NRC and NEI on impact of large commercial airplane to nuclear power plant, introducing comments from society and public and responses from NRC, and briefly discussing relevant issues. (author)

Canada's nuclear non-proliferation policy

International Nuclear Information System (INIS)

1985-01-01

Canada's non-proliferation and safeguards policy has two objectives: 1) to promote the emergence of a more effective and comprehensive international non-proliferation regime; and 2) to assure the Canadian people and the international community that Canadian nuclear exports will not be used for any nuclear explosive purpose. By emphasizing the key role of the NPT, by promoting reliance upon and improvements in the IAEA safeguards system, by treating nuclear weapon and non-nuclear weapon states alike regarding Canadian nuclear exports, by working for new approaches covering the sensitive phases (e.g. reprocessing) of the nuclear fuel cycle, Canada's policy promotes attainment of the first objective. The latter objective is served through the network of bilateral nuclear agreements that Canada has put into place with its nuclear partners. Those agreements provide assurance that Canada's nuclear exports are used solely for legitimate, peaceful, nuclear energy production purposes. At the same time, Canada, having formulated its non-proliferation and safeguards policy during the period 1945 to 1980, has recognized that it has gone as far as it can on its own in this field and that from this point on any further changes should be made on the basis of international agreement. The Canadian objective in post-INFCE forums such as the Committee on Assurances of Supply is to exert Canada's best efforts to persuade the international community to devise a more effective and comprehensive international non-proliferation regime into which Canada and other suppliers might subsume their national requirements

Nuclear technologies for local energy systems

International Nuclear Information System (INIS)

McDonnell, F.N.; Lynch, G.F.

1990-03-01

If nuclear energy is to realize its full potential as a safe and cost-effective alternative to fossil fuels, applications beyond those that are currently being serviced by large, central nuclear power stations must be identified and appropriate reactors developed. The Canadian program on reactor systems for local energy supply is at the forefront of these developments. This program emphasizes design simplicity, low power density and fuel rating, reliance on natural processes, passive systems, and reduced reliance on operator action. The first product, the SLOWPOKE Energy System, is a 10 MW heat source specifically designed to provide hot water to satisfy the needs of local heating systems for building complexes, institutions and municipal district heating systems. A demonstration heating reactor has been constructed at the Whiteshell Nuclear Research Establishment in Manitoba and has been undergoing an extensive test program since first operation in 1987 July. Based on the knowledge learned from the design, construction, licensing and operational testing of this facility, the design of the 10 MW commercial-size unit is well advanced, and Atomic Energy of Canada Limited is prepared to commit the construction of the first commercial unit. Although the technical demonstration of the concept is important, it is recognized that another crucial element is the public and regulatory acceptance of small nuclear systems in urban areas. The decision by a community to commit the construction of a SLOWPOKE Energy System brings to a sharp focus the current public apprehension about nuclear technologies

Insurer risk control and nuclear liability

International Nuclear Information System (INIS)

DeMerchant, C.

2015-01-01

We specialize in high quality insurance risk management, underwriting and inspections for Canadian nuclear exposures. We provide true risk transfer, secure insurance capacity and collaborate with the world's nuclear experts to create innovative domestic solutions for our clients and members. The benefit of our experience works for all stake holders: insured clients, members, multi-level government agencies and all Canadians. NIAC has a 55-year history of partnering with insurers around the globe to create reliable risk management for the nuclear industry. We offer Canadian risk solutions, thought leadership and expertise that provides security and confidence to our customers and members. NIAC leads in the areas of nuclear insurance law, good governance and claims administration to create a true Centre of Excellence.

Insurer risk control and nuclear liability

Energy Technology Data Exchange (ETDEWEB)

DeMerchant, C. [Nuclear Insurance Association of Canada, Toronto, ON (Canada)

2015-07-01

We specialize in high quality insurance risk management, underwriting and inspections for Canadian nuclear exposures. We provide true risk transfer, secure insurance capacity and collaborate with the world's nuclear experts to create innovative domestic solutions for our clients and members. The benefit of our experience works for all stake holders: insured clients, members, multi-level government agencies and all Canadians. NIAC has a 55-year history of partnering with insurers around the globe to create reliable risk management for the nuclear industry. We offer Canadian risk solutions, thought leadership and expertise that provides security and confidence to our customers and members. NIAC leads in the areas of nuclear insurance law, good governance and claims administration to create a true Centre of Excellence.

Safety/security interface assessments at commercial nuclear power plants

International Nuclear Information System (INIS)

Byers, K.R.; Brown, P.J.; Norderhaug, L.R.

1985-01-01

The findings of the Haynes Task Force Committee (NUREG-0992) are used as the basis for defining safety/security assessment team activities at commercial nuclear power plants in NRC Region V. A safety/security interface assessment outline and the approach used for making the assessments are presented along with the composition of team members. As a result of observing simulated plant emergency conditions during scheduled emergency preparedness exercises, examining security and operational response procedures, and interviewing plant personnel, the team has identified instances where safety/security conflicts can occur

Safety/security interface assessments at commercial nuclear power plants

International Nuclear Information System (INIS)

Byers, K.R.; Brown, P.J.; Norderhaug, L.R.

1985-07-01

The findings of the Haynes Task Force Committee (NUREG-0992) are used as the basis for defining safety/security assessment team activities at commercial nuclear power plants in NRC Region V. A safety/security interface assessment outline and the approach used for making the assessments are presented along with the composition of team members. As a result of observing simulated plant emergency conditions during scheduled emergency preparedness exercises, examining security and operational response procedures, and interviewing plant personnel, the team has identified instances where safety/security conflicts can occur. 2 refs

On things nuclear: the Canadian debate

International Nuclear Information System (INIS)

Mueller, P.G.

1977-01-01

An unbiased overview is given of the nuclear industry in Canada, with emphasis on its history, fundamentals of nuclear power plants and the CANDU reactor system, the need and ideal mix of future energy sources, economics of nuclear power, uranium supplies, radioactive releases, thermal pollution, physical security, and safety of nuclear power plants, and export of CANDU technology vs. nuclear proliferation. (E.C.B.)

Canadian inter-laboratory organically bound tritium (OBT) analysis exercise.

Science.gov (United States)

Kim, S B; Olfert, J; Baglan, N; St-Amant, N; Carter, B; Clark, I; Bucur, C

2015-12-01

Tritium emissions are one of the main concerns with regard to CANDU reactors and Canadian nuclear facilities. After the Fukushima accident, the Canadian Nuclear Regulatory Commission suggested that models used in risk assessment of Canadian nuclear facilities be firmly based on measured data. Procedures for measurement of tritium as HTO (tritiated water) are well established, but there are no standard methods and certified reference materials for measurement of organically bound tritium (OBT) in environmental samples. This paper describes and discusses an inter-laboratory comparison study in which OBT in three different dried environmental samples (fish, Swiss chard and potato) was measured to evaluate OBT analysis methods currently used by CANDU Owners Group (COG) members. The variations in the measured OBT activity concentrations between all laboratories were less than approximately 20%, with a total uncertainty between 11 and 17%. Based on the results using the dried samples, the current OBT analysis methods for combustion, distillation and counting are generally acceptable. However, a complete consensus OBT analysis methodology with respect to freeze-drying, rinsing, combustion, distillation and counting is required. Also, an exercise using low-level tritium samples (less than 100 Bq/L or 20 Bq/kg-fresh) would be useful in the near future to more fully evaluate the current OBT analysis methods. Crown Copyright © 2015. Published by Elsevier Ltd. All rights reserved.

The Canadian Nuclear Safety Commission regulatory process for decommissioning a uranium mining facility

International Nuclear Information System (INIS)

Scissons, K.; Schryer, D.M.; Goulden, W.; Natomagan, C.

2002-01-01

The Canadian Nuclear Safety Commission (CNSC) regulates uranium mining in Canada. The CNSC regulatory process requires that a licence applicant plan for and commit to future decommissioning before irrevocable decisions are made, and throughout the life of a uranium mine. These requirements include conceptual decommissioning plans and the provision of financial assurances to ensure the availability of funds for decommissioning activities. When an application for decommissioning is submitted to the CNSC, an environmental assessment is required prior to initiating the licensing process. A case study is presented for COGEMA Resources Inc. (COGEMA), who is entering the decommissioning phase with the CNSC for the Cluff Lake uranium mine. As part of the licensing process, CNSC multidisciplinary staff assesses the decommissioning plan, associated costs, and the environmental assessment. When the CNSC is satisfied that all of its requirements are met, a decommissioning licence may be issued. (author)

Commercial Spent Nuclear Fuel Waste Package Misload Analysis

International Nuclear Information System (INIS)

J.K. Knudson

2003-01-01

The purpose of this calculation is to estimate the probability of misloading a commercial spent nuclear fuel waste package with a fuel assembly(s) that has a reactivity (i.e., enrichment and/or burnup) outside the waste package design. The waste package designs are based on the expected commercial spent nuclear fuel assemblies and previous analyses (Macheret, P. 2001, Section 4.1 and Table 1). For this calculation, a misloaded waste package is defined as a waste package that has a fuel assembly(s) loaded into it with an enrichment and/or burnup outside the waste package design. An example of this type of misload is a fuel assembly designated for the 21-PWR Control Rod waste package being incorrectly loaded into a 21-PWR Absorber Plate waste package. This constitutes a misloaded 21-PWR Absorber Plate waste package, because the reactivity (i.e., enrichment and/or burnup) of a 21-PWR Control Rod waste package fuel assembly is outside the design of a 21-PWR Absorber Plate waste package. These types of misloads (i.e., fuel assembly with enrichment and/or burnup outside waste package design) are the only types that are evaluated in this calculation. This calculation utilizes information from ''Frequency of SNF Misload for Uncanistered Fuel Waste Package'' (CRWMS M and O 1998) as the starting point. The scope of this calculation is limited to the information available. The information is based on the whole population of fuel assemblies and the whole population of waste packages, because there is no information about the arrival of the waste stream at this time. The scope of this calculation deviates from that specified in ''Technical Work Plan for: Risk and Criticality Department'' (BSC 2002a, Section 2.1.30) in that only waste package misload is evaluated. The remaining issues identified (i.e., flooding and geometry reconfiguration) will be addressed elsewhere. The intended use of the calculation is to provide information and inputs to the Preclosure Safety Analysis

Development of comprehensive waste acceptance criteria for commercial nuclear waste

International Nuclear Information System (INIS)

O'Hara, F.A.; Miller, N.E.; Ausmus, B.S.; Yates, K.R.; Means, J.L.; Christensen, R.N.; Kulacki, F.A.

1979-01-01

A detailed methodology is presented for the identification of the characteristics of commercial nuclear waste which may require criteria. This methodology is analyzed as a six-step process which begins with identification of waste operations and proceeds until the waste characteristics affecting the potential release of radionuclides are determined. All waste types and operations were analyzed using the methodology presented. Several illustrative example are included. It is found that thirty-three characteristics can be identified as possibly requiring criteria

The state of radioactive waste management and personnel radiation exposure in commercial nuclear power plants in fiscal 1981

International Nuclear Information System (INIS)

1982-01-01

Radioactive waste management: The owners of commercial nuclear power plants are obligated to control the release of gaseous and liquid radioactive wastes below the objective release levels, and to store solid wastes in containers on the site. As for the former, the released (radioactive) quantity in fiscal 1981 (from April, 1981, to March, 1982,) together with the objective levels are given for respective nuclear power stations; and as for the latter, the stored quantity and also the cumulative quantity up to the year are given. Radiation exposure: The owners of commercial nuclear power plants are obligated to control the personnel exposure below the permissible level. The personnel exposure dose in fiscal 1981 is given for respective nuclear power station. (Mori, K.)

Canadian small wind market

International Nuclear Information System (INIS)

Moorhouse, E.

2010-01-01

This PowerPoint presentation discussed initiatives and strategies adopted by the Canadian Wind Energy Association (CanWEA) to support the development of Canada's small wind market. The general public has shown a significant interest in small wind projects of 300 kW. Studies have demonstrated that familiarity and comfort with small wind projects can help to ensure the successful implementation of larger wind projects. Small wind markets include residential, farming and commercial, and remote community applications. The results of CanWEA market survey show that the small wind market grew by 78 percent in 2008 over 2007, and again in 2009 by 32 percent over 2008. The average turbine size is 1 kW. A total of 11,000 turbines were purchased in 2007 and 2008. Global small wind market growth increased by 110 percent in 2008, and the average turbine size was 2.4 kW. Eighty-seven percent of the turbines made by Canadian mid-size wind turbine manufacturers are exported, and there is now a significant risk that Canada will lose its competitive advantage in small wind manufacturing as financial incentives have not been implemented. American and Canadian-based small wind manufacturers were listed, and small wind policies were reviewed. The presentation concluded with a set of recommendations for future incentives, educational programs and legislation. tabs., figs.

Reactor safety study. An assessment of accident risks in U.S. commercial nuclear power plants. Executive summary

Energy Technology Data Exchange (ETDEWEB)

NONE

1975-10-01

The Reactor Safety Study was sponsored by the U. S. Atomic Energy Commission to estimate the public risks that could be involved in potential accidents in commercial nuclear power plants of the type now in use. It was performed under the independent direction of Professor Norman C. Rasmussen of the Massachusetts Institute of Technology. The risks had to be estimated, rather than measured, because although there are about 50 such plants now operating, there have been no nuclear accidents to date resulting in significant releases of radioactivity in U.S. commercial nuclear power plants. The objective of the study was to make a realistic estimate of these risks and, to provide perspective, to compare them with non-nuclear risks to which our society and its individuals are already exposed. This information may be of help in determining the future reliance by society on nuclear power as a source of electricity. The results from this study suggest that the risks to the public from potential accidents in nuclear power plants are comparatively small.

Reactor safety study. An assessment of accident risks in U.S. commercial nuclear power plants. Executive summary

International Nuclear Information System (INIS)

1975-10-01

The Reactor Safety Study was sponsored by the U. S. Atomic Energy Commission to estimate the public risks that could be involved in potential accidents in commercial nuclear power plants of the type now in use. It was performed under the independent direction of Professor Norman C. Rasmussen of the Massachusetts Institute of Technology. The risks had to be estimated, rather than measured, because although there are about 50 such plants now operating, there have been no nuclear accidents to date resulting in significant releases of radioactivity in U.S. commercial nuclear power plants. The objective of the study was to make a realistic estimate of these risks and, to provide perspective, to compare them with non-nuclear risks to which our society and its individuals are already exposed. This information may be of help in determining the future reliance by society on nuclear power as a source of electricity. The results from this study suggest that the risks to the public from potential accidents in nuclear power plants are comparatively small

Canadian involvement in international nuclear cooperation

International Nuclear Information System (INIS)

Jennekens, Jon.

1981-01-01

Since 1945 Canada has been actively involved in the development of an international consensus on measures to prevent the proliferation of nuclear weapons. In parallel with this involvement, Canada has entered into cooperation agreements with several countries under which nuclear materials, equipment and facilities have been supplied in connection with the medical, industrial, agricultural and electrical power applications of nuclear energy. This paper summarizes the actions taken by Canada to encourage the peaceful uses of nuclear energy and to avoid the spread of nuclear weapons [fr

Canadian involvement in international nuclear cooperation

International Nuclear Information System (INIS)

Jennekens, J.

1981-01-01

Since 1945 Canada has been actively involved in the development of an international consensus on measures to prevent the proliferation of nuclear weapons. In parallel with this involvement, Canada has entered into cooperative agreements with several countries under which nuclear materials, equipment and facilities have been supplied in connection with the medical, industrial, agricultural and electrical power applications of nuclear energy. This paper summarizes the actions taken by Canada to encourage the peaceful uses of nuclear energy and to avoid the spread of nuclear weapons. (author)

Qualifying commercial grade instruments for use in nuclear power generating stations

International Nuclear Information System (INIS)

Lamothe, R.J.; Scally, C.R.

1983-01-01

Nuclear environmental qualification of instrumentation has been successfully accomplished by many commercial grade equipment manufacturers. This paper was prepared as a guide to those manufacturers who want some insight into a qualification program. The areas addressed are the regulations and documents, the qualification program, and a case history of a chart recorder qualifications. The principal standards relating to a nuclear qualification program are IEEE Std. 323-1974 IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations, IEEE Std. 344-1975 IEEE Recommended Practices for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations and 10CFR50.49. Previously NUREG 0588 Interim Staff Position on Environmental Qualification of Safety-Related Equipment. These define the intent and purpose of the qualification. The qualification program itself consists of several distinct parts which require explanation, including the determination of qualified life, choice of test samples, selection of appropriate acceptance criteria, aging program, radiation testing, seismic testing, abnormal environment tests and others. The case history illustrates the qualification program and the thought processes involved

Cross-border issues that arise in conjunction with the execution of U.S.-Canadian natural gas contracts

International Nuclear Information System (INIS)

Martin, J. G.

1999-01-01

Development of the U.S.-Canadian natural gas market as it is today and the issues that may arise in cross-border transactions involving natural gas contracts between the two countries are reviewed. In this context, the paper reviews recent history of U.S.-Canadian trade relations culminating in the development of NAFTA, the U.S. regulatory and legislative framework surrounding cross-border natural gas transactions, and general U.S. foreign trade policy that may come into play at the U.S.- Canada border. The paper also examines certain issues arising in the U.S. commercial context that may be of interest to Canadian corporations, specifically the U.S. Uniform Commercial Code, state jurisdiction on the U.S. side of the border, state and federal tax concerns, and the mechanics and potential benefits for a Canadian parent company in forming a U.S.-based subsidiary to handle U.S.-Canada natural gas transactions. 71 refs

The structure of the nuclear industry

International Nuclear Information System (INIS)

Leaist, G.T.; Morisette, E.F.

1981-01-01

Since 1952, when Canadians began to study the application of reactors to power generation, the CANDU reactor design and the manufacturing and and engineering capability supporting it have evolved into a world-class technology. At present, Atomic Energy of Canada Ltd. works directly with provincial electrical utilities in developing their power reactor requirements. It assumes responsibility for the detailed design of the nuclear steam supply system of stations, undertakes some procurement activities, and may represent the utilities in licensing applications. The detailed design and supply of components for the remainder of the nuclear steam plant, as well as for the secondary plant, are provided in Ontario by Ontario Hydro together with manufacturers, and in Quebec and New Brunswick by private firms. Canadian utilities have always assumed the project managment function themselves, but with export sales AECL has taken turnkey responsiblity for either the nuclear steam plant or the complete power station. AECL owns design specifications and other documentation, the use of which it can license, but manufacturing technology resides with Canadian industry. Canadian manufacturers have supported AECL design licensing initiatives overseas. The Canadian nuclear industry's major problem is the current lack of a vigorous domestic market combined with an uncertain international one

The problematic of nuclear wastes

International Nuclear Information System (INIS)

Rozon, D.

2004-01-01

Within the frame of a project of modification of radioactive waste storage installations, and of refurbishing the Gentilly-2 nuclear plant (Quebec, Canada), the author first gives an overview and comments assessments of the volume and nature of nuclear wastes produced by Canadian nuclear power plants. He presents the Canadian program of nuclear waste management (history, Seaborn assessment Commission, mission of the SGDN-NWMO). He discusses the relationship between risk and dose, the risk duration, and the case of non radioactive wastes. He discusses energy challenges in terms of CO 2 emissions and with respect to climate change, proposes an alternative scenario on a long term, compares nuclear energy and wind energy, and discusses the nuclear technology evolution

Learning effects and the commercialization of new energy technologies: the case of nuclear power

International Nuclear Information System (INIS)

Zimmerman, M.B.

1982-01-01

Recently, attention has been focused on government policy toward commercialization of new energy technologies. Arguments are offered that, in the early days of commercialization, significant learning externalities that justify subsidy are present. Using nuclear power as a case study, this article estimates the learning effects actually present. The effect of experience on construction cost and on the accuracy of cost estimation is examined. External learning is separated from internalized learning about both construction cost and cost estimation. Finally, an estimate of the value of both kinds of learning externality is provided. The results suggest learning externalities were present, but had little effect on the rate of commercialization. 19 references, 5 tables

Cost structure analysis of commercial nuclear power plants in Japan based on corporate financial statements of electric utility companies

International Nuclear Information System (INIS)

Kunitake, Norifumi; Nagano, Koji; Suzuki, Tatsujiro

1998-01-01

In this paper, we analyze past and current cost structure of commercial nuclear power plants in Japan based on annual corporate financial statements published by the Japanese electric utility companies, instead of employing the conventional methodology of evaluating the generation cost for a newly constructed model plant. The result of our study on existing commercial nuclear plants reveals the increasing significance of O and M and fuel cycle costs in total generation cost. Thus, it is suggested that electric power companies should take more efforts to reduce these costs in order to maintain the competitiveness of nuclear power in Japan. (author)

Nuclear power in Canada: questions and answers

International Nuclear Information System (INIS)

1975-01-01

To further public understanding of nuclear power generation, the Canadian Nuclear Association commissioned a special task force to coordinate contributions of experts in all parts of the nuclear industry. These contributions have been arranged in a question and answer format and are aimed at the average Canadian reader who is genuinely seeking factual information on nuclear power. Areas covered include electricity demand, comparison of nuclear generation with other forms of thermal electricity production, radiation sources and effects on man and his environment; features of different reactor types, thermal discharges and waste management. (O.T.)

Expressive freedom and tobacco advertising: a Canadian perspective.

Science.gov (United States)

Manfredi, Christopher P

2002-03-01

In 1989, Canada enacted the Tobacco Products Control Act (TPCA), which prohibited tobacco advertising, required health warnings on tobacco packaging, and restricted promotional activities. Canada's tobacco companies challenged the TPCA's constitutionality, arguing that it infringed on freedom of expression. Although it seemed likely that the Canadian Supreme Court would uphold the legislation, in 1995 the court declared the impugned provisions to be unconstitutional. The decision is testimony to the constraining force of liberalism on tobacco regulation, but it is also evidence of the power of political will. While the Canadian government could have used the decision to justify withdrawing from further confrontations with powerful commercial interests, it chose instead to enact new tobacco control legislation in 1997.

