AECL annual report 1996-1997

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-07-01

The 1996/1997 Annual Report of Atomic Energy of Canada Ltd. (AECL) is published and submitted to the Honourable member of parliament, Minister of Natural Resources. Included in this report are messages from marketing, commercial operations, product development, CANDU research, waste management, environmental management, financial review and copies of financial statements.

The AECL study for an intense neutron - generator (technical details)

Energy Technology Data Exchange (ETDEWEB)

Bartholomew, G A; Tunnicliffe, P R

1966-07-01

The AECL study for an intense neutron-generator has been in progress for two years. Recently the scientific and technical details and the conceptual designs were compiled in a report supporting proposals addressed to AECL's Board of Directors for further work. The compilation is being issued in this form to permit further discussion of the technical aspects. However readers are asked to appreciate that it was written primarily for an AECL audience, and specifically that those chapters giving tentative information about costs, the rate of investment and similar items have been omitted or modified, many references have been made to interim internal reports in order to complete the local documentation, but these references do not imply that the reports themselves can be made generally available. (author)

The AECL study for an intense neutron - generator (technical details)

International Nuclear Information System (INIS)

Bartholomew, G.A.; Tunnicliffe, P.R.

1966-01-01

The AECL study for an intense neutron-generator has been in progress for two years. Recently the scientific and technical details and the conceptual designs were compiled in a report supporting proposals addressed to AECL's Board of Directors for further work. The compilation is being issued in this form to permit further discussion of the technical aspects. However readers are asked to appreciate that it was written primarily for an AECL audience, and specifically that those chapters giving tentative information about costs, the rate of investment and similar items have been omitted or modified, many references have been made to interim internal reports in order to complete the local documentation, but these references do not imply that the reports themselves can be made generally available. (author)

On the difference between DRAGON and WIMS-AECL calculations of the coolant void reactivity

International Nuclear Information System (INIS)

Altiparmakov, D.; Roubtsov, D.; Irish, J.D.

2009-01-01

A difference in the shape of the burnup dependence of the coolant void reactivity (CVR) has been observed between DRAGON and WIMS-AECL calculations. This paper discusses the root cause of the difference and assesses the impact on burnup and full-core reactor calculations. A Fortran procedure has been developed to run WIMS-AECL as necessary in order to mimic DRAGON burnup calculations with leakage effects included. The comparison of standard WIMS-AECL results and simulated DRAGON results demonstrated that the difference is due to different definitions of CVR. If the same CVR definition is used, then the results of both WIMS-AECL and DRAGON analyses are essentially indistinguishable. The discrepancies in the fuel composition and cell-averaged two-group cross sections that are due to differences in WIMS-AECL and DRAGON leakage treatments are insignificant. (author)

AECL's reliability and maintainability program

International Nuclear Information System (INIS)

Wolfe, W.A.; Nieuwhof, G.W.E.

1976-05-01

AECL's reliability and maintainability program for nuclear generating stations is described. How the various resources of the company are organized to design and construct stations that operate reliably and safely is shown. Reliability and maintainability includes not only special mathematically oriented techniques, but also the technical skills and organizational abilities of the company. (author)

The AECL study for an intense neutron - generator (technical details)

Energy Technology Data Exchange (ETDEWEB)

Bartholomew, G.A.; Tunnicliffe, P.R

1966-07-01

The AECL study for an intense neutron-generator has been in progress for two years. Recently the scientific and technical details and the conceptual designs were compiled in a report supporting proposals addressed to AECL's Board of Directors for further work. The compilation is being issued in this form to permit further discussion of the technical aspects. However readers are asked to appreciate that it was written primarily for an AECL audience, and specifically that those chapters giving tentative information about costs, the rate of investment and similar items have been omitted or modified, many references have been made to interim internal reports in order to complete the local documentation, but these references do not imply that the reports themselves can be made generally available. (author)

The development, qualification and availability of AECL analytical, scientific and design codes

International Nuclear Information System (INIS)

Kupferschmidt, W.C.H.; Fehrenbach, P.J.; Wolgemuth, G.A.; McDonald, B.H.; Snell, V.G.

2001-01-01

Over the past several years, AECL has embarked on a comprehensive program to develop, qualify and support its key safety and licensing codes, and to make executable versions of these codes available to the international nuclear community. To this end, we have instituted a company-wide Software Quality Assurance (SQA) Program for Analytical, Scientific and Design Computer Programs to ensure that the design, development, maintenance, modification, procurement and use of computer codes within AECL is consistent with today's quality assurance standards. In addition, we have established a comprehensive Code Validation Project (CVP) with the goal of qualifying AECL's 'front-line' safety and licensing codes by 2001 December. The outcome of this initiative will be qualified codes, which are properly verified and validated for the expected range of applications, with associated statements of accuracy and uncertainty for each application. The code qualification program, based