Nuclear scientists and engineers in Canada - A coming shortage?

International Nuclear Information System (INIS)

Stoll, P.

1995-01-01

A survey of large Canadian employers was used to identify the current level of employment of engineers and scientists in applications of nuclear technology. The survey assessed the labour market implications of three alternative future scenarios for the industry over the period 1994-2009 to determine the capability of the industry to maintain a competitive Canadian presence in domestic and international markets for nuclear generating facilities. The study found that under the nuclear phase-out and no-growth scenarios the requirements for nuclear experts decline from present levels of employment, but the Canadian industry retains to ability to meet an eventual renewed demand for CANDU generating systems. Under the growth scenario, requirements for nuclear scientists and engineers increase, although at a rate which can be met from domestic sources. The Canadian situation was compared with that in other OECD countries, as assessed by a study conducted by the OECD/NEA. According to this source, labour market conditions for nuclear qualified human resources in most participating OECD member countries resemble those of Canada. (author). 3 refs, 2 figs, 4 tabs

Occupational radiation exposure at commercial nuclear power reactors, 1981. Annual report

International Nuclear Information System (INIS)

Brooks, B.G.

1982-11-01

This report presents an updated compilation of occupational radiation exposures at commercial nuclear power reactors for the years 1969 through 1981. This year's report contains data received from the 70 light water cooled reactors (LWRs) and one high temperature gas cooled reactor that had been declared to be in commercial operation for at least one full year as of December 31, 1981. This represents an increase of two reactors over the number contained in last year's report. The total number of personnel monitored at LWRs in 1981 was 124,504, a slight decrease from that found in 1980. The number of workers that received measurable doses during 1981 was 82,183 which is about 2000 more than that found in 1980. The total collective dose at LWRs for 1981 is estimated to be 54,142 man-rems, which is only about 350 man-rems more than that reported in 1980. The report also presents a summary and some analyses of the exposure data contained in the termination reports that have been submitted by nuclear power licensees to the Commission pursuant to 10 CFR Section 20.408. As of December 31, 1981, personal identification and exposure information had been collected and computerized for some 210,000 of these terminating reactor personnel

Nuclear knowledge management strategies in Canada

International Nuclear Information System (INIS)

Torgerson, D.F.; Aly, A.M.M.; Shalaby, B.

2004-01-01

An effective knowledge management strategy must encompass three basic elements; a sound resource management and training strategy to maintain nuclear competency in the face of accelerated retirements of current generation of experts and the development of advanced products, effective engineering tools to preserve the current technology and design basis and effective information management systems to facilitate pooling and sharing of information amongst different entities. The Canadian Nuclear Industry and its regulatory agency, the Canadian Nuclear Safety Commission (CNSC) recognized the importance of nuclear knowledge management and have already implemented a number of initiatives, in order to maintain competency, capture and preserve existing knowledge, advance the nuclear technology, develop future nuclear workers and maintain a critical R and D capability. The paper describes activities and initiatives undertaken or in progress in Canada in order to ensure a smooth transition of nuclear knowledge to the next generation of nuclear workers. Although this paper intends to address the Canadian scene in general, special emphasis will be placed on activities currently underway at Atomic Energy of Canada Limited (AECL) as the design authority and guardian of the CANDU technology. (author)

SP-100 nuclear space power systems with application to space commercialization

International Nuclear Information System (INIS)

Smith, J.M.

1988-01-01

The purpose of this paper is to familiarize the Space Commercialization Community with the status and characteristics of the SP-100 space nuclear power system. The program is a joint undertaking by the Department of Defense, the Department of Energy and NASA. The goal of the program is to develop, validate, and demonstrate the technology for space nuclear power systems in the range of 10 to 1000 kWe electric for use in the future civilian and military space missions. Also discussed are mission applications which are enhanced and/or enabled by SP-100 technology and how this technology compares to that of more familiar solar power systems. The mission applications include earth orbiting platforms and lunar/Mars surface power

Summary of inspection findings of licensee inservice testing programs at United States commercial nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Dunlop, A.; Colaccino, J.

1996-12-01

Periodic inspections of pump and valve inservice testing (IST) programs in United States commercial nuclear power plants are performed by Nuclear Regulatory Commission (NRC) Regional Inspectors to verify licensee regulatory compliance and licensee commitments. IST inspections are conducted using NRC Inspection Procedure 73756, {open_quotes}Inservice Testing of Pumps and Valves{close_quotes} (IP 73756), which was updated on July 27, 1995. A large number of IST inspections have also been conducted using Temporary Instruction 2515/114, {open_quotes}Inspection Requirements for Generic Letter 89-04, Acceptable Inservice Testing Programs{close_quotes} (TI-2515/114), which was issued January 15, 1992. A majority of U.S. commercial nuclear power plants have had an IST inspection to either IP 73756 or TI 2515/114. This paper is intended to summarize the significant and recurring findings from a number of these inspections since January of 1990.

Nuclear-powered submarines

International Nuclear Information System (INIS)

Curren, T.

1989-01-01

The proposed acquisition of nuclear-powered submarines by the Canadian Armed Forces raises a number of legitimate concerns, including that of their potential impact on the environment. The use of nuclear reactors as the propulsion units in these submarines merits special consideration. Radioactivity, as an environmental pollutant, has unique qualities and engenders particular fears among the general population. The effects of nuclear submarines on the environment fall into two distinct categories: those deriving from normal operations of the submarine (the chief concern of this paper), and those deriving from a reactor accident. An enormous body of data must exist to support the safe operation of nuclear submarines; however, little information on this aspect of the proposed submarine program has been made available to the Canadian public. (5 refs.)

A nuclear engineering curriculum for Asia-Pacific

International Nuclear Information System (INIS)

Bereznai, G.; Sumitra, T.; Chankow, N.; Chanyotha, S.

1996-01-01

This paper describes the nuclear engineering education and professional development curricula that are being developed at Chulalongkorn University in Bangkok, Thailand. The program was initiated in response to the Thai Government's policy to keep the option of nuclear electric generation available as the country responds to the rapid growth of industrialization and increased standard of living, and the accompanying increase in electricity consumption. The program has three main thrusts: university education, professional development, and public education. Although this paper concentrates on the university curriculum, it is shown how the university program is integrated with the development of industry professionals. The Nuclear Engineering Curricula being developed and implemented at Chulalongkorn University will offer programs at the Bachelor, Master and Doctorate levels. The curricula are designed to provide comprehensive education and training for engineers and scientists planning careers in the peaceful use of nuclear energy, with emphasis on the applications to industry and for nuclear electric generation. The Project of Human Resource Development in the Nuclear Engineering field is the result of a cooperative effort between agencies of the Thai and Canadian Governments, including the Electricity Generating Authority of Thailand, the Office of Atomic Energy for Peace, Chulalongkorn University and several other Thai Universities; Atomic Energy of Canada Limited, the Canadian International Development Agency, several Canadian Universities as well as members of the Canadian Nuclear Industry. (author)

Nevada commercial spent nuclear fuel transportation experience

International Nuclear Information System (INIS)

1991-09-01

The purpose of this report is to present an historic overview of commercial reactor spent nuclear fuel (SNF) shipments that have occurred in the state of Nevada, and to review the accident and incident experience for this type of shipments. Results show that between 1964 and 1990, 309 truck shipments covering approximately 40,000 miles moved through Nevada; this level of activity places Nevada tenth among the states in the number of truck shipments of SNF. For the same period, 15 rail shipments moving through the State covered approximately 6,500 miles, making Nevada 20th among the states in terms of number of rail shipments. None of these shipments had an accident or an incident associated with them. Because the data for Nevada are so limited, national data on SNF transportation and the safety of truck and rail transportation in general were also assessed

Status of commercial nuclear high-level waste disposal. Special report

International Nuclear Information System (INIS)

Dau, G.J.; Williams, R.F.

1976-09-01

The results of this review, presented in the form of a functional description of high level waste management system, shows that technology is available to dispose of nuclear waste safely by several different processes. The most attractive alternative in terms of available technology and shortness of time to demonstrate it at commercial scale is a system that converts the waste to a solid by immobilizing the radioactive elements in a glass matrix. Brief comments are also given on international efforts in high level waste management and advanced disposal concepts

Exporting the Canadian licensing program

International Nuclear Information System (INIS)

Whelan, D.J.

1981-06-01

This paper deals with the problems of an overseas regulatory agency in licensing a Canadian-supplied nuclear plant which is referenced to a plant in Canada. Firstly, the general problems associated with the use of a reference plant are discussed. This is followed by a discussion of specific problems which arise from the licensing practices in Canada. The paper concludes with recommendations to simplify the task of demonstrating the licensability of an overseas CANDU plant

Opting out of the commercial use of nuclear power in Germany and challenges arising to nuclear supervision

International Nuclear Information System (INIS)

Renneberg, W.

2001-01-01

The governing majority in Germany has decided to opt out of the commercial use of nuclear power and to terminate this use in a safe and managed way. In the opinion of the federal government, the reasons for this decision include the potential for severe accidents, which is considered intolerable in the long run even though the probability of occurrence is low. In addition, there are the problems of final storage of radioactive waste, issues associated with the risk of proliferation, and the need to end a deep-seated societal conflict in Germany. In its function as the Top Regulator, the department responsible for nuclear matters of the Federal Ministry for the Environment, Nature Conservation, and Nuclear Safety (BMU) has two important functions: It acts as the federal supervisor of the federal states which execute the Atomic Energy Act on behalf of the federal government, and it exercises the duty of preparing the nuclear policy outlined in the norms established by the federal government. After lengthy discussions with the operators of nuclear power plants an agreement was elaborated in preparation of a solution acceptable to all participants, which essentially defines an electricity quota for nuclear power plant operation and deals with spent fuel and nuclear waste management problems. This implies a number of challenges arising to the BMU as a consequence of the need to further ensure a high safety standard. It also means international efforts as well as the need to counteract the impending loss of competence in the nuclear field. (orig.) [de

Probabilistic safety assessment technology for commercial nuclear power plant security evaluation

International Nuclear Information System (INIS)

Liming, J.K.; Johnson, D.H.; Dykes, A.A.

2004-01-01

Commercial nuclear power plant physical security has received much more intensive treatment and regulatory attention since September 11, 2001. In light of advancements made by the nuclear power industry in the field of probabilistic safety assessment (PSA) for its power plants over that last 30 years, and given the many examples of successful applications of risk-informed regulation at U. S. nuclear power plants during recent years, it may well be advisable to apply a 'risk-informed' approach to security management at nuclear power plants from now into the future. In fact, plant PSAs developed in response to NRC Generic Letter 88-20 and related requirements are used to help define target sets of critical plant safety equipment in our current security exercises for the industry. With reasonable refinements, plant PSAs can be used to identify, analyze, and evaluate reasonable and prudent approaches to address security issues and associated defensive strategies at nuclear power plants. PSA is the ultimate scenario-based approach to risk assessment, and thus provides a most powerful tool in identifying and evaluating potential risk management decisions. This paper provides a summary of observations of factors that are influencing or could influence cost-effective or 'cost-reasonable' security management decision-making in the current political environment, and provides recommendations for the application of PSA tools and techniques to the nuclear power plant operational safety response exercise process. The paper presents a proposed framework for nuclear power plant probabilistic terrorist risk assessment that applies these tools and techniques. (authors)

Safeguards Guidance for Designers of Commercial Nuclear Facilities – International Safeguards Requirements for Uranium Enrichment Plants

Energy Technology Data Exchange (ETDEWEB)

Philip Casey Durst; Scott DeMuth; Brent McGinnis; Michael Whitaker; James Morgan

2010-04-01

For the past two years, the United States National Nuclear Security Administration, Office of International Regimes and Agreements (NA-243), has sponsored the Safeguards-by-Design Project, through which it is hoped new nuclear facilities will be designed and constructed worldwide more amenable to nuclear safeguards. In the course of this project it was recognized that commercial designer/builders of nuclear facilities are not always aware of, or understand, the relevant domestic and international safeguards requirements, especially the latter as implemented by the International Atomic Energy Agency (IAEA). To help commercial designer/builders better understand these requirements, a report was prepared by the Safeguards-by-Design Project Team that articulated and interpreted the international nuclear safeguards requirements for the initial case of uranium enrichment plants. The following paper summarizes the subject report, the specific requirements, where they originate, and the implications for design and construction. It also briefly summarizes the established best design and operating practices that designer/builder/operators have implemented for currently meeting these requirements. In preparing the subject report, it is recognized that the best practices are continually evolving as the designer/builder/operators and IAEA consider even more effective and efficient means for meeting the safeguards requirements and objectives.

Can we Plan. The political economy of commercial nuclear energy policy in the United States

International Nuclear Information System (INIS)

Campbell, J.L. Jr.

1984-01-01

The dissertation is an analysis of the commercial nuclear energy sector's decline in the United States. The research attempts to reconcile the debate between Weberian-institutional and Marxist political theory about the state's inability to successfully plan industrial development in advanced capitalist countries. Synthesizing these views, the central hypothesis guiding the research is that the greater the state's relative autonomy from political and economic constraints in an institutional sense, i.e., the greater its insulation from the contradictions of capitalism and democracy, the greater its planning capacity and the more successful it will be in directing industrial performance. The research examines one industrial sector, commercial nuclear energy, and draws two major comparison. First, the French and US nuclear industries are compared, since the state's relative autonomy is much greater in the former than in the latter. This comparison is developed to identify policy areas where nuclear planning has succeeded in France but failed in America. Four areas are identified: reactor standardization, waste management, reactor safety, and financing. Second, looking particularly at the US, the policy areas are compared to analyze the development of policy and its effects on the sector's performance and to determine the degree to which planning was undermined by the structural constraints characteristic of a state with low relative autonomy

Lessons learned in planning the Canadian Nuclear Legacy Liabilities Program

International Nuclear Information System (INIS)

Stephens, M.; Brooks, S.; Miller, J.; Neal, P.; Mason, R.

2011-01-01

In 2006, Atomic Energy of Canada Limited (AECL) and Natural Resources Canada (NRCan) began implementing a $7B CDN, 70-year Nuclear Legacy Liabilities Program (NLLP) to deal with legacy decommissioning and environmental issues at AECL nuclear sites. The objective of the NLLP is to safely and cost-effectively reduce the nuclear legacy liabilities and associated risks based on sound waste management and environmental principles in the best interest of Canadians. The NLLP comprises a number of interlinked decommissioning, waste management and environmental restoration activities that are being executed at different sites by various technical groups. Many lessons about planning and executing such a large, diverse Program have been learned in planning the initial five-year 'start-up' phase (concluded 2011 March), in planning the three-year second phase (currently being commenced), and in planning individual and interacting activities within the Program. The activities to be undertaken in the start-up phase were planned by a small group of AECL technical experts using the currently available information on the liabilities. Several internal and external reviews of the Program during the start-up phase examined progress and identified several improvements to planning. These improvements included strengthening communications among the groups within the Program, conducting more detailed advance planning of the interlinked activities, and being cautious about making detailed commitments for activities for which major decisions had yet to be made. The second phase was planned by a dedicated core team. More and earlier input was solicited from the suppliers than in the planning for the first phase. This was to ensure that the proposed program of work was feasible, and to be able to specify in more detail the resources that would be required to carry it out. The NLLP has developed several processes to assist in the detailed planning of the numerous projects and

American commercial nuclear power industry programs, work processes, and organizational changes

International Nuclear Information System (INIS)

Reynerson, D.M.

1995-01-01

The American electric utility industry is undergoing a continuing series of regulatory and commercial changes unprecedented in the recent history of the industry. The changes are resulting in an industrywide examination of all facets of the business including the arena of operations and maintenance costs in conjunction with the nuclear facilities. The very viability of most nuclear facilities to a large extent depends on the effective implementation of program, process, and organizational reviews. These reviews, in one form or another, are under way at a number of facilities sometimes as a open-quotes stand-alone activityclose quotes and as often as not as a portion of a corporate and firmwide initiative. The impetus is coming from the marketplace, and both major challenges and opportunities are encompassed by the changes

Winning public and political support for nuclear

International Nuclear Information System (INIS)

McFadden, D.J.

2006-01-01

The nuclear industry is entering an historic battle for the hearts and minds of Canadians as government decides on nuclear new build. Recent polls indicate that public support is rising for nuclear power. However, the support could be eroded by negative events or intense lobbying by anti-nuclear groups. The nuclear industry must deal with concerns raised about nuclear power, such as cost, safety, reliability and waste. The nuclear industry should build upon the positive movement in public support. The industry must go to Canadians with a credible message which responds effectively to public concerns. It must be remembered that winning public support will be essential to winning and maintaining political support. (author)

Winning public and political support for nuclear

Energy Technology Data Exchange (ETDEWEB)

McFadden, D.J. [Gowling LaFleur Henderson, LLP, Toronto, Ontario (Canada)

2006-07-01

The nuclear industry is entering an historic battle for the hearts and minds of Canadians as government decides on nuclear new build. Recent polls indicate that public support is rising for nuclear power. However, the support could be eroded by negative events or intense lobbying by anti-nuclear groups. The nuclear industry must deal with concerns raised about nuclear power, such as cost, safety, reliability and waste. The nuclear industry should build upon the positive movement in public support. The industry must go to Canadians with a credible message which responds effectively to public concerns. It must be remembered that winning public support will be essential to winning and maintaining political support. (author)

Manufacturing opportunities in the Canadian CANDU and heavy water programs

International Nuclear Information System (INIS)

Reny, J.P.

The volume of business available to Canadian manufacturers of CANDU power plant and heavy water plant components is analyzed over about the next 10 years. Implications of exported nuclear technology and plants are explored. (E.C.B.)

The nuclear engineering programmes at the Royal Military College of Canada. Part II

Energy Technology Data Exchange (ETDEWEB)

Bonin, H.W. [Royal Military College of Canada, Dept. of Chemistry and Chemical Engineering, Kingston, Ontario (Canada)

2002-08-01

The coverage of the activities within the nuclear science and engineering programmes at RMC reveals the dynamism of the College which is still growing at a fast rate. Being the only completely bilingual university in Canada and a true national institution gathering students and staff from all parts of the country. RMC continues in its mission to support the Canadian Forces, the Department of National Defence, the people of Canada and Canadian Industry that includes the nuclear sector. It is in this spirit that the staff has been actively involved with organizations such as the Canadian Nuclear Society and the Canadian Nuclear Association, having hosted four of the Student conferences and three major topical conferences of the CNS.

The nuclear engineering programmes at the Royal Military College of Canada. Part II

International Nuclear Information System (INIS)

Bonin, H.W.

2002-01-01

The coverage of the activities within the nuclear science and engineering programmes at RMC reveals the dynamism of the College which is still growing at a fast rate. Being the only completely bilingual university in Canada and a true national institution gathering students and staff from all parts of the country. RMC continues in its mission to support the Canadian Forces, the Department of National Defence, the people of Canada and Canadian Industry that includes the nuclear sector. It is in this spirit that the staff has been actively involved with organizations such as the Canadian Nuclear Society and the Canadian Nuclear Association, having hosted four of the Student conferences and three major topical conferences of the CNS

Stochastic sensitivity analysis of the biosphere model for Canadian nuclear fuel waste management

International Nuclear Information System (INIS)

Reid, J.A.K.; Corbett, B.J.

1993-01-01

The biosphere model, BIOTRAC, was constructed to assess Canada's concept for nuclear fuel waste disposal in a vault deep in crystalline rock at some as yet undetermined location in the Canadian Shield. The model is therefore very general and based on the shield as a whole. BIOTRAC is made up of four linked submodels for surface water, soil, atmosphere, and food chain and dose. The model simulates physical conditions and radionuclide flows from the discharge of a hypothetical nuclear fuel waste disposal vault through groundwater, a well, a lake, air, soil, and plants to a critical group of individuals, i.e., those who are most exposed and therefore receive the highest dose. This critical group is totally self-sufficient and is represented by the International Commission for Radiological Protection reference man for dose prediction. BIOTRAC is a dynamic model that assumes steady-state physical conditions for each simulation, and deals with variation and uncertainty through Monte Carlo simulation techniques. This paper describes SENSYV, a technique for analyzing pathway and parameter sensitivities for the BIOTRAC code run in stochastic mode. Results are presented for 129 I from the disposal of used fuel, and they confirm the importance of doses via the soil/plant/man and the air/plant/man ingestion pathways. The results also indicate that the lake/well water use switch, the aquatic iodine mass loading parameter, the iodine soil evasion rate, and the iodine plant/soil concentration ratio are important parameters

Canadian accelerator breeder system development

International Nuclear Information System (INIS)

Schriber, S.O.

1982-11-01

A shortage of fissile material at a reasonable price is expected to occur in the early part of the twenty-first century. Converting fertile material to fissile material by electronuclar methods is an option that can extend th world's resources of fissionable material, supplying fuel for nuclear power stations. This paper presents the rationale for electronuclear breeders and describes the Canadian development program for an accelerator breeder facility that could produce 1 Mg of fissile material per year

Nuclear energy's continuing benefits to Canada

International Nuclear Information System (INIS)

Gray, J.L.

1981-06-01

The goal of the Canadian nuclear power program when it began twenty years ago was to reduce Canadian dependence on imported coal. This goal has been met, with 35 percent of Ontario's electricity being produced by CANDU reactors. These reactors have been proven reliable and safe, and provide a considerable cost advantage over coal. The CANDU reactor was developed with the strengths and limitations of Canadian industry in mind, the newest stations have over 85 percent Canadian-manufactured components. A similar benefit should be found in many countries with manufacturing capabilities comparable to Canada's. The use of natural uranium as a fuel has been a wise choice both technically and economically. A new industry was created in Canada in order to gain an assured supply of heavy water. The personnel brought to or trained in Canada to work in all parts of the nuclear industry represent a valuable asset in themselves. Radioisotope exports are making a significant contribution. Nuclear power is likely to make its greatest impact in the next century, when it will be a necessity

Microbial issues pertaining to the Canadian concept for the disposal of nuclear fuel waste

International Nuclear Information System (INIS)

Stroes-Gascoyne, S.; West, J.M.

1994-03-01

AECL Research is developing a concept for the permanent disposal of nuclear fuel waste in plutonic rock of the Canadian Shield. The Federal Environmental Assessment Review Panel has issued a set of guidelines to be used by AECL Research in preparing an Environmental Impact Statement (EIS) for this concept. These guidelines require that the EIS address a number of microbiological factors and their potential to affect the integrity of the multiple barrier system on which the disposal concept is based. This report formulates a number of views and positions on microbiological factors that could influence the performance of a disposal vault in plutonic rock. Microbiological factors discussed include the presence and survival of microbes, biofilms, corrosion, biodegradation (of emplaced materials), gas production, geochemical changes, radionuclides migration, colloid formation, mutation, pathogens and methylation. Not all issues can be fully resolved with the current state of knowledge. Studies being performed to underscore and strengthen current knowledge are briefly discussed. (author). 92 refs., 1 tab

Government, utilities, industry and universities: partners for nuclear development in Canada and abroad

International Nuclear Information System (INIS)

Hurst, D.G.; Woolston, J.E.

1971-09-01

In Canada, eleven power reactors installed or committed at four sites will provide 5 520 MW(e) for an investment of $1 800 million. Uranium production during the decade 1958-1967 totalled 79 700 tonnes U 3 O 8 worth $1 621 million. For nuclear research, development and control, the federal government employs about 6 000 people and spends about $80 million/year which includes the cost of operating three major research reactors (> 30 MW each). Aggregate commercial isotope production has reached 14 megacuries, and Canada has about 3 000 licensed users. Three power and two research reactors of Canadian design are or will be installed in developing countries overseas. Legislation in 1946 made atomic energy a federal responsibility and established an Atomic Energy Control Board. The Board's regulations, which deal primarily with health, safety and security, are administered with the co-operation of appropriate departments of the federal and provincial governments. Large-scale nuclear research began in 1941 and continued under the National Research Council until 1952 when the federal government created a public corporation, Atomic Energy of Canada Limited, to take over both research and the exploitation of atomic energy. Another public corporation, Eldorado Nuclear Limited, conducts research and development on the processing of uranium and operates Canada's only uranium refinery, but prospecting and mining is undertaken largely by private companies. The publicly owned electrical utilities of Ontario and Quebec operate nuclear power stations and participate, with governments, in their financing. Private industry undertakes extensive development and manufacturing, mainly under contract to Atomic Energy of Canada Limited and the utilities, and industry has formed its own Canadian Nuclear Association. Canadian universities undertake nuclear research, and receive significant government support; one has operated a research reactor since 1959. Canada's nuclear program is

Aging management guideline for commercial nuclear power plants-pumps

International Nuclear Information System (INIS)

Booker, S.; Katz, D.; Daavettila, N.; Lehnert, D.

1994-03-01

This Aging Management Guideline (AMG) describes recommended methods for effective detection and mitigation of age-related degradation mechanisms in BWR and PWR commercial nuclear power plant pumps important to license renewal. The intent of this AMG is to assist plant maintenance and operations personnel in maximizing the safe, useful life of these components. It also supports the documentation of effective aging management programs required under the License Renewal Rule 10 CFR Part 54. This AMG is presented in a manner that allows personnel responsible for performance analysis and maintenance to compare their plant-specific aging mechanisms (expected or already experienced) and aging management program activities to the more generic results and recommendations presented herein

Aging management guideline for commercial nuclear power plants-pumps

Energy Technology Data Exchange (ETDEWEB)

Booker, S.; Katz, D.; Daavettila, N.; Lehnert, D. [MDC-Ogden Environmental and Energy Services, Southfield, MI (United States)

1994-03-01

This Aging Management Guideline (AMG) describes recommended methods for effective detection and mitigation of age-related degradation mechanisms in BWR and PWR commercial nuclear power plant pumps important to license renewal. The intent of this AMG is to assist plant maintenance and operations personnel in maximizing the safe, useful life of these components. It also supports the documentation of effective aging management programs required under the License Renewal Rule 10 CFR Part 54. This AMG is presented in a manner that allows personnel responsible for performance analysis and maintenance to compare their plant-specific aging mechanisms (expected or already experienced) and aging management program activities to the more generic results and recommendations presented herein.

Nuclear power - assures the energy future. V. 1

International Nuclear Information System (INIS)

1982-01-01

This volume presents summaries of the addresses given by the chairman and the president of the Canadian Nuclear Association, as well as reports of the CNA economic development, education and manpower, international affairs, legislative, public affairs, safety and environment, social issues, and technology committees. The annual reports of the CNA council and the Canadian Nuclear Society are also given

Nuclear issues in the Canadian energy context

Energy Technology Data Exchange (ETDEWEB)

1979-01-01

Participants holding a wide spectrum of views and representing the nuclear industry, churches, anti-nuclear groups, and the general public participated in sessions on the ethics of nuclear power, waste disposal, health and environmental effects of energy development, decision making and the regulatory process, and the economics of nuclear and other energy sources.

A study of supply-chain capabilities in the Canadian wind power industry

International Nuclear Information System (INIS)

Wittholz, H.; Pan, D.

2004-11-01

In recent years, Canadian wind energy has developed to a total installed capacity of 439 MW. It is possible that by 2012, the cumulative installed wind power capacity may reach 5,600 MW, representing an investment of $8.4 billion. This analysis of the supply-chain structure in the life cycle of a wind farm identified many potential areas where Canadian companies can offer services. Opportunities for both manufacturers and service providers were presented. It was emphasized that although wind energy is a growth industry, Canada has not participated in the development and commercialization of large wind turbine technology. The technical barriers facing Canadian suppliers regarding wind turbine generator (WTG) assembly and component manufacturing were presented. Currently, Canada imports all large WTGs and components. In order to maximize benefits to the Canadian economy, it was recommended that Canadian companies acquire European technology through licences, joint ventures or foreign investment. Technology transfer funding, training and technical assistance funding, tax incentives for capital equipment and support to universities and colleges were also recommended. It was suggested that Canadian companies should focus on manufacturing rotor blades, towers, base frames, nacelle covers and spinners, flexible drive shafts, disk brakes, vibration mounts, inverters, control cabinets, and generators. tabs., figs

Nuclear industry prospects: A Canadian perspective

International Nuclear Information System (INIS)

Morden, Reid

1995-01-01

Canada, with its proven, safe and versatile CANDU reactor is well poised for the second half-century of nuclear fission. Canada's nuclear pedigree goes back to the turn-of-the-century work of Ernest Rutherford in Montreal. This year, Canada's nuclear industry celebrates the 50th anniversary of the start-up of its first research reactor at Chalk River. Last year, the pioneering work of Bert ram Blockhouse in Physics was honoured with a Nobel Prize. Future international success for the nuclear industry, such as has been achieved here in Korea, depends on continued cooperative and collaborative team work between the public and private sectors, continued strong research and development backing by the government, and new strategic partnerships. The biggest challenge is financing for the emerging markets. The brightness or dimness of future prospects are relative to the intensity of the lessons learned from history. In Canada we have a fairly long nuclear pedigree, It goes back almost a century to 1898, when Ernest Rutherford set up a world centre at McGill University in Montreal for research into the structure of the atom and into radioactivity

Why a criminal ban? Analyzing the arguments against somatic cell nuclear transfer in the Canadian parliamentary debate.

Science.gov (United States)

Caulfield, Timothy; Bubela, Tania

2007-02-01

Somatic cell nuclear transfer (SCNT) remains a controversial technique, one that has elicited a variety of regulatory responses throughout the world. On March 29, 2005, Canada's Assisted Human Reproduction Act came into force. This law prohibits a number of research activities, including SCNT. Given the pluralistic nature of Canadian society, the creation of this law stands as an interesting case study of the policy-making process and how and why a liberal democracy ends up making the relatively rare decision to use a statutory prohibition, backed by severe penalties, to stop a particular scientific activity. In this article, we provide a comprehensive and systematic legal analysis of the legislative process and parliamentary debates associated with the passage of this law.

Nuclear 101, a course on the nuclear sector for workers in the nuclear sector

Energy Technology Data Exchange (ETDEWEB)

Donev, J.M.K.C., E-mail: jason.donev@ucalgary.ca [Univ. of Calgary, Calgary, AB (Canada); Boreham, D.; Day, S., E-mail: boreham@mcmaster.ca, E-mail: dayse@mcmaster.ca [McMaster Univ., Hamilton, ON (Canada); Dranga, R.; Krasznai, J.; Matthews, R.; Whitlock, J. [Atomic Energy of Canada Limited, Chalk River, ON (Canada)

2014-07-01

People who work in the nuclear science and technology community are often called upon in social situations to answer questions about the nuclear industry outside their area of direct expertise. In 2012 the Canadian Nuclear Society created 'Nuclear 101', a two-day general-level course to provide more information on the nuclear sector to people who are part of the nuclear science and technology community. This paper will discuss how Nuclear 101 aids public outreach discussions and the lessons learned after two years of operation, and will look at future directions for the course. (author)

Nuclear 101, a course on the nuclear sector for workers in the nuclear sector

International Nuclear Information System (INIS)

Donev, J.M.K.C.; Boreham, D.; Day, S.; Dranga, R.; Krasznai, J.; Matthews, R.; Whitlock, J.

2014-01-01

People who work in the nuclear science and technology community are often called upon in social situations to answer questions about the nuclear industry outside their area of direct expertise. In 2012 the Canadian Nuclear Society created 'Nuclear 101', a two-day general-level course to provide more information on the nuclear sector to people who are part of the nuclear science and technology community. This paper will discuss how Nuclear 101 aids public outreach discussions and the lessons learned after two years of operation, and will look at future directions for the course. (author)

Nuclear exports and international cooperation

International Nuclear Information System (INIS)

McCardle, J.J.

1981-06-01

Canada's nuclear export policy together with its non-proliferation and safeguards policy embrace both the country's desire to promote international cooperation in the peaceful uses of nuclear energy and its effort to minimize the risk of further proliferation of nuclear weapons. This policy reflects the belief that only if Canadian parliamentary and public opinion can be convinced that Canada's nuclear exports will not contribute to nuclear proliferation will the long-term health of the country's nuclear industry be assured. Canada requires a political commitment to non-proliferation from its nuclear partners, and looks to the IAEA to administer safeguards on nuclear material of Canadian origin to guarantee that commitment. Agreements reached with its nuclear partners are in accordance with provisions of the non-proliferation treaty and include a contingency provision for fall-back safeguards if the other state should withdraw from the NPT. Provision is made for mutual agreement on reprocessing and enrichment of nuclear material. Agreements have been reached with some twenty nuclear partners, and efforts are continuing to come to new international understanding on reprocessing, enrichment, and plutonium storage

Canadian and international approaches to regulatory effectiveness

International Nuclear Information System (INIS)

Lojk, R.

2014-01-01

Regulatory effectiveness is an important attribute of any regulator, particularly nuclear regulators. As the nuclear industry has matured, and as the social landscape has changed, so have views on what constitutes regulatory effectiveness. Canada has evolved its regulatory structure and modernized its legislative framework and technical requirements and guidance over time. In addition, Canada continues to collaborate with international agencies, particularly the NEA and the IAEA, to ensure that there is a common understanding of the indicators and key attributes of regulatory effectiveness. This paper discusses Canadian and international views on the subject, including perspectives from other industries. (author)

Addressing issues raised by stakeholders: evolving practices at the Canadian Nuclear Safety Commission (CNSC)

International Nuclear Information System (INIS)

Flavelle, Peter

2004-01-01

request of community groups, in 1994 the AECB began to publish the Radiation Index to provide information to the public on radiation exposure from Canadian nuclear generating stations. The proliferation of environmental assessment documents has lead the CNSC to develop EA summaries to simplify information for interested stakeholders and to direct them to where more detailed information can be found. The CNSC created Report Cards on Nuclear Power Plants in response to a recommendation of the Auditor General of Canada for a more transparent reporting of the status of nuclear power plants. Extensive stakeholder consultation is an integral part of developing new or amending existing regulations. It took three years of consultations to develop the regulations pursuant to the Nuclear Safety and Control Act. Subsequent amendments to those regulations also receive stakeholder scrutiny, and in some instances the implementation of regulations is modified in response to stakeholder consultation. Furthermore, the drafting of every Regulatory Policy, Standard and Guide includes stakeholder review and formal dispositioning of stakeholder comments as part of the Regulatory Documents Development Process. In summary, operations and practices at the Canadian Nuclear Safety Commission have been evolving in response to changing societal expectations and in response to issues and concerns expressed by stakeholders about the nuclear industry and nuclear regulation in Canada

Building on our past... building for the future. 33rd Annual Canadian Nuclear Society conference and 36th CNS/CNA student conference

International Nuclear Information System (INIS)

2012-01-01

The 33rd Annual Canadian Nuclear Society Conference and 36th CNS/CNA Student Conference was held in Saskatoon, Saskatchewan, Canada on June 10-13, 2012. With the theme of the conference, 'Building on our Past... Building for the Future', the conference specifically noted the 50th anniversary of the first-nuclear-produced electricity in Canada by the small Nuclear Power Demonstration (NPD) plant on June 4, 1962 and the 60th anniversary of the creation of Atomic Energy of Canada Limited in April 1952. The conference brought together over 360 delegates for the technical sessions with very broad subject matter of: physics, environment and waste management, safety and licensing, life extension, fusion technology, fuel and advanced reactors, reactor materials, uranium mining, I and C process, and, thermalhydraulics. Two plenary sessions focussed on: Small Modular Reactors; and, radioisotopes primarily for medical applications. The student conference was well attended with plenary sessions focussing on: Nuclear Industry Power Developments: The Renaissance; and a panel discussion on the overview of the proposed refurbishment of the Darlington four-unit station.

Canadian experience with wet and dry fuel storage concepts

International Nuclear Information System (INIS)

Mayman, S.A.

1978-07-01

Canada has been storing fuel in water-filled pools for 30 years. There have been no significant problems, but until recently little effort has been invested in quantitative assessment of fuel performance under storage conditions. Work is now in progress to provide such information. Storage pools at nuclear generating stations have operated satisfactorily. The Canadian nuclear industry has nevertheless been studying methods for reducing storage costs and/or increasing reliability. Various concepts, using both water and air cooling, have been suggested. One such concept - the air-cooled concrete canister - is presently under test at the Whiteshell Nuclear Research Establishment. (author)

US refining capacity for Canadian heavy oil : current overview and future potential

International Nuclear Information System (INIS)

Paget, S.

2006-01-01

This presentation provided an overview of the Canadian oil sands industry and investigated the potential heavy oil refining capacity of the United States. An outline of the first commercial developments of steam assisted gravity drainage (SAGD) in Alberta's oil sands was provided. Canada's reserves were compared with oil shale and heavy oil reserves in the United States and Venezuela. Influences of Canadian developments from western Canadian conventional crude oil were reviewed, and an oil sands production forecast was provided. Recent refining developments in the United States include delayed coking; catalytic cracking; fluid coking; flexicoking; and LC-fining. However, many oil sand producers are now choosing to upgrade oil, and producers are currently saturating United States markets with heavy crude oil. Canadian crude prices reached $90 per barrel in 2006. Heavy oil pipelines are now being constructed and existing heavy oil pipelines are being expanded. ConocoPhillips is planning to invest $1 billion for a new heavy oil coker, while BP is investing $3 billion for a heavy oil refinery in Indiana which plans to refine Canadian crude oil supplies. However, bitumens from Alberta are volatile in price, and excess Canadian production must be exported. Less than 10 per cent of western Canadian crude has tidewater access, and capital providers are concerned about cost over-runs. In order for the Canadian oil sands industry to succeed, refining capacity in the United States must be expanded, and open access must be provided to the Gulf coast as well as to the Pacific Ocean. tabs., figs

The "Canadian" in Canadian Children's Literature.

Science.gov (United States)

Bainbridge, Joyce; Wolodko, Brenda

2001-01-01

Notes that a rich body of Canadian children's literature exists that reflects the country's literary and socio-cultural values, beliefs, themes and images, including those of geography, history, language and identity. Discusses how Canadians tend to identify themselves first by region or province and then by nation. (SG)

Radiation by the numbers: developing an on-line Canadian radiation dose calculator as a public engagement and education tool

Energy Technology Data Exchange (ETDEWEB)

Dalzell, M.T.J. [Sylvia Fedoruk Canadian Centre for Nuclear Innovation, Saskatoon, Saskatchewan (Canada)

2016-06-15

Concerns arising from misunderstandings about radiation are often cited as a main reason for public antipathy towards nuclear development and impede decision-making by governments and individuals. A lack of information about everyday sources of radiation exposure that is accessible, relatable and factual contributes to the problem. As part of its efforts to be a fact-based source of information on nuclear issues, the Sylvia Fedoruk Canadian Centre for Nuclear Innovation has developed an on-line Canadian Radiation Dose Calculator as a tool to provide context about common sources of radiation. This paper discusses the development of the calculator and describes how the Fedoruk Centre is using it and other tools to support public engagement on nuclear topics. (author)

Aging management guideline for commercial nuclear power plants - heat exchangers

International Nuclear Information System (INIS)

Booker, S.; Lehnert, D.; Daavettila, N.; Palop, E.

1994-06-01

This Aging Management Guideline (AMG) describes recommended methods for effective detection and mitigation of age-related degradation mechanisms in commercial nuclear power plant heat exchangers important to license renewal. The intent of this AMG is to assist plant maintenance and operations personnel in maximizing the safe, useful life of these components. It also supports the documentation of effective aging management programs required under the License Renewal Rule 10 CFR 54. This AMG is presented in a manner that allows personnel responsible for performance analysis and maintenance to compare their plant-specific aging mechanisms (expected or already experienced) and aging management program activities to the more generic results and recommendations presented herein

Aging management guideline for commercial nuclear power plants - heat exchangers

Energy Technology Data Exchange (ETDEWEB)

Booker, S.; Lehnert, D.; Daavettila, N.; Palop, E.

1994-06-01

This Aging Management Guideline (AMG) describes recommended methods for effective detection and mitigation of age-related degradation mechanisms in commercial nuclear power plant heat exchangers important to license renewal. The intent of this AMG is to assist plant maintenance and operations personnel in maximizing the safe, useful life of these components. It also supports the documentation of effective aging management programs required under the License Renewal Rule 10 CFR 54. This AMG is presented in a manner that allows personnel responsible for performance analysis and maintenance to compare their plant-specific aging mechanisms (expected or already experienced) and aging management program activities to the more generic results and recommendations presented herein.

Assessment of terrorist threats to the Canadian energy sector

Energy Technology Data Exchange (ETDEWEB)

Shull, A. [Carleton Univ., Ottawa, ON (Canada). Norman Paterson School of International Affairs]|[Ottawa Univ., ON (Canada). Faculty of Law

2006-03-15

A critical terrorist threat assessment of Canadian energy systems was presented, as well as an analysis of integrated continental systems. Recent responses to heightened threat levels on the part of the Canadian government have ranged from information sharing to emergency preparedness and disaster mitigation strategies. This paper examined threats that the energy sector has traditionally encountered and argued that response capabilities do not match current threats posed by terrorism. The potential of a terrorist attack on the Canadian energy infrastructure is significant and has been referred to as a possible target by terrorist organizations. Actions taken by the Canadian government in response to heightened threat levels were examined. A review of energy industry security measures included outlines of: the natural gas industry, the electric sector, and nuclear reactors and waste. It was noted that not all elements of the critical energy infrastructure share the same level of risk. Recommendations included increased information sharing between government agencies and the private sector; resiliency standards in densely populated areas; and insulating the energy grid against a cascading blackout through the use of DC rather than AC lines. 59 refs.

Assessment of terrorist threats to the Canadian energy sector

International Nuclear Information System (INIS)

Shull, A.

2006-01-01

A critical terrorist threat assessment of Canadian energy systems was presented, as well as an analysis of integrated continental systems. Recent responses to heightened threat levels on the part of the Canadian government have ranged from information sharing to emergency preparedness and disaster mitigation strategies. This paper examined threats that the energy sector has traditionally encountered and argued that response capabilities do not match current threats posed by terrorism. The potential of a terrorist attack on the Canadian energy infrastructure is significant and has been referred to as a possible target by terrorist organizations. Actions taken by the Canadian government in response to heightened threat levels were examined. A review of energy industry security measures included outlines of: the natural gas industry, the electric sector, and nuclear reactors and waste. It was noted that not all elements of the critical energy infrastructure share the same level of risk. Recommendations included increased information sharing between government agencies and the private sector; resiliency standards in densely populated areas; and insulating the energy grid against a cascading blackout through the use of DC rather than AC lines. 59 refs

The roles played by the Canadian General Electric Company's Atomic Power Department in Canada's nuclear power program: work, organization and success in APD, 1955-1995

International Nuclear Information System (INIS)

Cantello, G.W.

2003-01-01

This thesis explores the roles played by the Canadian General Electric Company's Atomic Power Department (APD) in Canada's distinctive nuclear power program. From the establishment of APD in 1955 until the completion of the KANUPP project in Pakistan in 1972, the company's strategy encompassed the design, manufacture, and commissioning of entire nuclear power projects in Canada and abroad. APD then developed a specialized role in the design and supply of complete nuclear fuel handling systems, nuclear fuel bundles, and service work, that sustained a thriving workplace. Five key factors are identified as the reasons behind the long and successful history of the department: (1) Strong, capable and efficient management from the start, (2) Flexible organizational structure, (3) Extremely competent design group, (4) Excellent manufacturing, test, commissioning and service capabilities, (5) Correctly identifying, at the right time, the best fields in which to specialize. (author)

Start up and commercial operation of Laguna Verde nuclear power plant. Unit 1

International Nuclear Information System (INIS)

Torres Ramirez, J.F.

1991-01-01

Prior to start up of Laguna Verde nuclear power plant preoperational tests and start tests were performed and they are described in its more eminent aspects. In relation to commercial operation of nuclear station a series of indicator were set to which allow the measurement of performance in unit 1, in areas of plant efficiency and personal safety. Antecedents. Laguna Verde station is located in Alto Lucero municipality in Veracruz state, 70 kilometers north-northeast from port of Veracruz and a 290 kilometers east-northeast from Mexico city. The station consist of two units manufactured by General Electric, with a nuclear system of vapor supply also called boiling water (BWR/5), and with a system turbine-generator manufactured by Mitsubishi. Each unit has a nominal power of 1931 MWt and a level design power of 675 Mwe and a net power of 654 Electric Megawatts

Nuclear power in Pakistan

International Nuclear Information System (INIS)

Siddiqui, Z.H.; Qureshi, I.H.

2005-01-01

Pakistan started its nuclear power program by installing a 137 M We Canadian Deuterium Reactor (Candu) at Karachi in 1971 which became operational in 1972. The post-contract technical support for the Karachi Nuclear Power Plant (KANUPP) was withdrawn by Canada in 196 as a consequence of Indian nuclear device test in 1974. In spite of various difficulties PAEC resolved to continue to operate KANUPP and started a process for the indigenous fabrication of spare parts and nuclear fuel. The first fuel bundle fabricated in Pakistan was loaded in the core in 1980. Since then KANUPP has been operating on the indigenously fabricated fuel. The plant computer systems and the most critical instrumentation and Control system were also replaced with up-to date technology. In 2002 KANUPP completed its original design life of 30 year. A program for the life extension of the plant had already been started. The second nuclear power plant of 300 M We pressurized water reactor purchased from China was installed in Chashma in 1997, which started commercial operations in 2001. Another unit of 300 M We will be installed at Chashma in near future. These nuclear power plants have been operating under IAEA safeguards agreements. PAEC through the long-term performance of the two power plants has demonstrated its competence to safely and successfully operate and maintain nuclear power plants. Pakistan foresees an increasingly important and significant share of nuclear power in the energy sector. The Government has recently allocated a share of 8000 MWe for nuclear energy in the total energy scenario of Pakistan by the year 2025. (author)

The Canadian Dollar and the Dutch and Canadian Diseases

Directory of Open Access Journals (Sweden)

Serge Coulombe

2013-10-01

Full Text Available With the spectacular rise of the dollar, along with rising natural-resource prices during the first decade of the 21st century, Canadians heard a great deal about Dutch disease. Many politicians and pundits blamed the phenomenon — in which a country’s currency, inflated by rising commodity prices, renders manufacturing exports increasingly uncompetitive — for rising unemployment in the Canadian manufacturing industry. But a close look at what happened during that period reveals that the Dutch disease mechanism was only part of the story. The other part, and quantitatively the most important, is an affliction of an altogether different providence: Canadian disease. Canadian disease is the economic trouble that can be caused by Canada’s extraordinarily heavy reliance on the United States as a trading partner. As a consequence, a sudden depreciation of the U.S, dollar will deteriorate the competitiveness of Canadian manufacturing exporters. Such a phenomenon was at work during the “Great Appreciation” of the Canadian dollar between 2002 and 2008 — the largest such appreciation on record in this country. The depreciation of the U.S. dollar is a phenomenon that is independent of the resource boom and the resulting consequences on the Canadian economy cannot be endorsed to a Dutch disease. Almost 2/3 of the employment losses that are exchange rate related in the trade-exposed manufacturers in Canada during the 2002–2008 period could be attributed to the Canadian disease. The Canadian dollar is partly driven by commodity prices, and the appreciation of the Canadian dollar exerts a negative impact on manufacturing industries that are exposed to international competition. This phenomenon can be coined as a Dutch Affair. The Dutch Affair becomes a disease in the long run when the non-renewable resource is depleted and the manufacturing base is gone. New manufacturing activities might not reappear due to a variety of obstacles. In Canada

Prevalence of antimicrobial resistance in fecal Escherichia coli and Salmonella enterica in Canadian commercial meat, companion, laboratory, and shelter rabbits (Oryctolagus cuniculus) and its association with routine antimicrobial use in commercial meat rabbits.

Science.gov (United States)

Kylie, Jennifer; McEwen, Scott A; Boerlin, Patrick; Reid-Smith, Richard J; Weese, J Scott; Turner, Patricia V

2017-11-01

presence of antimicrobial resistant E. coli or S. enterica on farms; trends towards resistance were present when resistance to specific antimicrobial classes was examined. E. coli was widely prevalent in many Canadian domestic rabbit populations, while S. enterica was rare. The prevalence of AMR in isolated bacteria was variable and most common in isolates from commercial meat rabbits (96% of the AMR isolates were from commercial meat rabbit fecal samples). Our results highlight that domestic rabbits, and particularly meat rabbits, may be carriers of phenotypically antimicrobial-resistant bacteria and AMR genes, possibly contributing to transmission of these bacteria and their genes to bacteria in humans through food or direct contact, as well as to other co-housed animal species. Copyright © 2017 Elsevier B.V. All rights reserved.

Education and the CNA: A Canadian approach to a global agenda

International Nuclear Information System (INIS)

Summers, R.; Hynes, S.

1994-01-01

The Canadian Nuclear Association (CNA) has launched an initiative which objective is not only to offer the target audience a better understanding of the nuclear industry, but also to offer the nuclear industry a better understanding of the target audience (educators, students and parents). By expanding the CNA conventional mandate (science) to include input from social studies teachers and guidance counselors, and by recognizing the interconnection of science, technology, energy, environment and society, it is aimed at maintaining a proactive position in the global environment

Canada's nuclear non-proliferation policy

International Nuclear Information System (INIS)

1982-05-01

Canada's non-proliferation safeguards policy has two objectives: 1) to promote a more effective and comprehensive international non-proliferation regime; and 2) to ensure that Canadian nuclear exports will not be used for any nuclear explosive purpose. By emphasizing the key role of the Non-Proliferation Treaty, promoting reliance upon and improvements in the IAEA safeguards system, treating nuclear weapon and non-weapon states alike, and working for new approaches covering reprocessing, Canada promotes attainment of the first objective. The second is served through the network of bilateral nuclear agreements that Canada has put into place with its partners. The Canadian objective in post-INFCE forums is to persuade the international community to devise a more effective and comprehensive non-proliferation regime into which Canada and other suppliers may subsume their national requirements

Preparing for the future: the implications of the information revolution for the Canadian nuclear industry

Energy Technology Data Exchange (ETDEWEB)

Luke, M O [Atomic Energy of Canada Limited, Pinawa, MB (Canada)

1997-12-31

The information revolution provides an opportunity for the Canadian nuclear industry to reinvigorate the information environment that supports companies and employees in achieving business and personal goals. Five necessary steps are to intensify the information environment; develop a new human resources model that stresses access to, and sharing of, information, and which comes to grips with the need for better programs to retrain and retain employees and to accommodate the `mercenary` workforce; promote awareness of the information revolution; nurture individual initiatives; and develop an integrated approach called information engineering, which involves collaborative work between information technology, information management, and human resources. At the heart of all of these steps is the need for a new way of thinking about information and a determination to share information widely within our organisations and industry. Applying the recommended approaches within our industry will enable us to compete successfully in a global marketplace in which we are outnumbered and out gunned. (author) 28 refs., 2 figs.

Preparing for the future: the implications of the information revolution for the Canadian nuclear industry

International Nuclear Information System (INIS)

Luke, M.O.

1996-01-01

The information revolution provides an opportunity for the Canadian nuclear industry to reinvigorate the information environment that supports companies and employees in achieving business and personal goals. Five necessary steps are to intensify the information environment; develop a new human resources model that stresses access to, and sharing of, information, and which comes to grips with the need for better programs to retrain and retain employees and to accommodate the 'mercenary' workforce; promote awareness of the information revolution; nurture individual initiatives; and develop an integrated approach called information engineering, which involves collaborative work between information technology, information management, and human resources. At the heart of all of these steps is the need for a new way of thinking about information and a determination to share information widely within our organisations and industry. Applying the recommended approaches within our industry will enable us to compete successfully in a global marketplace in which we are outnumbered and out gunned. (author)

Canada's nuclear industry, greenhouse gas emissions, and the Kyoto Protocol

International Nuclear Information System (INIS)

Pendergast, D.R.; Duffey, R.B.; Tregunno, D.

1998-01-01

The Kyoto Protocol of the United Nations Framework Convention on Climate change, dated December 10, 1997 committed Canada to reduce greenhouse gases to 6% below 1990 levels by 2008-2012. Other nations also committed to varying degrees of reduction. The Protocol includes provisions for credit to the 'developed' counties for initiatives which lead to greenhouse gas reduction in the 'developing' countries and for the sharing of credit between 'developed' countries for projects undertaken jointly. The rules and details for implementation of these guidelines remain to be negotiated. We begin our study by establishing the magnitude of greenhouse gas emissions already avoided by the nuclear industry in Canada since the inception of commercial power plants in 1971. We then review projections of energy use in Canada and anticipated increase in electricity use up to the year 2020. These studies have anticipated no (or have 'not permitted') further development of nuclear electricity production in spite of the clear benefit with respect to greenhouse gas emission. The studies also predict a relatively small growth of electricity use. In fact the projections indicate a reversal of a trend toward increased per capita electricity use which is contrary to observations of electricity usage in national economies as they develop. We then provide estimates of the magnitude of greenhouse gas reduction which would result from replacing the projected increase in fossil fuel electricity by nuclear generation through the building of more plants and/or making better use of existing installations. This is followed by an estimate of additional nuclear capacity needed to avoid CO 2 emissions while providing the electricity needed should per capita usage remain constant. Canada's greenhouse gas reduction goal is a small fraction of international commitments. The Kyoto agreement's 'flexibility mechanism' provisions provide some expectation that Canada could obtain some credit for greenhouse gas

The nuclear industry in Canada

International Nuclear Information System (INIS)

Anderson, D.; Broughton, W.

1992-01-01

The nuclear industry in Canada comprises three identifiable groups: (1) Atomic Energy of Canada Limited (AECL), (2) electrical utilities that use nuclear power plants, (3) private engineering and manufacturing companies. At the end of World War II, AECL was charged with investigating and developing peaceful uses of atomic power. Included in the results is the Canada deuterium uranium (CANDU) reactor, a peculiarly Canadian design. The AECL maintains research capability and operates as the prime nuclear steam supply system supplier. Utilities in three Canadian provinces operate nuclear power plants, New Brunswick, Quebec, and Ontario, with the majority in Ontario. From the beginning of the nuclear program in Canada, private industry has been an important partner to AECL and the utilities, filling roles as manufacturing subcontractors and as component designers. The prime objective of this paper is to illuminate the role of private industry in developing and maintaining a competitive world-class nuclear industry

Addressing issues raised by stakeholders: impacts on process, content and behaviour in the case of the Canadian nuclear waste management organization

International Nuclear Information System (INIS)

Shaver, Kathryn

2004-01-01

The purpose of this paper is to highlight how stakeholder input has shaped the work of the Canadian Nuclear Waste Management Organization (NWMO) in both process and content. In 2002, NWMO was mandated by the Government of Canada to undertake a study of different approaches for the long-term management of used nuclear fuel, and to recommend an approach to the Government by November 15, 2005. Public consultations are an important part of this legislated mandate. In inviting broad dialogue and feedback from the public at large, experts, and other communities of interest, NWMO intends that its processes, the study and its recommendations will reflect the values and perspectives of Canadian society. The organization has adopted a reflective study approach, through which it deliberately seeks public input at each stage of study. A continuum of engagement activities provides for dynamic interaction between the engagement processes and the research and analysis. The insights gained from engagement are integrated into the NWMO's study, to continuously enrich the iterative learning process. NWMO has received a wide range of comments, insights and questions from face-to-face discussions, workshops, round-tables, written submissions and public opinion research. The sections that follow illustrate how this stakeholder input has helped to shape the organisation's public engagement plans, work-plan and the focus of the assessment that is now in progress. Going forward, issues and comments provided by different communities of interest will assist the assessment of the management approaches and help design NWMO's recommendation to the Government of Canada. (author)

Enhanced security in the nuclear industry

International Nuclear Information System (INIS)

Frappier, G.

2007-01-01

This article describes the security in the nuclear industry. After 9/11, Canada's nuclear regulator - the Canadian Nuclear Safety Commission (CNSC) - determined that the entire industry (including its own organization) faced a need for significant enhancements in their approach to security.

International arrangements for nuclear-fuel-cycle facilities: the politics of the problem

International Nuclear Information System (INIS)

Epstein, W.

1977-01-01

Thirty years after the Three-Power Declaration on November 5, 1945, promising effective safeguards on the information exchange on atomic energy, many nations are selling and transferring nuclear materials, equipment, and technology without these ''effective enforceable safeguards.'' Even though there is no actual commercial need to reprocess spent fuel into Pu, France and West Germany are planning to sell reprocessing plants to non-NPT countries. The erosion of faith in and the weakening of the NPT are pointed out. The Canadian decision not to resume nuclear aid to India is commended. The question of how effective and enforceable the international (IAEA/NPT) safeguards are, is addressed. The weaknesses of the London Suppliers' Club position on safeguards are pointed out. Multinational fuel cycle centers would not much help to contain the risks of nuclear proliferation. Additional measures needed for really effective safeguards are listed. The unilateral embargo of nuclear exports by U.S. is proposed. Political measures to discourage nations from acquiring nuclear weapons are also listed. Only a combination of political, psychological, and technical measures can produce an effective nonproliferation regime

PBNC 2014 : 19th Pacific Basin Nuclear Conference; 38th Annual Student Conference of the Canadian Nuclear Society and Canadian Nuclear Association

Energy Technology Data Exchange (ETDEWEB)

NONE

2014-07-01

The 19th Pacific Basin Nuclear Conference (PBNC), held in Vancouver, August 24 - 28, 2014, was an outstanding success in all aspects. With the theme 'Fulfilling the Promise of Nuclear Technology Around the Pacific Basin in the 21st Century', it included 46 senior-level presentations, 300 technical papers from countries around the Pacific rim and others, 53 student posters and a number of exhibits from several countries. The venue of Vancouver proved attractive to the large contingent of attendees from the Asian side of the Pacific Ocean, who constituted over a third of the 600 delegates. This years conference: showcased the advancement of nuclear technology in power generation, health science, and environmental stewardship; discussed challenges facing nuclear technology; and highlighted future developments.

Range of Applicability and Bias Determination for Postclosure Criticality of Commercial Spent Nuclear Fuel

International Nuclear Information System (INIS)

Radulescu, Georgeta; Mueller, Don; Goluoglu, Sedat; Hollenbach, Daniel F; Fox, Patricia B

2007-01-01

The purpose of this calculation report, Range of Applicability and Bias Determination for Postclosure Criticality of Commercial Spent Nuclear Fuel, is to validate the computational method used to perform postclosure criticality calculations. The validation process applies the criticality analysis methodology approach documented in Section 3.5 of the Disposal Criticality Analysis Methodology Topical Report. The application systems for this validation consist of waste packages containing transport, aging, and disposal canisters (TAD) loaded with commercial spent nuclear fuel (CSNF) of varying assembly types, initial enrichments, and burnup values that are expected from the waste stream and of varying degree of internal component degradation that may occur over the 10,000-year regulatory time period. The criticality computational tool being evaluated is the general-purpose Monte Carlo N-Particle (MCNP) transport code. The nuclear cross-section data distributed with MCNP 5.1.40 and used to model the various physical processes are based primarily on the Evaluated Nuclear Data File/B Version VI (ENDF/B-VI) library. Criticality calculation bias and bias uncertainty and lower bound tolerance limit (LBTL) functions for CSNF waste packages are determined based on the guidance in ANSI/ANS 8.1-1998 (Ref. 4) and ANSI/ANS 8.17-2004 (Ref. 5), as described in Section 3.5.3 of Ref. 1. The development of this report is consistent with Test Plan for: Range of Applicability and Bias Determination for Postclosure Criticality. This calculation report has been developed in support of licensing activities for the proposed repository at Yucca Mountain, Nevada, and the results of the calculation may be used in the criticality evaluation for CSNF waste packages based on a conceptual TAD canister.

SOURCE OF BURNUP VALUES FOR COMMERCIAL SPENT NUCLEAR FUEL ASSEMBLIES

International Nuclear Information System (INIS)

BSC

2004-01-01

Waste packages are loaded with commercial spent nuclear fuel (SNF) that satisfies the minimum burnup requirements of a criticality loading curve. The burnup value assigned by the originating nuclear utility to each SNF assembly (assigned burnup) is used to load waste packages in compliance with a criticality loading curve. The burnup provided by a nuclear utility has uncertainties, so conservative calculation methods are used to characterize those uncertainties for incorporation into the criticality loading curves. Procedural safety controls ensure that the correct assembly is loaded into each waste package to prevent a misload that could create a condition affecting the safety margins. Probabilistic analyses show that procedural safety controls can minimize the chance of a misload but can not completely eliminate the possibility. Physical measurements of burnup with instrumentation in the surface facility are not necessary due to the conservative calculation methods used to produce the criticality loading curves. The reactor records assigned burnup of a commercial SNF assembly contains about two percent uncertainty, which is increased to five-percent to ensure conservatism. This five-percent uncertainty is accommodated by adjusting the criticality loading curve. Also, the record keeping methods of nuclear utilities are not uniform and the level of detail required by the NRC has varied over the last several decades. Thus, some SNF assemblies may have assigned burnups that are averages for a batch of assemblies with similar characteristics. Utilities typically have access to more detailed core-follow records that allow the batch average burnup to be changed to an assembly specific burnup. Alternatively, an additional safety margin is incorporated into the criticality loading curve to accommodate SNF assemblies with batch average burnups or greater uncertainties due to the methodology used by the nuclear utility. The utility records provide the assembly identifier

Nuclear proliferation and civilian nuclear power: report of the Nonproliferation Alternative Systems Assessment Program. Volume IV. Commercial potential

International Nuclear Information System (INIS)

1979-12-01

Volume IV provides time and cost estimates for positioning new nuclear power systems for commercial deployment. The assessment also estimates the rates at which the new systems might penetrate the domestic market, assuming the continuing viability of the massive light-water reactor network that now exists worldwide. This assessment does not recommend specific, detailed program plans and budgets for individual systems; however, it is clear from this analysis that any of the systems investigated could be deployed if dictated by national interest

U.S. Commercial Spent Nuclear Fuel Assembly Characteristics - 1968-2013

Energy Technology Data Exchange (ETDEWEB)

Hu, Jianwei [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Peterson, Joshua L. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Gauld, Ian C. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Bowman, Stephen M. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

2016-09-01

Activities related to management of spent nuclear fuel (SNF) are increasing in the US and many other countries. Over 240,000 SNF assemblies have been discharged from US commercial reactors since the late 1960s. The enrichment and burnup of SNF have changed significantly over the past 40 years, and fuel assembly designs have also evolved. Understanding the general characteristics of SNF helps regulators and other stakeholders form overall strategies towards the final disposal of US SNF. This report documents a survey of all US commercial SNF assemblies in the GC-859 database and provides reference SNF source terms (e.g., nuclide inventories, decay heat, and neutron/photon emission) at various cooling times up to 200 years after fuel discharge. This study reviews the distribution and evolution of fuel parameters of all SNF assemblies discharged over the past 40 years. Assemblies were categorized into three groups based on discharge year, and the median burnups and enrichments of each group were used to establish representative cases. An extended burnup case was created for boiling water reactor (BWR) fuels, and another was created for the pressurized water reactor (PWR) fuels. Two additional cases were developed to represent the eight mixed oxide (MOX) fuel assemblies in the database. Burnup calculations were performed for each representative case. Realistic parameters for fuel design and operations were used to model the SNF and to provide reference fuel characteristics representative of the current inventory. Burnup calculations were performed using the ORIGEN code, which is part of the SCALE nuclear modeling and simulation code system. Results include total activity, decay heat, photon emission, neutron flux, gamma heat, and plutonium content, as well as concentrations for 115 significant nuclides. These quantities are important in the design, regulation, and operations of SNF storage, transportation, and disposal systems.

'When you use the term 'long term', how long is that term'. Risk, Exclusion, and the Politics of Knowledge Production in Canadian Nuclear Fuel Waste Management Policy Making

International Nuclear Information System (INIS)

Stanley, Anna

2006-01-01

Risk operates within Canadian Nuclear Fuel Waste (NFW) management policy making as a heuristic for knowledge production about its effects which reconciles the knowledge of the nuclear industry with the outcomes of the NFW management process. In so doing it marginalizes the present and historical experiences of Aboriginal peoples with the nuclear industry, and removes from view the ways in which they have been implicated in the geography and political economy of the nuclear industry. Risk is a discursive form that protects a particular group's claims about the effects of NFW by providing it a universalizing epistemological structure with which to obscure its connection to context. Further risk discourse provides the nuclear industry with a conceptual vocabulary that deliberately casts all competing knowledge as perceptions, values, or as an object of inquiry. The arguments of Aboriginal peoples about the residual effects of radiation in their lands which hosted nuclear activities, such as uranium mining and disposal, have no representation in how the discourse of risk defines and represents knowledge, and thus no purchase in the policy debate. As a result the challenge they present to the nuclear industry's claims are contained. The arrangements which permit the unloading of the negative effects of nuclear power generation onto Aboriginal peoples are thus reproduced (both materially and conceptually), but not shown, by the policy making process and likely, its outcome. In order to raise critical questions about the democratic abilities of risk, this paper has examined the role of 'risk' in Canadian NFW policy making. I have shown how when the politics of knowledge production within the philosophy of risk is analyzed, and the use and role of the notion of risk are interrogated, difficult questions are posed for the democratic potential of risk. I have suggested, through an analysis of the NWMO's representations of Aboriginal content in their process, that in this

Argentine nuclear program

International Nuclear Information System (INIS)

Leibovich, H.; Takacs, E.A.

1983-01-01

The paper describes Argentina's nuclear program, detailing its objectives, the schedule of construction of nuclear plants and local production of required equipment. The technologies adopted so far, the local industrial and engineering participation, the preliminary study for the construction of the next power station and Argentina's nonproliferation nuclear policy are analyzed. Argentina's point of view on Canadian nonproliferation policy and CANDU reactor export is discussed

Analysis of gross error rates in operation of commercial nuclear power stations

International Nuclear Information System (INIS)

Joos, D.W.; Sabri, Z.A.; Husseiny, A.A.

1979-01-01

Experience in operation of US commercial nuclear power plants is reviewed over a 25-month period. The reports accumulated in that period on events of human error and component failure are examined to evaluate gross operator error rates. The impact of such errors on plant operation and safety is examined through the use of proper taxonomies of error, tasks and failures. Four categories of human errors are considered; namely, operator, maintenance, installation and administrative. The computed error rates are used to examine appropriate operator models for evaluation of operator reliability. Human error rates are found to be significant to a varying degree in both BWR and PWR. This emphasizes the import of considering human factors in safety and reliability analysis of nuclear systems. The results also indicate that human errors, and especially operator errors, do indeed follow the exponential reliability model. (Auth.)

The regional control of the canadian energy production

International Nuclear Information System (INIS)

Petitlaurent, S.; Sarrazin, J.

2004-12-01

This document provides information and presents data on the energy situation in many regions of Canada. The first part deals with the petroleum and the bitumen shales of Alberta (reserves, exploitation and production, environmental impacts), the second part discusses with the hydroelectricity choice of Quebec and the 2004 crisis. The nuclear situation of Ontario is presented in the third part (nuclear park, programs, uranium reserves, research and development on Candu reactors), while the fourth part deals with the renewable energies (wind power and biomass). The canadian situation facing the Kyoto protocol is discussed in the last part. (A.L.B.)

Aging management guideline for commercial nuclear power plants-stationary batteries

International Nuclear Information System (INIS)

Berg, R.; Shao, J.; Krencicki, G.; Giachetti, R.

1994-03-01

The Aging Management Guideline (AMG) describes recommended methods for effective detection and mitigation of age-related degradation mechanisms in BWR and PWR commercial nuclear power plant stationary batteries important to license renewal. The intent of this AMG is to assist plant maintenance and operations personnel in maximizing the safe, useful life of these components. It also supports the documentation of effective aging management programs required under the License Renewal Rule 10 CFR Part 54. This AMG is presented in a manner that allows personnel responsible for performance analysis and maintenance to compare their plant-specific aging mechanisms (expected or already experienced) and aging management program activities to the more generic results and recommendations presented herein

Aging Management Guideline for commercial nuclear power plants: Electrical switchgear

International Nuclear Information System (INIS)

Toman, G.; Gazdzinski, R.; Schuler, K.

1993-07-01

This Aging Management Guideline (AMG) provides recommended methods for effective detection and mitigation of age-related degradation mechanisms in BWR and PWR commercial nuclear power plant electrical switchgear important to license renewal. The latent of this AMG to assist plant maintenance and operations personnel in maximizing the safe, useful life of these components. It also supports the documentation of effective aging management programs required under the License Renewal Rule 10 CFR Part 54. This AMG is presented in a manner which allows personnel responsible for performance analysis and maintenance, to compare their plant-specific aging mechanisms (expected or already experienced) and aging management program activities to the more generic results and recommendations presented herein

Fire protection of safe shutdown capability at commercial nuclear power plants

International Nuclear Information System (INIS)

Sullivan, K.

1993-01-01

The comprehensive industrial safety standards and codes that exist today have evolved from lessons learned through past experience, research results, and improvements in technological capabilities. The current requirements for fire safety features of commercial nuclear power stations operated in the U.S. are a notable example of this practice. Although fire protection has always been an important design requirement, from the aftermath of a serious fire that occurred in 1975 at the Browns Ferry plant, it was learned that the life safety and property protection concerns of the major fire insurance underwriters may not sufficiently encompass nuclear safety issues, particularly with regard to the potential for fire damage to result in the common mode failure of redundant trains of systems, and composites important to the safe shutdown of the reactor. Following its investigations into the Browns Ferry fire, the Nuclear Regulatory Commission (NRC) promulgated guidance documents, which ultimately developed into mandatory regulations, necessary to assure the implementation of a fire protection program that would address nuclear safety concerns. The new criteria that evolved, contain prescriptive design features, as well as personnel and administrative requirements the Commission determined to be necessary to provide a defense-in-depth level of protection against the hazards of fire and its associated effects on safety related equipment. These criteria are primarily contained in Appendix R of Title 10 to the Code of Federal Regulations (10 CFR 50)

NRC/FEMA operational response procedures for response to a commercial nuclear reactor accident

International Nuclear Information System (INIS)

1983-11-01

Procedures have been developed by the US Nuclear Regulatory Commission (NRC) and the Federal Emergency Management Agency (FEMA) which provide the response teams of both agencies with the steps to be taken in responding to an emergency at a commercial nuclear power plant. The emphasis of these procedures is mainly on the interface between NRC and FEMA at their respective Headquarters and Regional Offices and at the various sites at which such an emergency could occur. Detailed procedures are presented that cover for both agencies, notification schemes and manner of activation, organizations at Headquaters and the site, interface procedures, coordination of onsite and offsite operations, the role of the Senior FEMA Official, and the cooperative efforts of each agency's public information staff

Lessons learned from commercial experience with nuclear plant decontamination to safe storage

International Nuclear Information System (INIS)

Fischer, S.R.; Partain, W.L.; Sype, T.

1995-01-01

The Department of Energy (DOE) has successfully performed decontamination and decommissioning (D ampersand D) on many production reactors it. DOE now has the challenge of performing D ampersand D on a wide variety of other nuclear facilities. Because so many facilities are being closed, it is necessary to place many of them into a safe-storage status before conducting D ampersand D-for perhaps as much as 20 yr. The challenge is to achieve this safe-storage condition in a cost-effective manner while remaining in compliance with applicable regulations. The DOE Office of Environmental Management, Office of Transition and Management, commissioned a lessons learned study of commercial experience with safe storage and transition to D ampersand D. Although the majority of the commercial experience has been with reactors, many of the lessons learned presented in this paper are directly applicable to transitioning the DOE Weapons Complex

Determination of internationally controlled materials according to provisions of the law for the regulations of nuclear source materials, nuclear fuel materials and reactors

International Nuclear Information System (INIS)

1981-01-01

This rule is established under the provisions of the law concerning the regulation of nuclear raw materials, nuclear fuel materials and reactors, and the former notification No. 26, 1961, is hereby abolished. Internationally regulated goods under the law are as follows: nuclear raw materials, nuclear fuel materials and moderator materials transferred by sale or other means from the governments of the U.S., U.K., Canada, Australia and France or the persons under their jurisdictions according to the agreements concluded between the governments of Japan and these countries, respectively, the nuclear fuel materials recovered from these materials or produced by their usage, nuclear reactors, the facilities and heavy water transferred by sale or other means from these governments or the persons under their jurisdictions, the nuclear fuel materials produced by the usage of such reactors, facilities and heavy water, the nuclear fuel materials sold by the International Atomic Energy Agency under the contract between the Japanese government and the IAEA, the nuclear fuel materials recovered from these materials or produced by their usage, the heavy water produced by the facilities themselves transferred from the Canadian government, Canadian governmental enterprises or the persons under the jurisdiction of the Canadian government or produced by the usage of these facilities, etc. (Okada, K.)

Competing Discourses about Youth Sexual Exploitation in Canadian News Media.

Science.gov (United States)

Saewyc, Elizabeth M; Miller, Bonnie B; Rivers, Robert; Matthews, Jennifer; Hilario, Carla; Hirakata, Pam

2013-10-01

Media holds the power to create, maintain, or break down stigmatizing attitudes, which affect policies, funding, and services. To understand how Canadian news media depicts the commercial sexual exploitation of children and youth, we examined 835 Canadian newspaper articles from 1989-2008 using a mixed methods critical discourse analysis approach, comparing representations to existing research about sexually exploited youth. Despite research evidence that equal rates of boys and girls experience exploitation, Canadian news media depicted exploited youth predominantly as heterosexual girls, and described them alternately as victims or workers in a trade, often both in the same story. News media mentioned exploiters far less often than victims, and portrayed them almost exclusively as male, most often called 'customers' or 'consumers,' and occasionally 'predators'; in contrast, research has documented the majority of sexually exploited boys report female exploiters. Few news stories over the past two decades portrayed the diversity of victims, perpetrators, and venues of exploitation reported in research. The focus on victims but not exploiters helps perpetuate stereotypes of sexual exploitation as business or a 'victimless crime,' maintains the status quo, and blurs responsibility for protecting youth under the UN Convention on the Rights of the Child. Health care providers and researchers can be advocates for accuracy in media coverage about sexual exploitation; news reporters and editors should focus on exploiters more than victims, draw on existing research evidence to avoid perpetuating stereotypes, and use accurate terms, such as commercial sexual exploitation, rather than terms related to business or trade.

Pyrolytic carbon coatings for nuclear fuels from commercial butane

International Nuclear Information System (INIS)

Abdelrazek, I.D.; Abdelhalim, A.S.

1976-01-01

Uranium dioxide and graphite semi-spherical particles (average diameter = 300 um) were coated with pyrolytic carbon at relatively low temperatures (800 to 1200 0 C). The spouting gas was a mixture of commercial butane and nitrogen. The hydrocarbon served as a source for carbon whereas nitrogenated as a diluent and a support for the bed. The total gas flow rate was 3.5 lit/min and the hydrocarbon content varied from 3 to 10%. Coating efficiencies ranging from 4 to 25 percent were obtained. The densities of the coatings varied from 1.25 g/cm 3 (which corresponds to coatings of laminar microstructures) and 1.82 g/cm 3 (which suggests the formation of isotropic coatings. Metallographic examination (using polarized light) of the pyrolytic carbon formed at the experimental conditions indicated the possibility of using the coatings for nuclear fuel applications

Nuclear information seminar

International Nuclear Information System (INIS)

1982-01-01

The fourth meeting of this type (previous ones were held in 1976, 1977, and 1980) presented papers from ten speakers representing Canadian nuclear power utilities, contractors, and Atomic Energy of Canada Limited. Topics discussed were: the development of nuclear power in Canada and elsewhere, potential use of CANDU reactors for steam generation, waste management, public perceptions, and comparison of nuclear power with coal-fired plants in western Canada

State of the art review of radioactive waste volume reduction techniques for commercial nuclear power plants

International Nuclear Information System (INIS)

1980-04-01

A review is made of the state of the art of volume reduction techniques for low level liquid and solid radioactive wastes produced as a result of: (1) operation of commercial nuclear power plants, (2) storage of spent fuel in away-from-reactor facilities, and (3) decontamination/decommissioning of commercial nuclear power plants. The types of wastes and their chemical, physical, and radiological characteristics are identified. Methods used by industry for processing radioactive wastes are reviewed and compared to the new techniques for processing and reducing the volume of radioactive wastes. A detailed system description and report on operating experiences follow for each of the new volume reduction techniques. In addition, descriptions of volume reduction methods presently under development are provided. The Appendix records data collected during site surveys of vendor facilities and operating power plants. A Bibliography is provided for each of the various volume reduction techniques discussed in the report

How Canada's and India's nuclear roles have been sadly misrepresented

International Nuclear Information System (INIS)

Bindon, G.; Mukerji, S.

1977-01-01

The authors are concerned to remove misunderstandings about the termination of nuclear cooperation between Canada and India following India's explosion of a nuclear device in 1974. The history of the cooperation between the two countries, leading to the construction of the Rajasthan-1 reactor, is recounted. It is suggested that India had long intended to explode a nuclear device, consistent with its refusal to sign the nonproliferation treaty; surprise was therefore unwarranted. The value of the Rajasthan contract to the Canadian nuclear industry is emphasized, on the grounds that it came at a crucial time, just after Douglas Point had reached full power in 1962. The authors seem to believe that Canadian industry will suffer in that it will be more difficult to achieve agreements with developing countries in the future. This is made the occasion for some general criticism of the Canadian nuclear programme, but not of the Indian, which is held to be more diversified, and therefore able to develop supposedly practical and better alternatives to nuclear energy. (N.D.H.)

NuclearFACTS: public engagement about the impacts of nuclear research

Energy Technology Data Exchange (ETDEWEB)

Dalzell, M.T.J.; Alexander, R.N.; Main, M.G., E-mail: matthew.dalzell@fedorukcentre.ca [Sylvia Fedoruk Canadian Centre for Nuclear Innovation, Saskatoon, SK, (Canada)

2015-07-01

The Forum for Accountability and Communities Talking nuclear Science - nuclearFACTS - is a cornerstone of the Sylvia Fedoruk Canadian Centre for Nuclear Innovation's efforts to engage the people of Saskatchewan in evidence-based conversations about the impacts of the nuclear research, development and training activities supported by the Fedoruk Centre. The second annual nuclearFACTS public colloquium was held 20 November 2014, and featured the participation of 16 research projects. This paper discusses the continued development of the nuclearFACTS concept and its role in the Fedoruk Centre's upstream engagement efforts. (author)

The potential for microbial life in a Canadian high-level nuclear fuel waste disposal vault

International Nuclear Information System (INIS)

Stroes-Gascoyne, S.

1989-12-01

Recent studies have concluded that microbial contamination of a nuclear fuel waste disposal vault is inevitable. Factors that will affect the development of substantial population of micro-organisms include: physiological tolerance of microbes; fluid movement in a vault; availability of nutrients; and availability of energy sources. It is difficult to resolve whether microbial growth will either positively or negatively affect the performance of a vault. One of the necessary steps towards ultimately answering this question is to assess the potential for microbial growth in a disposal vault, based on a nutrient and energy budget. This report gives a quantitative (but conservative) inventory of nutrients and potential energy sources present in a Canadian nuclear fuel waste vault, which hypothetically could support the growth of micro-organisms. Maximum population densities are calculated based on these inventories and assuming that all conditions for microbial growth are optimal, although this will certainly not be the case. Laboratory studies under the vault-relevant conditions are being performed to put realistic boundaries on the calculated numbers. Initial results from these studies, combined with data from a natural analogue site indicate that the calculated population densities could be overestimated by four to five orders of magnitude. Limited data show no effect of the presence of microbes on the transport of Tc, I, and Sr in backfill sand columns. Additional work is needed to address transport effects on buffer and backfill clay columns

Use of open source information and commercial satellite imagery for nuclear nonproliferation regime compliance verification by a community of academics

Science.gov (United States)

Solodov, Alexander

The proliferation of nuclear weapons is a great threat to world peace and stability. The question of strengthening the nonproliferation regime has been open for a long period of time. In 1997 the International Atomic Energy Agency (IAEA) Board of Governors (BOG) adopted the Additional Safeguards Protocol. The purpose of the protocol is to enhance the IAEA's ability to detect undeclared production of fissile materials in member states. However, the IAEA does not always have sufficient human and financial resources to accomplish this task. Developed here is a concept for making use of human and technical resources available in academia that could be used to enhance the IAEA's mission. The objective of this research was to study the feasibility of an academic community using commercially or publicly available sources of information and products for the purpose of detecting covert facilities and activities intended for the unlawful acquisition of fissile materials or production of nuclear weapons. In this study, the availability and use of commercial satellite imagery systems, commercial computer codes for satellite imagery analysis, Comprehensive Test Ban Treaty (CTBT) verification International Monitoring System (IMS), publicly available information sources such as watchdog groups and press reports, and Customs Services information were explored. A system for integrating these data sources to form conclusions was also developed. The results proved that publicly and commercially available sources of information and data analysis can be a powerful tool in tracking violations in the international nuclear nonproliferation regime and a framework for implementing these tools in academic community was developed. As a result of this study a formation of an International Nonproliferation Monitoring Academic Community (INMAC) is proposed. This would be an independent organization consisting of academics (faculty, staff and students) from both nuclear weapon states (NWS) and

The evolution of Canadian research reactors, 1942 to 1992

International Nuclear Information System (INIS)

Lidstone, R.F.

1993-01-01

This report reviews the evolution of Canadian research reactor design over the past fifty years. Canadian research reactors have played a central role in the development of CANDU power reactors and the creation of an international business based on the production of medical and industrial radioisotopes. A focus on neutronic efficiency, which stemmed from the incentive for direct use of Canada's abundant uranium resources, has resulted in several generations of multipurpose reactors with a common heritage of neutronic efficiency. Each successive nuclear design has been engineered with the best available resources to extrapolate slightly from the current technology base to meet specific program requirements and to incorporate the flexibility needed to accommodate evolving priorities. (Author) 19 refs., 2 tabs., 2 figs

Nuclear and uranium policies

International Nuclear Information System (INIS)

MacNabb, G.M.; Uranium Canada Ltd., Ottawa, Ontario)

The background of the uranium industry in Canada is described. Government policies with respect to ownership of the uranium mining industry, price stabilization, and especially reservation of sufficient supplies of nuclear fuels for domestic utilities, are explained. Canadian policy re nuclear exports and safeguards is outlined. (E.C.B.)

Nuclear proliferation and civilian nuclear power. Report of the Nonproliferation Alternative Systems Assessment Program. Volume IV. Commercial potential

Energy Technology Data Exchange (ETDEWEB)

1980-06-01

This volume of the Nonproliferation Alternative Systems Assessment Program (NASAP) report provides time and cost estimates for positioning new nuclear power systems for commercial deployment. The assessment also estimates the rates at which the new systems might penetrate the domestic market, assuming the continuing viability of the massive light-water reactor network that now exists worldwide. This assessment does not recommend specific, detailed program plans and budgets for individual systems; however, it is clear from this analysis that any of the systems investigated could be deployed if dictated by national interest.

Nuclear proliferation and civilian nuclear power. Report of the Nonproliferation Alternative Systems Assessment Program. Volume IV. Commercial potential

International Nuclear Information System (INIS)

1980-06-01

This volume of the Nonproliferation Alternative Systems Assessment Program (NASAP) report provides time and cost estimates for positioning new nuclear power systems for commercial deployment. The assessment also estimates the rates at which the new systems might penetrate the domestic market, assuming the continuing viability of the massive light-water reactor network that now exists worldwide. This assessment does not recommend specific, detailed program plans and budgets for individual systems; however, it is clear from this analysis that any of the systems investigated could be deployed if dictated by national interest

R and M practices in commercial aviation

International Nuclear Information System (INIS)

Matteson, T.D.

1985-01-01

During 1982-83, Los Alamos Technical Associates (LATA) and American Management Systems (AMS) conducted an extensive review of design and operations practices in the commercial air transport industry focused on reliability and maintenance for the Electric Power Research Institute (EPRI). The genesis of this review was a discussion of the technical and environmental similarities of the commercial air transport and commercial nuclear power communities and the potential opportunities for experience transfer from air transport to nuclear power. This paper focuses on those similarities believed to be of particular interest to the nuclear power community

Leaching studies of natural and synthetic titanite, a potential host for wastes from the reprocessing of Canadian nuclear fuel

International Nuclear Information System (INIS)

Hayward, P.J.; Doern, F.E.; Cecchetto, E.V.; Mitchell, S.L.

1983-01-01

Glass ceramics (i.e., glasses subjected to controlled crystallization) with synthetic titanite as the major crystalline phase are being considered as potential hosts for the radioactive wastes arising from possible future reprocessing of nuclear fuel in Canada. In order to assess the stability of titanite in the anticipated environment of a disposal vault sited 500-1000 m deep within a granitic pluton in the Canadian Shield, leaching experiments have been performed with natural and synthetic titanite, using a synthetic groundwater whose composition is based on findings from a recent borehole-survey. The results are in qualitative agreement with calculations of solution equilibria for titanite and its main alteration products, and indicate that titanite should be stable and suffer no net leaching under anticipated conditions in the vault

Training of troubleshooting skills in nuclear power plants

International Nuclear Information System (INIS)

Rhodes, W.; Szlapetis, I.J.; Casselman, K.

1995-12-01

This report details the study of training of troubleshooting skills for Canadian nuclear power plant operators and maintainers. The study was conducted in three distinct stages: 1) literature review and production of annotated bibliographies; 2) survey of experts in training for troubleshooting skills in North America; 3) survey of Canadian nuclear power plant training centres. Within this report are 12 annotated bibliographies of significant documents and an extensive bibliographic listing of relevant literature. The review of the literature and the survey of training experts identified the state-of-art in troubleshooting training with respect to training approaches and training tools. Trainers in the military, pharmaceutical, petro-chemical, and nuclear industries were surveyed and/or interviewed to determine the current approaches and technologies used in training for troubleshooting. Training personnel responsible for Canada's major nuclear generating stations (Bruce, Darlington, Pickering, and Point Lepreau) were interviewed and surveyed to determine the status of troubleshooting training in the Canadian nuclear industry. This information has been integrated and presented in this report. Conclusions and recommendations regarding the nature of the troubleshooting tasks performed by operators and maintainers and the related training were submitted. (author). 152 refs., 7 tabs., 1 fig

Training of troubleshooting skills in nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Rhodes, W; Szlapetis, I J; Casselman, K [Rhodes and Associates, Inc., Willowdale, ON (Canada)

1995-12-01

This report details the study of training of troubleshooting skills for Canadian nuclear power plant operators and maintainers. The study was conducted in three distinct stages: (1) literature review and production of annotated bibliographies; (2) survey of experts in training for troubleshooting skills in North America; (3) survey of Canadian nuclear power plant training centres. Within this report are 12 annotated bibliographies of significant documents and an extensive bibliographic listing of relevant literature. The review of the literature and the survey of training experts identified the state-of-art in troubleshooting training with respect to training approaches and training tools. Trainers in the military, pharmaceutical, petro-chemical, and nuclear industries were surveyed and/or interviewed to determine the current approaches and technologies used in training for troubleshooting. Training personnel responsible for Canada`s major nuclear generating stations (Bruce, Darlington, Pickering, and Point Lepreau) were interviewed and surveyed to determine the status of troubleshooting training in the Canadian nuclear industry. This information has been integrated and presented in this report. Conclusions and recommendations regarding the nature of the troubleshooting tasks performed by operators and maintainers and the related training were submitted. (author). 152 refs., 7 tabs., 1 fig.

Technology review of commercial food service equipment - final report

Energy Technology Data Exchange (ETDEWEB)

Rahbar, S; Krsikapa, S [Canadian Gas Research Inst., Don Mills, ON (Canada); Fisher, D; Nickel, J; Ardley, S; Zabrowski, D [Fisher Consultants (Canada); Barker, R F [ed.

1996-05-15

Technical information on commercial gas cooking appliances was presented. This second volume provided an appliance-by-appliance comprehensive assessment of the energy performance of commercial food service equipment. Energy assessments were made for the following categories of cooking equipment: fryers, griddles, broilers, ranges, Chinese ranges, ovens, steamers, steam kettles, and braising pans. Recommendations were made for improving the energy efficiency and overall performance of gas appliances to support of the Canadian gas utilities marketing and energy conservation initiatives. 71 refs., 37 tabs., 58 figs.

Commercial incineration demonstration

International Nuclear Information System (INIS)

Vavruska, J.S.; Borduin, L.C.

1982-01-01

Low-level radioactive wastes (LLW) generated by nuclear utilities presently are shipped to commercial burial grounds for disposal. Increasing transportation and disposal costs have caused industry to consider incineration as a cost-effective means of volume reduction of combustible LLW. Repeated inquiries from the nuclear industry regarding the applicability of the Los Alamos controlled air incineration (CAI) design led the DOE to initiate a commercial demonstration program in FY-1980. Development studies and results in support of this program involving ion exchange resin incineration and fission/activation product distributions within the Los Alamos CAI are described

Nuclear fuel waste disposal

International Nuclear Information System (INIS)

Allan, C.J.

1993-01-01

The Canadian concept for nuclear fuel waste disposal is based on disposing of the waste in a vault excavated 500-1000 m deep in intrusive igneous rock of the Canadian Shield. The author believes that, if the concept is accepted following review by a federal environmental assessment panel (probably in 1995), then it is important that implementation should begin without delay. His reasons are listed under the following headings: Environmental leadership and reducing the burden on future generations; Fostering public confidence in nuclear energy; Forestalling inaction by default; Preserving the knowledge base. Although disposal of reprocessing waste is a possible future alternative option, it will still almost certainly include a requirement for geologic disposal

Spectral analysis of coolant activity from a commercial nuclear generating station

International Nuclear Information System (INIS)

Swann, J.D.; Lewis, B.J.; Ip, M.

2008-01-01

In support of the development of a real-time on-line fuel failure monitoring system for the CANDU reactor, actual gamma spectroscopy data files from the gaseous fission product (GFP) monitoring system were acquired from almost four years of operation at a commercial Nuclear Generating Station (NGS). Several spectral analysis techniques were used to process the data files. Radioisotopic activity from the plant information (PI) system was compared to an in-house C++ code that was used to determine the photopeak area and to a separate analysis with commercial software from Canberra-Aptec. These various techniques provided for a calculation of the coolant activity concentration of the noble gas and iodine species in the primary heat transport system. These data were then used to benchmark the Visual DETECT code, a user friendly software tool which can be used to characterize the defective fuel state based on a coolant activity analysis. Acceptable agreement was found with the spectral techniques when compared to the known defective bundle history at the commercial reactor. A more generalized method of assessing the fission product release data was also considered with the development of a pre-processor to evaluate the radioisotopic release rate from mass balance considerations. The release rate provided a more efficient means to characterize the occurrence of a defect and was consistent with the actual defect situation at the power plant as determined from in-bay examination of discharged fuel bundles. (author)

An assessment of the Canadian Forces' capability to manage the consequences of the domestic use of chemical, biological, radiological or nuclear weapons of mass destruction

International Nuclear Information System (INIS)

Pickering, W.L.

2003-01-01

In view of the threat to Canadian domestic targets presented by the asymmetric use of chemical, biological, radiological or nuclear (CBRN) weapons of mass destruction (WMD), this thesis examines whether the Canadian Forces (CF) has capability deficiencies in managing the consequences of such an attack. Research included an examination of the post Cold War strategic environment, the state of the art in CBRN technology, current concepts and experience in managing the consequences of major disasters and responsibilities at the municipal, provincial and federal levels of government. The methodology used included scenario based planning to develop circumstances where WMD might be used domestically, and decomposition to break down the scenarios into events and potential CF roles and tasks. The current CF structure was used to determine the probable CF response, which included the ability of CF units to perform the required tasks, the CF response time and the ability of the CF to sustain the operation. (author)

Building generation four: results of Canadian research program on generation IV energy technologies

International Nuclear Information System (INIS)

Anderson, T.; Leung, L.K.H.; Guzonas, D.; Brady, D.; Poupore, J.; Zheng, W.

2014-01-01

A collaborative grant program has been established between Natural Sciences and Engineering Research Council (NSERC) of Canada, Natural Resources Canada (NRCan), and Atomic Energy of Canada Limited (AECL) to support research and development (R&D) for the Canadian SuperCritical Water-cooled Reactor (SCWR) concept, which is one of six advanced nuclear reactor systems being studied under the Generation-IV International Forum (GIF). The financial support for this grant program is provided by NSERC and NRCan. The grant fund has supported university research investigating the neutronic, fuel, thermal-hydraulics, chemistry and material properties of the Canadian SCWR concept. Twenty-two universities have actively collaborated with experts from AECL Nuclear Laboratories and NRCan's CanmetMATERIALS (CMAT) Laboratory to advance the technologies, enhance their infrastructure, and train highly qualified personnel. Their R&D findings have been contributed to GIF fulfilling Canada's commitments. The unique collaborative structure and the contributions to Canada's nuclear science and technology of the NSERC/NRCan/AECL Generation IV Energy Technologies Program are presented. (author)

Nuclear fusion - The Sun's promise: the race for nuclear fusion. The Canadian who wants to save the World. How ITER wants to get back on track

International Nuclear Information System (INIS)

Dupin, Ludovic; Lucas, Thierry

2016-01-01

As some projects of development of reactor based on nuclear fusion already exist in France and in North America as prototypes or only projects with different objectives in terms of fabrication and exploitation, with the high ambition to produce an unlimited energy, a first article describes the works performed by start-ups in North America to develop new concepts of reactors based on nuclear fusion. These reactors are smaller, more flexible and less expensive than previous projects, and their development is supported by actors of the digital economy. A second article focuses on the example of General Fusion, a young Canadian company located near Vancouver, which is building its first prototypes of fusion reactor, and which succeeded in raising funds (more than hundred millions dollars), and grew from 4 to 65 employees in five years. The third article discusses the situation of ITER, the international experimental reactor which is being built in Cadarache, its delays and cost overruns, and the policy implemented by its new manager to try to get the project back on track

Education and training of operators and maintenance staff at commercial nuclear power stations in Japan

International Nuclear Information System (INIS)

Takahashi, M.; Kataoka, H.

1998-01-01

Safe and stable operation of a nuclear power station requires personnel fostering. In Japan, with the objectives of systematically securing qualified people for a long period of time, and maintaining and improving their skills and knowledge, the utilities have created strict personnel training plans, for continuous education and training. Concrete examples of education and training for operators and maintenance personnel at commercial nuclear power stations in Japan, such as education systems training, facility and contents of curriculum, are detailed including some related matters. Recent activities to catch up with environment changes surrounding education and training of operators and maintenance staff are also mentioned. (author)

Commercial nuclear reactors and waste: the current status

International Nuclear Information System (INIS)

Platt, A.M.; Robinson, J.V.

1980-04-01

During the last five years, the declared size of the commercial light water reactor (LWR) nuclear power industry in the US has steadily decreased. As of January 1980, the total number of power plants had dropped to 191 from the 226 in December 31, 1974. At least another nine were cancelled in the last few months. This report was developed as the first of a series to track implications to waste management due to such changes in the declared size of the industry. For the presently declared size, key conclusions are: the declared reactors will peak at a capacity of 162 GWe and consume about 10 6 MTU as enrichment feed. As few as two repositories of about 100,000 MTHM capacity each would hold the waste. Predisposal storage (reactor basins and AFRs) would peak at less than 100,000 MTHM (in the year 2020) with one repository opening in the year 1997 and the other in the year 2020. Most of the 100,000 MTHM would have to be in AFR storage unless current practice regarding reactor basin size was radically changed

Commercializing the next generation: the AP600 advanced simplified nuclear power plant

International Nuclear Information System (INIS)

Bruschi, H.J.

1994-01-01

Today, government and industry are working together on advanced nuclear power plant designs that take advantage of valuable lessons learned from the experience to date and promise to reconcile the demands of economic expansion with the laws of environmental protection. In the U.S., the Department of Energy (DOE) and the Electric Power Research Institute (EPRI) initiated a design certification program in 1989 to develop and commercialize advanced light water reactors (ALWRs) for the next round of power plant construction. Advanced, simplified technology is one approach under development to end the industry's search for a simpler, more forgiving, and less costly reactor. As part of this program, Westinghouse is developing the AP600, a new standard 600 MWe advanced, simplified plant. The design strikes a balance between the use of proven technology and new approaches. The result is a greatly streamlined plant that can meet safety regulations and reliability requirements, be economically competitive, and promote broader public confidence in nuclear energy. 1 fig

A model for the release, dispersion and environmental impact of a postulated reactor accident from a submerged commercial nuclear power plant

Science.gov (United States)

Bertch, Timothy Creston

1998-12-01

Nuclear power plants are inherently suitable for submerged applications and could provide power to the shore power grid or support future underwater applications. The technology exists today and the construction of a submerged commercial nuclear power plant may become desirable. A submerged reactor is safer to humans because the infinite supply of water for heat removal, particulate retention in the water column, sedimentation to the ocean floor and inherent shielding of the aquatic environment would significantly mitigate the effects of a reactor accident. A better understanding of reactor operation in this new environment is required to quantify the radioecological impact and to determine the suitability of this concept. The impact of release to the environment from a severe reactor accident is a new aspect of the field of marine radioecology. Current efforts have been centered on radioecological impacts of nuclear waste disposal, nuclear weapons testing fallout and shore nuclear plant discharges. This dissertation examines the environmental impact of a severe reactor accident in a submerged commercial nuclear power plant, modeling a postulated site on the Atlantic continental shelf adjacent to the United States. This effort models the effects of geography, decay, particle transport/dispersion, bioaccumulation and elimination with associated dose commitment. The use of a source term equivalent to the release from Chernobyl allows comparison between the impacts of that accident and the postulated submerged commercial reactor plant accident. All input parameters are evaluated using sensitivity analysis. The effect of the release on marine biota is determined. Study of the pathways to humans from gaseous radionuclides, consumption of contaminated marine biota and direct exposure as contaminated water reaches the shoreline is conducted. The model developed by this effort predicts a significant mitigation of the radioecological impact of the reactor accident release

Lessons learned in planning the Canadian Nuclear Legacy Liabilities Program

International Nuclear Information System (INIS)

Stephens, Michael E.; Brooks, Sheila M.; Miller, Joan M.; Mason, Robert A.

2011-01-01

In 2006, Atomic Energy of Canada Limited (AECL) and Natural Resources Canada (NRCan) began implementing a $7B CDN, 70-year Nuclear Legacy Liabilities Program (NLLP) to deal with legacy decommissioning and environmental issues at AECL nuclear sites. The objective of the NLLP is to safely and cost-effectively reduce the nuclear legacy liabilities and associated risks based on sound waste management and environmental principles in the best interest of Canadians. The liabilities include shutdown research and prototype power reactors, fuel handling facilities, radiochemical laboratories, support buildings, radioactive waste storage facilities, and contaminated lands at several sites located across eastern Canada from Quebec to Manitoba. The largest site, Chalk River Laboratories (CRL) in Ontario, will continue as an operational nuclear site for the foreseeable future. Planning and delivery of the Program is managed by the Liability Management Unit (LMU), a group that was formed within AECL for the purpose. The composition and progress of the NLLP has been reported in recent conferences. The NLLP comprises a number of interlinked decommissioning, waste management and environmental restoration activities that are being executed at different sites, and by various technical groups as suppliers to the LMU. Many lessons about planning and executing such a large, diverse Program have been learned in planning the initial five-year 'start-up' phase (which will conclude 2011 March), in planning the five-year second phase (which is currently being finalized), and in planning individual and interacting activities within the Program. The activities to be undertaken in the start-up phase were planned by a small group of AECL technical experts using the currently available information on the liabilities. Progress in executing the Program was slower than anticipated due to less than ideal alignment between some planned technical solutions and the actual requirements, as well as the

Canadian-based aircrew exposure from cosmic radiation on commercial airline routes

Energy Technology Data Exchange (ETDEWEB)

McCall, M.J.; Green, A.R.; Lewis, B.J.; Bennett, L.G.I.; Pierre, M. [Royal Military College of Canada, Kingston, Ontario (Canada); Schrewe, U. [Physikalisch Technische Bundesanstalt, Braunschweig (Germany); O' Brien, K. [Northern Arizona Univ., Flagstaff, Arizona (United States); Feldsberger, E. [University of Graz (Austria)

2000-07-01

As part of a continuing study on the occupational exposure of Canadian-based aircrew, a Tissue Equivalent Proportional Counter (TEPC) was used to monitor this exposure on 64 flight routes spanning a range of geomagnetic latitudes between 40{sup o}S and 85{sup o}N. The microdosimetric data obtained from these flights were compared to that obtained from several terrestrial sources and were used to characterize the radiation field at jet altitudes. From 20 000 ambient dose equivalent rates obtained at various altitudes and geomagnetic latitudes, a correlation was developed to allow for the interpolation of the dose rate for any global position, altitude and date. By integration of this dose rate function over a great circle flight path, a predictive code was developed to provide a total ambient dose equivalent prediction for a given flight. (author)

Unlocking the atom : the Canadian book on nuclear technology

International Nuclear Information System (INIS)

Tammemagi, H.; Jackson, D.

2002-01-01

This book describes Canada's role in developing a world-class reactor, medical isotope and food irradiation systems and it's leading role in uranium mining. It gives an introduction to both natural and man-made radiation and covers the spectrum of nuclear technology that includes power reactors, nuclear safety, nuclear waste, medicine, uranium, fusion, industrial and research applications. The second chapter in this book introduces the reader to nuclear fission, the fission reactor, nuclear weapons and the Candu Nuclear Power Reactor. The third chapter familiarizes the reader with different types of natural and man-made radiations. The fourth chapter discusses the biological effects of radiation. Electricity and the different technologies to produce electrical power are the subject of chapter five. The Candu reactor and the various Candu designs and performance are discussed in some detail in chapter six. In chapter seven the authors discuss the different types of reactors that have been constructed worldwide. Nuclear safety and nuclear regulations are the subject of chapter eight. In chapter nine the authors discuss nuclear power and the environment. High-level nuclear waste and nuclear waste disposal are discussed in chapter ten. Diagnostic and therapeutic nuclear medicine is the subject of chapter eleven. The benefits of nuclear technology in industry and science are discussed in chapter twelve. Uranium mining and uranium as the nuclear fuel are discussed in chapter thirteen. Chapter fourteen discusses the future of fission with respect to advanced Candu fuel cycles and advanced Candu reactor designs. Chapter fifteen is a discussion of nuclear fusion and Canada's role in fusion research. Chapter sixteen discusses nuclear science and research and the role of the National nuclear laboratory and the universities

Behaviors and Conditions that Challenge Teamwork: An Assessment of Operating Events at U.S. Commercial Nuclear Power Plants

International Nuclear Information System (INIS)

Desaulniers, David R.

1998-01-01

As part of its regulatory activities, the U.S. Nuclear Regulatory Commission (NRC) reviews events and routine activities at commercial nuclear power facilities throughout the United States. Frequently, these reviews have highlighted team performance as an important factor in either the initiation or mitigation of significant events and conditions at these facilities. This paper summarizes operating experience relevant to the understanding of teamwork at U.S. nuclear power plants during recent years, describes the specific behaviors that were considered detrimental to team performance, and discusses the conditions that were identified as contributing to these behaviors. (author)

Proceedings of the Canadian Nuclear Society international conference on containment design

International Nuclear Information System (INIS)

Black, R.K.

1984-01-01

The subject of containment was discussed under the major topic headings of: USA views on containment design operation and regulation, containment structure analysis, containment envelope and energy suppression systems, European views on containment design operation and regulation, containment atmosphere control, Canadian views on containment design operation and regulation, containment analysis, and regulatory requirements, testing, and periodic inspection

Canadian experience with spin-offs from nuclear technology

International Nuclear Information System (INIS)

Lennox, C.G.; Garvey, P.M.

1989-01-01

The innovation process introduced into AECL's research laboratories is described, with its achievements in increased commercial and spin-off businesses. In particular, the role of the champion or entrepreneur is emphasized in the manner in which he/she interacts within a dedicated team to pursue each opportunity. Examples are provided of several commercial and business development opportunities resulting from the background research programs

The future of nuclear power

International Nuclear Information System (INIS)

Horton, S.G.

1987-01-01

Canadians are heavily dependent upon reliable and affordable sources of energy to sustain their lifestyle. In a world threatened by diminishing energy resources, Canadians need to plan for the future. Canadian electrical utilities must respond to rapidly changing circumstances and uncertainties to ensure that the public's demand for electricity is met with a high quality product. There is a need to strike a proper balance between demand management alternatives and new supply options. Nuclear power will remain as an alternative supply option. The place of CANDU will depend upon its continued high performance, public acceptance and the leadership given to the program

Regulation of the Canadian nuclear industry

International Nuclear Information System (INIS)

Gummer, W.K.

1982-02-01

This paper reviews the nuclear regulatory process in Canada in the following context. First, the pertinent factors in the present political and economic environment are identified, including both domestic and international matters. Second, the basis for current Atomic Energy Control Board operations is considered, with reference to both the Atomic Energy Control Act (1946) and the proposed Nuclear Control and Administration Act (Bill C-14, 1977). Some specific areas of the regulatory process are discussed in detail to show where ambiguity or uncertainty may arise: these areas are uranium exploration and mining, occupational health and safety, environmental protection, waste management, heavy water plants and transportation

The Price-Anderson Act: A Linchpin in the Development of Commercial Nuclear Power in the United States

International Nuclear Information System (INIS)

Quattrocchi, J. L.

2006-01-01

The dawn of the atomic age brought with it both the hope of great benefit and the fear of great disaster. By the mid-1950's, the United States recognized that it was in the national interest to promote commercial development of nuclear energy in medicine and industry, particularly in the generation of electric power. The uncertainties of the technology and the potential for severe accidents were clear obstacles to commercial development. Exposure to potentially serious uninsured liabilities inhibited the private sector. These impediments led Congress to enact the Price-Anderson Act in 1957. Its three-fold purpose was to encourage private development of nuclear power, establish a framework for handling liability claims and provide a ready source of funds to compensate accident victims. The law was originally enacted for ten years but has now been extended four times. The major provisions of the Act and its importance to the public and to insurers are described in this paper.(author)

The Canadian Safeguards Support Program - A future outlook

International Nuclear Information System (INIS)

Keeffe, R.; Truong, Q.S. Bob

2001-01-01

Full text: The Canadian Safeguards Support Program (CSSP) is one of the first safeguards support programs with an overall objective to assist the IAEA by providing technical assistance and other resources and by developing equipment to improve the effectiveness of international safeguards. This paper provides a brief discussion of the evolution of the CSSP, from the beginning when the program was under joint management between the Atomic Energy Control Board (AECB) and Atomic Energy of Canada Limited (AECL), a Canadian crown corporation, until recent years when the AECB became responsible for all projects and financial management. Recently, new legislation came into force and the AECB became the Canadian Nuclear Safety Commission (CNSC). However, the mandate and management of the CSSP under the CNSC remain fundamentally unchanged. Major CSSP activities are devoted to the following areas: (a) Human resource assistance through the provision of cost-free experts (CFEs) to the IAEA; (b) Training of IAEA inspectors and facility operators, development of training resources and integrated approaches for training; (c) System studies, e.g. the development of integrated safeguards approach for CANDU reactors, geological repository, and physical model; (d) Equipment development, e.g. the VXI Integrated Fuel Monitor, Digital Cerenkov Viewing Device, seals, remote monitoring, encryption and authentication; (e) Information technology which includes satellite imagery, Geographical Information System (GIS), and position tracking of spent fuel containers. The CSSP has continued to evolve during the past 25 years. Although formerly larger the CSSP budget has settled to a stable level of just slightly above (Canadian) $2M. Leveraging of the CSSP budget through collaborations with several Member State Support Programs and Canadian government departments has provided mutual benefits for all parties involved and useful results that have been put into practical use by the IAEA. (author)

Canadian propane industry by the numbers

International Nuclear Information System (INIS)

Anon.

1999-01-01

Excerpts from the 1997 'Canadian Propane Industry Statistical Review in Brief' are provided to illustrate propane production, transportation, industrial, automotive, agricultural, residential, commercial and public administration uses. Of the 12.67 billion litres of propane produced in Canada in 1997, approximately 60 per cent was exported to the United States at an average export price of 14.17 cents per litre. Total value of propane exports to the United States in 1997 exceeded one billion dollars. Ninety-five per cent of all propane produced in Canada originated from gas plants in Alberta. Major refinery production, as well as use as petrochemical feedstock was in Ontario, Alberta and Quebec

Civilian protection and Britain's commercial nuclear installations

International Nuclear Information System (INIS)

1981-01-01

The subject is treated as follows: initial conclusions (major nuclear attack on military installations; nuclear attack including civil nuclear targets; conventional attack on civil nuclear installations); nature of nuclear weapons explosions and power reactor releases (general; dose effects and biologically significant isotopes; nuclear weapon effects; effect of reactors and other fuel-cycle installations in a thermonuclear area; implications of reactor releases due to conventional attack, sabotage, civil disorder or major accident). (U.K.)

Canadian digitization: radical beginning and pragmatic follow-on

Science.gov (United States)

Grant, Terrill K.

2000-08-01

The Canadian Army, like most Western armies, spent a lot of time soul-searching about the application of technology to its Command and Control processes during the height of the Cold War in the 70's and 80's. In the late 1980's, these efforts were formalized in a program called the Tactical Command, Control and Communications System (TCCCS). As envisioned, the project would replace in one revolutionary Big Bang all of the tactical communications employed in the Canadian field forces. It would also add significant capabilities such as a long range satellite communications system, a universal tactical e-mail system, and a command and control system for the commander and his staff from division to unit HQ. In 1989, the project was scaled back due to budgetary constraints by removing the divisional trunk communications system and the command and control system. At this point a contract was let to Computing Devices Canada for the core communications functionality. During the next 6 years, the Canadian Army expanded on this digitization effort by amending the contract to add in a trunk system and a situational awareness system. As well, in 1996, Computing Devices received a contract to develop and integrate a C2 system with the communications system thereby restoring the final two Cs of TCCCS. This paper discusses the architecture and implementation of the TCCCS as the revolutionary enabler of the Canadian Army's digitization effort for the early 2000 era. The choice of a hybrid approach of using commercial standards supplemented by appropriate NATO communications standards allowed for an easy addition of the trunk system. As well, conformance to the emerging NATO Communications architecture for Land Tactical Communications in the Post 2000 era will enhance interoperability with Canada's allies. The paper also discusses the pragmatic approach taken by the Canadian Army in inserting C2 functionally into TCCCS, and presents the ultimate architecture and functionality. This

Development of first full scope commercial CANDU-6 fuel handling simulator

Energy Technology Data Exchange (ETDEWEB)

Crawford, W., E-mail: BCrawford@atlanticnuclear.ca [Atlantic Nuclear Services Inc., Fredericton, NB (Canada); McInerney, J. M., E-mail: JMcInerney@nbpower.com [Point Lepreau Generating Station, Maces Bay, NB (Canada); Moran, E.S.; Nice, J. W.; Sinclair, D.M.; Somerville, S.; Usalp, E.C.; Usalp, M., E-mail: EMoran@atlanticnuclear.ca, E-mail: JNice@atlanticnuclear.ca, E-mail: DSinclair@atlanticnuclear.ca, E-mail: SSomerville@atlanticnuclear.ca, E-mail: ECUsalp@atlanticnuclear.ca, E-mail: MUsalp@atlanticnuclear.ca [Atlantic Nuclear Services Inc., Fredericton, NB (Canada)

2015-07-01

Unique to CANDU reactors is continuous on-power refueling. In the CANDU-6 design, the fuel bundles are contained within 380 pressure tubes. Fuelling machines, one on either side of the reactor face move on a bridge and carriage system to the appointed channel and fuel under computer control. The fuelling machine is an immensely complicated mechanical device. None of the original Canadian full scope simulators incorporated the interaction of the fuel handling system. Traditionally, the final stages of Fuel Handling Operator qualification utilizes on the job training in a production environment carried out in the station main control room. For the purpose of supporting continual improvement in fuel handling training at the Third Qinshan Nuclear Plant Company (TQNPC), Atlantic Nuclear Services in a joint project with New Brunswick Power, developed the first commercial full scope CANDU-6 Fuel Handling simulator, integrated into the existing TQNPC Full Scope Simulator framework. The TQNPC Fuel Handling simulator is capable of supporting all normal on-power and off-power refuelling procedures as well as other abnormal operating conditions, which will allow training to be conducted, based on the plant specific operating procedures. This paper will discuss its development, the importance of this tool and its advantages over past training practices. (author)

Development of first full scope commercial CANDU-6 fuel handling simulator

International Nuclear Information System (INIS)

Crawford, W.; McInerney, J. M.; Moran, E.S.; Nice, J. W.; Sinclair, D.M.; Somerville, S.; Usalp, E.C.; Usalp, M.

2015-01-01

Unique to CANDU reactors is continuous on-power refueling. In the CANDU-6 design, the fuel bundles are contained within 380 pressure tubes. Fuelling machines, one on either side of the reactor face move on a bridge and carriage system to the appointed channel and fuel under computer control. The fuelling machine is an immensely complicated mechanical device. None of the original Canadian full scope simulators incorporated the interaction of the fuel handling system. Traditionally, the final stages of Fuel Handling Operator qualification utilizes on the job training in a production environment carried out in the station main control room. For the purpose of supporting continual improvement in fuel handling training at the Third Qinshan Nuclear Plant Company (TQNPC), Atlantic Nuclear Services in a joint project with New Brunswick Power, developed the first commercial full scope CANDU-6 Fuel Handling simulator, integrated into the existing TQNPC Full Scope Simulator framework. The TQNPC Fuel Handling simulator is capable of supporting all normal on-power and off-power refuelling procedures as well as other abnormal operating conditions, which will allow training to be conducted, based on the plant specific operating procedures. This paper will discuss its development, the importance of this tool and its advantages over past training practices. (author)

Independent verification in operations at nuclear power plants

International Nuclear Information System (INIS)

Donderi, D.C.; Smiley, A.; Ostry, D.J.; Moray, N.P.

1995-09-01

A critical review of approaches to independent verification in operations used in nuclear power plant quality assurance programs in other countries, was conducted for this study. This report identifies the uses of independent verification and provides an assessment of the effectiveness of the various approaches. The findings indicate that at Canadian nuclear power plants as much, if not more, independent verification is performed than at power plants in the other countries included in the study. Additional requirements in this area are not proposed for Canadian stations. (author)

Nuclear criticality safety in Canada

International Nuclear Information System (INIS)

Shultz, K.R.

1980-04-01

The approach taken to nuclear criticality safety in Canada has been influenced by the historical development of participants. The roles played by governmental agencies and private industry since the Atomic Energy Control Act was passed into Canadian Law in 1946 are outlined to set the scene for the current situation and directions that may be taken in the future. Nuclear criticality safety puts emphasis on the control of materials called special fissionable material in Canada. A brief account is given of the historical development and philosophy underlying the existing regulations governing special fissionable material. Subsequent events have led to a change in emphasis in the regulatory process that has not yet been fully integrated into Canadian legislation and regulations. Current efforts towards further development of regulations governing the practice of nuclear criticality safety are described. (auth)

Annual report 1975-1976

International Nuclear Information System (INIS)

1976-01-01

Progress, performance, and future plans are described for Canadian nuclear power plants, heavy water plants, nuclear research, commercial uses of radiation and radioisotopes, operations and administration, health protection, and collaboration with industry. (E.C.B.)

Research and development for Canadian nuclear power

International Nuclear Information System (INIS)

Robertson, J.A.

1976-01-01

Rapid expansion of the successful CANDU reactor system offers immediate substitution for scarce oil and gas, combined with long-term security of energy supplies. A continuing large and vigorous R and D program on nuclear power is essential to achieve these objectives. The program, described here, consists of tactical R and D in support of the current CANDU reactor system, strategic R and D to develop and demonstrate advanced CANDU systems, and exploratory R and D to put Canada in a position to exploit any fusion opportunities. Two support activities, management of radioactive wastes and techniques to safeguard nuclear materials against diversion, although integral components of the nuclear power programs, are identified separately because they are currently of special public interest. (author)

The Canadian initiative to bring the international thermonuclear experimental reactor to Canada

International Nuclear Information System (INIS)

James, R.A.

1996-01-01

The International Thermonuclear Experimental Reactor (ITER) is the next step in fusion research. It is expected to be the last major experimental facility, before the construction of a prototype commercial reactor. The Engineering Design Activities (EDA) of ITER are being funded by the USA, Japan, the Russian Federation, and the European Union, with each of the major parties contributing about 25% of the cost. Canada participates as part of the European coalition. The EDA is due to be completed in 1998, and the major funding partners are preparing for the decision on the siting and construction of ITER. The Canadian Fusion Fuels Technology Project (CFFTP) formed a Canadian ITER Siting Task Group to study siting ITER in Canada. The study indicated that hosting ITER would provide significant benefits, both technological and economic, to Canada. We have also confirmed that there would be substantial benefits to the ITER Project. CFFTP then formed a Canadian ITER Siting Board, with representation from a broad range of stakeholders, to champion, 'Canada as Host'. This paper briefly outlines the ITER Project, and the benefits to both Canada and the Project of a Canadian site. With this as background, the paper discusses the international scene and assesses Canada's prospects of being chosen to host ITER. (author)

The feasibility of using the 25MW super near boiling nuclear reactor (SNB25) to provide thermal and electrical energy for a large Canadian Forces base in the Canadian Arctic

Energy Technology Data Exchange (ETDEWEB)

Paquette, S.; Bonin, H.W.; Baskin, M.; Bowen, K.; Switzer, Z., E-mail: Stephane.Paquette@rmc.ca [Royal Military College of Canada, Dept. of Chemistry and Chemical Engineering, Kingston, Ontario (Canada)

2014-07-01

A feasibility study of a power plant using the Super Near Boiling 25 MWt (SNB25) nuclear reactor as a heat source and capable of supporting the electrical and thermal requirements for a base the size of Canadian Forces Base (CFB) Kingston in the Arctic was carried out. Such a power plant would allow the Canadian Armed Forces (CAF) to have a self-sustaining operational base in the Arctic to conduct Search and Rescue (SAR) and sovereignty missions. The thermal and electrical requirements for a base the size of CFB Kingston are determined to be 31.63 MWt and 7.16 MWe, respectively. Using the Heating Degree Days (HDD) approach to account for temperature differences between Southern Ontario and the Arctic, a base the size of CFB Kingston in the Arctic would require 75.16 MWt to operate. A chemical engineering software program, UniSim, was used to simulate the energy cycle of the base which consisted of a district heating loop to provide hot water and an Organic Rankine Cycle (ORC) using n-pentane as the working fluid to provide the electrical energy. The UniSim simulations determined that the cycle would use six shell and tube heat exchangers, two axial gas turbines coupled to generators, and twelve centrifugal pumps, in addition to a group of five SNB25 reactors that could provide 25.03 MWt and 2.63 MWe to a base in the Arctic with energy requirements about a third of those of CFB Kingston. The design foresees redundancy which is essential to safe operation in the Arctic. (author)

Romanian nuclear fuel program

International Nuclear Information System (INIS)

Budan, O.

1999-01-01

The paper presents and comments the policy adopted in Romania for the production of CANDU-6 nuclear fuel before and after 1990. The CANDU-6 nuclear fuel manufacturing started in Romania in December 1983. Neither AECL nor any Canadian nuclear fuel manufacturer were involved in the Romanian industrial nuclear fuel production before 1990. After January 1990, the new created Romanian Electricity Authority (RENEL) assumed the responsibility for the Romanian Nuclear Power Program. It was RENEL's decision to stop, in June 1990, the nuclear fuel production at the Institute for Nuclear Power Reactors (IRNE) Pitesti. This decision was justified by the Canadian specialists team findings, revealed during a general, but well enough technically founded analysis performed at IRNE in the spring of 1990. All fuel manufactured before June 1990 was quarantined as it was considered of suspect quality. By that time more than 31,000 fuel bundles had already been manufactured. This fuel was stored for subsequent assessment. The paper explains the reasons which provoked this decision. The paper also presents the strategy adopted by RENEL after 1990 regarding the Romanian Nuclear Fuel Program. After a complex program done by Romanian and Canadian partners, in November 1994, AECL issued a temporary certification for the Romanian nuclear fuel plant. During the demonstration manufacturing run, as an essential milestone for the qualification of the Romanian fuel supplier for CANDU-6 reactors, 202 fuel bundles were produced. Of these fuel bundles, 66 were part of the Cernavoda NGS Unit 1 first fuel load (the balance was supplied by Zircatec Precision Industries Inc. ZPI). The industrial nuclear fuel fabrication re-started in Romania in January 1995 under AECL's periodical monitoring. In December 1995, AECL issued a permanent certificate, stating the Romanian nuclear fuel plant as a qualified and authorised CANDU-6 fuel supplier. The re-loading of the Cernavoda NGS Unit 1 started in the middle

Development of a Flexible Computerized Management Infrastructure for a Commercial Nuclear Power Plant

International Nuclear Information System (INIS)

Ali, Syed Firasat; Hajek, Brian K.; Usman, Shoaib

2006-01-01

The report emphasizes smooth transition from paper-based procedure systems (PBPSs) to computer-based procedure systems (CBPSs) for the existing commercial nuclear power plants in the U.S. The expected advantages and of the transition are mentioned including continued, safe and efficient operation of the plants under their recently acquired or desired extended licenses. The report proposes a three-stage survey to aid in developing a national strategic plan for the transition from PBPSs to CBPSs. It also includes a comprehensive questionnaire that can be readily used for the first stage of the suggested survey

Development of a Flexible Computerized Management Infrastructure for a Commercial Nuclear Power Plant

Energy Technology Data Exchange (ETDEWEB)

Ali, Syed Firasat; Hajek, Brian K.; Usman, Shoaib

2006-05-01

The report emphasizes smooth transition from paper-based procedure systems (PBPSs) to computer-based procedure systems (CBPSs) for the existing commercial nuclear power plants in the U.S. The expected advantages and of the transition are mentioned including continued, safe and efficient operation of the plants under their recently acquired or desired extended licenses. The report proposes a three-stage survey to aid in developing a national strategic plan for the transition from PBPSs to CBPSs. It also includes a comprehensive questionnaire that can be readily used for the first stage of the suggested survey.

Erosion by pleistocene continental ice sheets in the area of the Canadian Shield

International Nuclear Information System (INIS)

Rutter, N.W.

The principles, theory and knowledge on the behaviour of glaciers indicate that only confined glacier flow is a major erosional agent. Unconfined, areally flowing ice sheets such as those present over the Canadian Shield during the Pleistocene Period modified the landscape very little. The potential for deep glacial erosion in future glaciations over the Canadian Shield area is low. Nuclear waste disposal sites, based only upon potential glacial erosion, should be located a few hundred meters below the surface in competent, fractureless crystalline shield bedrock, in relatively reliefless terrain, a few hundred kilometers away from the Paleozoic boundary. (auth)

Nuclear closed-cycle gas turbine (HTGR-GT): dry cooled commercial power plant studies

International Nuclear Information System (INIS)

McDonald, C.F.; Boland, C.R.

1979-11-01

Combining the modern and proven power conversion system of the closed-cycle gas turbine (CCGT) with an advanced high-temperature gas-cooled reactor (HTGR) results in a power plant well suited to projected utility needs into the 21st century. The gas turbine HTGR (HTGR-GT) power plant benefits are consistent with national energy goals, and the high power conversion efficiency potential satisfies increasingly important resource conservation demands. Established technology bases for the HTGR-GT are outlined, together with the extensive design and development program necessary to commercialize the nuclear CCGT plant for utility service in the 1990s. This paper outlines the most recent design studies by General Atomic for a dry-cooled commercial plant of 800 to 1200 MW(e) power, based on both non-intercooled and intercooled cycles, and discusses various primary system aspects. Details are given of the reactor turbine system (RTS) and on integrating the major power conversion components in the prestressed concrete reactor vessel

Response to 'Decades of delay in nuclear waste disposal - a failure to communicate'

International Nuclear Information System (INIS)

Nagasaki, S.

2014-01-01

In a recent opinion piece on the delay of nuclear waste disposal, Mr. H. Tammemagi asserts that it is important for a nuclear community to include in the Canadian public discourse the presence of natural radiation, comparisons between radioactive and non-radioactive wastes, and nuclear medicine. It is to the first two that I respond to, with the view that the lessons learnt from Japan have merit for addressing the issues in the Canadian context. (author)

Ontario is not ready to face a large-scale nuclear accident

International Nuclear Information System (INIS)

2017-07-01

On paper, in Japan as elsewhere, nuclear emergency plans are based on international standards and all look similar. The counter measures are sheltering, potassium iodate prophylaxis, evacuation and control of foodstuffs. With 18 nuclear reactors to produce electricity and a research reactor, Ontario should be especially well prepared. Moreover, in USA, there are six power plants located at less than 100 km from the Canadian border. Would Ontario do better than Japan in case of a severe nuclear disaster? Ontario is not ready to face a severe nuclear accident and the population surrounding nuclear power stations are at risk. The large number of inhabitants will hamper protective response actions. Consequently, Canadian authorities keep lax protective action levels. Using more stringent levels would mean to extend the protection zone that would include a too large number of persons. Canadian authorities should openly acknowledge that a severe nuclear accident could happen in Ontario like in any other country and trigger a complete reorganisation of emergency preparedness and response (EP and R) to cope with such a possibility. New response plans should be defined with the involvement of stakeholders

Commercial incineration demonstration

International Nuclear Information System (INIS)

Borduin, L.C.; Neuls, A.S.

1981-01-01

Low-level radioactive wastes (LLW) generated by nuclear utilities presently are shipped to commercial burial grounds for disposal. Substantially increasing shipping and disposal charges have sparked renewed industry interest in incineration and other advanced volume reduction techniques as potential cost-saving measures. Repeated inquiries from industry sources regarding LLW applicability of the Los Alamos controlled-air incineration (CAI) design led DOE to initiate this commercial demonstration program in FY-1980. The selected program approach to achieving CAI demonstration at a utility site is a DOE sponsored joint effort involving Los Alamos, a nuclear utility, and a liaison subcontractor. Required development tasks and responsibilities of the particpants are described. Target date for project completion is the end of FY-1985

Aging Management Guideline for commercial nuclear power plants: Motor control centers

International Nuclear Information System (INIS)

Toman, G.; Gazdzinski, R.; O'Hearn, E.

1994-02-01

This Aging Management Guideline (AMG) provides recommended methods for effective detection and mitigation of age-related degradation mechanisms in Boiling Water Reactor (BWR) and Pressurized Water Reactor (PWR) commercial nuclear power plant motor control centers important to license renewal. The intent of this AMG is to assist plant maintenance and operations personnel in maximizing the safe, useful life of these components. It also supports the documentation of effective aging management programs required under the License Renewal Rule 10 CFR Part 54. This AMG is presented in a manner that allows personnel responsible for performance analysis and maintenance to compare their plant-specific aging mechanisms (expected or already experienced) and aging management program activities to the more generic results and recommendations presented herein

Canadian decommissioning experience from policy to project

International Nuclear Information System (INIS)

Pare, F.E.

1992-01-01

The Canadian policy on decommissioning of nuclear facilities as defined in the Atomic Energy Control Act and Regulations is administered by the Atomic Energy Control Board (AECB), a Federal Government agency. It requires that these facilities be decommissioned according to approved plans which are to be developed by the owner of the nuclear facility during its early stages of design and to be refined during its operating life. In this regulatory environment, Atomic Energy of Canada Limited (AECL) has developed a decommissioning strategy for power stations which consists of three distinctive phases. After presenting AECL's decommissioning philosophy, this paper explains its foundations and describes how it has and soon will be applied to various facilities. It terminates by providing a brief summary of the experience gained up to date on the implementation of this strategy

Scenario analysis for the postclosure assessment of the Canadian concept for nuclear fuel waste disposal

Energy Technology Data Exchange (ETDEWEB)

Goodwin, B W; Stephens, M E; Davison, C C; Johnson, L H; Zach, R

1994-12-01

AECL Research has developed and evaluated a concept for disposal of Canada`s nuclear fuel waste involving deep underground disposal of the waste in intrusive igneous rock of the Canadian Shield. The postclosure assessment of this concept focusses on the effects on human health and the environment due to potential contaminant releases into the biosphere after the disposal vault is closed. Both radiotoxic and chemically toxic contaminants are considered. One of the steps in the postclosure assessment process is scenario analysis. Scenario analysis identifies factors that could affect the performance of the disposal system and groups these factors into scenarios that require detailed quantitative evaluation. This report documents a systematic procedure for scenario analysis that was developed for the postclosure assessment and then applied to the study of a hypothetical disposal system. The application leads to a comprehensive list of factors and a set of scenarios that require further quantitative study. The application also identifies a number of other factors and potential scenarios that would not contribute significantly to environmental and safety impacts for the hypothetical disposal system. (author). 46 refs., 3 tabs., 3 figs., 2 appendices.

Scenario analysis for the postclosure assessment of the Canadian concept for nuclear fuel waste disposal

International Nuclear Information System (INIS)

Goodwin, B.W.; Stephens, M.E.; Davison, C.C.; Johnson, L.H.; Zach, R.

1994-12-01

AECL Research has developed and evaluated a concept for disposal of Canada's nuclear fuel waste involving deep underground disposal of the waste in intrusive igneous rock of the Canadian Shield. The postclosure assessment of this concept focusses on the effects on human health and the environment due to potential contaminant releases into the biosphere after the disposal vault is closed. Both radiotoxic and chemically toxic contaminants are considered. One of the steps in the postclosure assessment process is scenario analysis. Scenario analysis identifies factors that could affect the performance of the disposal system and groups these factors into scenarios that require detailed quantitative evaluation. This report documents a systematic procedure for scenario analysis that was developed for the postclosure assessment and then applied to the study of a hypothetical disposal system. The application leads to a comprehensive list of factors and a set of scenarios that require further quantitative study. The application also identifies a number of other factors and potential scenarios that would not contribute significantly to environmental and safety impacts for the hypothetical disposal system. (author). 46 refs., 3 tabs., 3 figs., 2 appendices

'When you use the term 'long term', how long is that term'. Risk, Exclusion, and the Politics of Knowledge Production in Canadian Nuclear Fuel Waste Management Policy Making

Energy Technology Data Exchange (ETDEWEB)

Stanley, Anna [Univ. of Guelph (Canada). Dept. of Geography

2006-09-15

Risk operates within Canadian Nuclear Fuel Waste (NFW) management policy making as a heuristic for knowledge production about its effects which reconciles the knowledge of the nuclear industry with the outcomes of the NFW management process. In so doing it marginalizes the present and historical experiences of Aboriginal peoples with the nuclear industry, and removes from view the ways in which they have been implicated in the geography and political economy of the nuclear industry. Risk is a discursive form that protects a particular group's claims about the effects of NFW by providing it a universalizing epistemological structure with which to obscure its connection to context. Further risk discourse provides the nuclear industry with a conceptual vocabulary that deliberately casts all competing knowledge as perceptions, values, or as an object of inquiry. The arguments of Aboriginal peoples about the residual effects of radiation in their lands which hosted nuclear activities, such as uranium mining and disposal, have no representation in how the discourse of risk defines and represents knowledge, and thus no purchase in the policy debate. As a result the challenge they present to the nuclear industry's claims are contained. The arrangements which permit the unloading of the negative effects of nuclear power generation onto Aboriginal peoples are thus reproduced (both materially and conceptually), but not shown, by the policy making process and likely, its outcome. In order to raise critical questions about the democratic abilities of risk, this paper has examined the role of 'risk' in Canadian NFW policy making. I have shown how when the politics of knowledge production within the philosophy of risk is analyzed, and the use and role of the notion of risk are interrogated, difficult questions are posed for the democratic potential of risk. I have suggested, through an analysis of the NWMO's representations of Aboriginal content in their

Surrogate pregnancy: a guide for Canadian prenatal health care providers

OpenAIRE

Reilly, Dan R.

2007-01-01

Providing health care for a woman with a surrogate pregnancy involves unique challenges. Although the ethical debate surrounding surrogacy continues, Canada has banned commercial, but not altruistic, surrogacy. In the event of a custody dispute between a surrogate mother and the individual(s) intending to parent the child, it is unclear how Canadian courts would rule. The prenatal health care provider must take extra care to protect the autonomy and privacy rights of the surrogate. There is l...

Nuclear power : exploding the myths

International Nuclear Information System (INIS)

Edwards, G.

2001-01-01

A critique of the Canadian government's unaccountability in terms of nuclear decisions was presented. The federal government has spent more than $13 billion building dozens of nuclear facilities, and spreading Canadian nuclear technology to India, Pakistan, Taiwan, Korea, Argentina and Romania. The author argued that this was done without any public consultation or public debate. In addition, the federal government announced in 1996 that it will play a role in nuclear disarmament and would accept tonnes of leftover plutonium from dismantled nuclear warheads to be used as fuel in CANDU reactors. Samples of weapons plutonium fuels from Russia and the United States are currently being tested in a reactor at Chalk River, Ontario. In addition, China received a $1.5 billion loan from the Treasury of Canada to help finance a CANDU reactor. It was the largest loan in Canadian history, yet had no procedure to obtain taxpayer's permission. Turkey was promised an equal amount if it would build a CANDU reactor. Despite this activity, the nuclear industry is in a dying state. No reactors have been ordered in North America for the past 25 years and there are no future prospects. Nuclear expansion has also ground to a halt in western Europe, Germany, Sweden, Switzerland and France. The author discussed the association of nuclear energy with nuclear weapons and dispelled the myth that the nuclear energy programs have nothing to do with nuclear weapons. He also dispelled the myth that plutonium extracted from dismantled warheads can be destroyed by burning it as fuel in civilian reactors. The author emphasized that nuclear warheads are rendered useless when their plutonium cores are removed, but there is no method for destroying the plutonium, which constitutes a serious danger. The third myth which he dispelled was that nuclear power can significantly reduce greenhouse gas emissions. Studies show that each dollar invested in energy efficiency saves 5 to 7 times as much carbon

Lesson Learned in Preparation for Decommissioning of Three Canadian Prototype Power Reactors

International Nuclear Information System (INIS)

Vickerd, Meggan; Kenny, Stephen

2016-01-01

Lesson learned by Canadian Nuclear Laboratories (CNL)(former AECL) in preparation for decommissioning of three Prototype Reactors is a result of various strategies used for each site. CNL is responsible for the eventual decommissioning of three prototype power reactors; Nuclear Power Demonstration (NPD), Gentilly-1 and Douglas Point. Each of the Canadian prototype power reactor sites shutdown using different strategies. Depending on the site location, configuration, and intended designation of the respective sites, the individual facility systems (ventilation, electrical system, fire detection etc.) were also shut down using different strategies and operating objectives. As CNL embarks on decommissioning the first Canadian prototype reactor, this paper will reflect on the lessons learned over the past thirty years and what CNL is adjusting in the decommissioning strategy to prepare better plans for the future. The Nuclear Power Demonstration Nuclear Generating Station (NPDNGS) was constructed in late 1950's and operated from 1962 to 1987 when it was permanently shutdown after exceeding its operational goals. The NPD reactor was the first Canadian nuclear power reactor and it consisted of a single 20 MWe pressurized heavy water reactor located on a single facility site in Rolphton, Ontario. The NPD facility was shutdown to a 'Cold, Dark and Quiet' state and is maintained using an unmanned strategy by managing the site remotely with active fire detection and security surveillance systems, minimal electrical supply and an active ventilation system which is operated periodically to allow for intermittent inspections. The Douglas Point Nuclear Generating Station (DPNGS) was constructed in the early 1960's and operated from 1968 to 1984 when it was permanently shutdown. It consisted of a 200 MW prototype Canada Deuterium Uranium (CANDU) reactor and is embedded on the Bruce Power site near Kincardine, Ontario. The Douglas Point site is maintained in a

Liability problems of international transportation of nuclear material: The Canadian experience

International Nuclear Information System (INIS)

Schwartz, J.A.

1986-01-01

Canadian law in the field of transportation of radioactive materials has largely adopted international standards. Most of the respective laws, however, are as yet untested in court. According to the author it is likely that a broad and liberal interpretation will be given to all of the provisions which entitle injured parties to seek recourse against a transporter who has negligently carried out the duties imposed upon him. (CW) [de

NRC/FEMA operational response procedures for response to a commercial nuclear reactor accident. Revision 1

International Nuclear Information System (INIS)

1985-02-01

Procedures have been developed by the US Nuclear Regulatory Commission (NRC) and the Federal Emergency Management Agency (FEMA) which provide the response teams of both agencies with the steps to be taken in responding to an emergency at a commercial nuclear power plant. The emphasis of these procedures is mainly on the interface between NRC and FEMA at their respective Headquarters and Regional Offices and at the various sites at which such an emergency could occur. Detailed procedures are presented that cover for both agencies, notification schemes and manner of activation, organizations at Headquarters and the site, interface procedures, coordination of onsite and offsite operations, the role of the Senior FEMA Official, and the cooperative efforts of each agency's public information staff

Environmental radionuclide monitoring of Canadian harbours: a decade of analyses in support of due diligence activities by the Royal Canadian Navy.

Science.gov (United States)

Kelly, David G; Mattson, Kristine M; McDonald, Curtis; Nielsen, Kathy S; Weir, Ron D

2014-12-01

The Royal Canadian Navy has conducted a comprehensive programme of safety, security and environmental monitoring since the first visits of nuclear powered and nuclear capable vessels (NPV/NCVs) to Canadian harbours in the late 1960s. The outcomes of baseline monitoring and vessel visit sampling for the period 2003-2012 are described for vessel visits to Halifax (NS), Esquimalt (BC) and Nanoose (BC). Data were obtained by gamma-ray spectroscopy using high purity germanium detectors. No evidence was found for the release of radioactive fission or activation products by NCV/NPVs during the study period, although anthropogenically produced radionuclides were observed as part of the study's baseline monitoring. Background activities of Cs-137 can be observed in sediments from all three locations which are derived from well-documented radioactivity releases. The detection of I-131 in aquatic plants is consistently observed in Halifax at activities as high as 15,000 Bq kg(-1) dry weight. These data are tentatively assigned to the release of medical I-131, followed by bioaccumulation from seawater. I-131 was also observed in aquatic plants samples from Esquimalt (33 Bq kg(-1)) and Nanoose (20 Bq kg(-1)) for a single sampling following the Fukushima Daiichi accident. Crown Copyright © 2014. Published by Elsevier Ltd. All rights reserved.

Owners of nuclear power plants: Percentage ownership of commercial nuclear power plants by utility companies

International Nuclear Information System (INIS)

Wood, R.S.

1987-08-01

The following list indicates percentage ownership of commercial nuclear power plants by utility companies as of June 1, 1987. The list includes all plants licensed to operate, under construction, docked for NRC safety and environmental reviews, or under NRC antitrust review. It does not include those plants announced but not yet under review or those plants formally canceled. In many cases, ownership may be in the process of changing as a result of altered financial conditions, changed power needs, and other reasons. However, this list reflects only those ownership percentages of which the NRC has been formally notified. Part I lists plants alphabetically with their associated applicants/licensees and percentage ownership. Part II lists applicants/licensees alphabetically with their associated plants and percentage ownership. Part I also indicates which plants have received operating licenses (OL's). Footnotes for both parts appear at the end of this document

Mortality study of Canadian military personnel exposed to radiation: atomic test blasts and Chalk River nuclear reactor clean-ups, 1950's

International Nuclear Information System (INIS)

Raman, S.; Dulberg, C.S.; Spasoff, R.A.

1984-08-01

This report describes a historical cohort study of the group of Canadian military personnel exposed to radiation in the 1950s at atomic bomb test blasts in the U.S. and Australia, and at clean-up operations at the Chalk River Nuclear Laboratories. Overall and cause-specific mortality in the exposed group was compared to that of the control cohort of unexposed military personnel, matched on age, service, rank and trade. Analyses indicated no elevation in the exposed cohort, in overall or cause-specific mortality due to diseases associated with radiation. Since this study was restricted to an investigation of mortality, we must stress that we cannot generalize these results or conclusions to current morbidity experienced by the exposed cohort

Outline of safety regulations and administrations for commercial nuclear power plants in Japan

International Nuclear Information System (INIS)

Kinichi Yamamoto

1987-01-01

Outline of safety regulations and administrations for the commercial nuclear power plants in Japan is briefly described. The strict measures for safety assurance are always taken based on the principle of defense-indepth. In the actual procedures of regulatory control, the examinations and inspections shall be performed at each individual step in the stage of applications, and also in the stage of constructions. Thus, those regulatory examinations and inspections shall be performed in detail and carefully, and at the most suitable time; resulting in an effective regulatory control by the Ministry of International Trade and Industry. (author)

Too Few, Too Weak: Conflict of Interest Policies at Canadian Medical Schools

Science.gov (United States)

Shnier, Adrienne; Lexchin, Joel; Mintzes, Barbara; Jutel, Annemarie; Holloway, Kelly

2013-01-01

Introduction The education of medical students should be based on the best clinical information available, rather than on commercial interests. Previous research looking at university-wide conflict of interest (COI) policies used in Canadian medical schools has shown very poor regulation. An analysis of COI policies was undertaken to document the current policy environment in all 17 Canadian medical schools. Methods A web search was used to initially locate COI policies supplemented by additional information from the deans of each medical school. Strength of policies was rated on a scale of 0 to 2 in 12 categories and also on the presence of enforcement measures. For each school, we report scores for all 12 categories, enforcement measures, and summative scores. Results COI policies received summative scores that ranged from 0 to 19, with 0 the lowest possible score obtainable and 24 the maximum. The highest mean scores per category were for disclosure and ghostwriting (0.9) and for gifts and scholarships (0.8). Discussion This study provides the first comprehensive evaluation of all 17 Canadian medical school-specific COI policies. Our results suggest that the COI policy environment at Canadian medical schools is generally permissive. Policy development is a dynamic process. We therefore encourage all Canadian medical schools to develop restrictive COI policies to ensure that their medical students are educated based on the best clinical evidence available, free of industry biases and COI relationships that may influence the future medical thinking and prescribing practices of medical students in Canada once they graduate. PMID:23861928

Childhood leukaemia around Canadian nuclear facilities. Phase 2

International Nuclear Information System (INIS)

Clarke, E.A.; McLaughlin, J.; Anderson, T.W.

1991-06-01

Prompted by findings of increased occurrence of childhood leukaemia in the vicinity of some nuclear facilities in the United Kingdom, this study aimed to investigate whether the frequency of leukaemia among children born to mothers living near nuclear facilities in Ontario differed from the provincial average. The Ontario Cancer Registry was used to identify 1894 children aged 0 to 14 years who died from leukaemia between 1950 and 1987, and 1814 children who were diagnosed with leukaemia between 1964 and 1986. Residence at birth and death was obtained from birth and death certificates. Analyses were performed separately for nuclear research and development facilities; uranium mining, milling and refining facilities; and, nuclear generating stations; and for areas within the same county as the facility and 'nearby' - within a 25-km radius of the facility. Risk estimates were calculated as the ratio of the observed (O) number of events over the expected (E) number. In the vicinity of nuclear research and development facilities the rate of leukaemia was less than expected and within the bound of chance variation. In the areas around the uranium mining, milling and refining facilities and nuclear power plants leukaemia occurred slightly more frequently than expected, but due to small frequencies these differences may have arisen due to chance. Large differences between observed and expected rates were not detected around any of the Ontario facilities. This study was large enough to detect excess risks of the magnitude reported in the United Kingdom, but it was not large enough to discriminate between the observed relative risks and a chance finding. Levels of leukaemia detected near nuclear generating stations indicate the need for further investigation. (20 tabs., 15 figs., 32 refs.)

Nuclear waste management

International Nuclear Information System (INIS)

Wyatt, A.

1978-01-01

The Canadian Nuclear Association has specific views on the following aspects of waste management: a) public information and public participation programs should be encouraged; b) positive political leadership is essential; c) a national plan and policy are necessary; d) all hazardous materials should receive the same care as radioactive wastes; e) power plant construction need not be restricted as long as there is a commitment to nuclear waste management; f) R and D should be funded consistently for nuclear waste management and ancillary topics like alternative fuel cycles and reprocessing. (E.C.B.)

A nuclear reactor for district heating

International Nuclear Information System (INIS)

Bancroft, A.R.; Fenton, N.

1989-07-01

Global energy requirements are expected to double over the next 40 years. In the northern hemisphere, many countries consume in excess of 25 percent of their primary energy supply for building heating. Satisfying this need, within the constraints now being acknowledged for sustainable global development, provides an important opportunity for district heating. Fuel-use flexibility, energy and resource conservation, and reduced atmospheric pollution from acid gases and greenhouse gases, are important features offered by district heating systems. Among the major fuel options, only hydro-electricity and nuclear heat completely avoid emissions of combustion gases. To fill the need for an economical nuclear heat source, Atomic Energy of Canada Limited has designed a 10 MW plant that is suitable as a heat source within a network or as the main supply to large individual users. Producing hot water at temperatures below 100 degrees C, it incorporates a small pool-type reactor based on AECL's successful SLOWPOKE Research Reactor. A 2 MW prototype for the commercial unit is now being tested at the Whiteshell Nuclear Research Establishment in Manitoba. With capital costs of $7 million (Canadian), unit energy costs are projected to be $0.02/kWh for a 10 MW unit operating in a heating grid over a 30-year period. By keeping the reactor power low and the water temperature below 100 degrees C, much of the complexity of the large nuclear power plants can be avoided, thus allowing these small, safe nuclear heating systems to be economically viable

Aging Management Guideline for commercial nuclear power plants: Power and distribution transformers

International Nuclear Information System (INIS)

Toman, G.; Gazdzinski, R.

1994-05-01

This Aging Management Guideline (AMG) provides recommended methods for effective detection and mitigation of age-related degradation mechanisms in power and distribution transformers important to license renewal in commercial nuclear power plants. The intent of this AMG to assist plant maintenance and operations personnel in maximizing the safe, useful life of these components. It also supports the documentation of effective aging management programs required under the License Renewal Rule 10 CFR Part 54. This AMG is presented in a manner which allows personnel responsible for performance analysis and maintenance to compare their plant-specific aging mechanisms (expected or already experienced) and aging management program activities to the more generic results and recommendations presented herein

Response to 'Decades of delay in nuclear waste disposal - a failure to communicate'

Energy Technology Data Exchange (ETDEWEB)

Nagasaki, S. [McMaster Univ., Hamilton, Ontario (Canada)

2014-09-15

In a recent opinion piece on the delay of nuclear waste disposal, Mr. H. Tammemagi asserts that it is important for a nuclear community to include in the Canadian public discourse the presence of natural radiation, comparisons between radioactive and non-radioactive wastes, and nuclear medicine. It is to the first two that I respond to, with the view that the lessons learnt from Japan have merit for addressing the issues in the Canadian context. (author)

Cognitive aspects of sexual functioning: differences between East Asian-Canadian and Euro-Canadian women.

Science.gov (United States)

Morton, Heather; Gorzalka, Boris B

2013-11-01

The purpose of this study was to investigate the sexual beliefs of female undergraduates, as well as the thoughts they experience during sexual experiences. The study aimed to determine potential differences in these variables between East Asian-Canadians and Euro-Canadians, as well as the influence of acculturation on these variables. In addition, the relationships between sexual beliefs, automatic thoughts, and specific aspects of sexual functioning were examined. Euro-Canadian (n = 77) and East Asian-Canadian (n = 123) undergraduate women completed the Sexual Dysfunctional Beliefs Questionnaire, the Sexual Modes Questionnaire, the Female Sexual Function Index, and the Vancouver Index of Acculturation. East Asian women endorsed almost all sexual beliefs assessed in this study more than did Euro-Canadian women, and endorsement of these beliefs was associated with acculturation. In addition, East Asian-Canadian and Euro-Canadian women differed in the frequency of experiencing negative automatic thoughts. Results also revealed associations between difficulties in sexual functioning, and both sexual beliefs and automatic thoughts. Together, these results provide preliminary support for the hypothesis that differences in cognitive aspects of sexuality may underlie the differences in sexual functioning previously observed between these two groups.

History of Fire Events in the U.S. Commercial Nuclear Industry

International Nuclear Information System (INIS)

Bijan Najafi; Joglar-Biloch, Francisco; Kassawara, Robert P.; Khalil, Yehia

2002-01-01

Over the past decade, interest in performance-based fire protection has increased within the nuclear industry. In support of this growing interest, in 1997 the Electric Power Research Institute (EPRI) developed a long-range plan to develop/improve data and tools needed to support Risk-Informed/Performance-Based fire protection. This plan calls for continued improvement in collection and use of information obtained from fire events at nuclear plants. The data collection process has the objectives of improving the insights gained from such data and reducing the uncertainty in fire risk and fire modeling methods in order to make them a more reliable basis for performance based fire protection programs. In keeping with these objectives, EPRI continues to collect, review and analyze fire events in support of the nuclear industry. EPRI collects these records in cooperation with the Nuclear Electric Insurance Limited (NEIL), by compiling public fire event reports and by direct solicitation of U.S. nuclear facilities. EPRI fire data collection project is based on the principle that the understanding of history is one of the cornerstones of improving fire protection technology and practice. Therefore, the goal has been to develop and maintain a comprehensive database of fire events with flexibility to support various aspects of fire protection engineering. With more than 1850 fire records over a period of three decades and 2400 reactor years, this is the most comprehensive database of nuclear power industry fire events in existence today. In general, the frequency of fires in the U.S. commercial nuclear industry remains constant. In few cases, e.g., transient fires and fires in BWR offgas/recombiner systems, where either increasing or decreasing trends are observed, these trends tend to slow after 1980. The key issues in improving quality of the data remain to be consistency of the recording and reporting of fire events and difficulties in collection of records. EPRI has

Dictionaries of Canadian English | Considine | Lexikos

African Journals Online (AJOL)

... its best, reached a high degree of sophistication, there are still major opportunities waiting to be taken. keywords: dictionary, lexicography, canadian english, canadianisms, national dictionaries, canadian french, canadian first nations lan-guages, bilingual dictionaries, regional dictionaries, unfinished diction-ary projects ...

Canadian electricity exports and imports : an energy market assessment

International Nuclear Information System (INIS)

2003-01-01

This energy market assessment (EMA) report focuses on recent trends in exports and imports of Canadian electricity and the associated revenue and pricing. It also outlines major developments in electricity markets in Canada and the United States in the past decade with reference to the implications of electricity trade for both consumers and the power industry. This guide comes at a time of market openings in Alberta and Ontario, and with recent increases in applications to the National Energy Board for electricity exports and international power lines. The first chapter presents an overview of current Canadian federal regulatory regime for electricity exports and restructuring of the electric power industry in Canada and the United States. The second chapter reviews electricity exports and imports from a national perspective. Provincial analyses were presented in the third chapter which also covered international interconnections, export and import trends, export and import pricing, implications for consumer prices, and factors affecting future trade. The final chapter presents some observations on each of these issues. It is noted that exports have fluctuated significantly from year to year due to specific events including the shutdown of nuclear power plants, high gas prices, and the California electricity crisis in 2000-2001. Canadian international electricity trade has continued to yield net revenues of $1 to $2 billion per year due to strong electricity export prices. The relationship between export and import prices varies from province to province. Canadian utilities have emphasized the need for more transmission to the U.S. to foster future trade and improve transmission reliability. refs., tabs., figs

Prevalence of lapine rotavirus, astrovirus, and hepatitis E virus in Canadian domestic rabbit populations.

Science.gov (United States)

Xie, XiaoTing; Bil, Joanna; Shantz, Emily; Hammermueller, Jutta; Nagy, Eva; Turner, Patricia V

2017-09-01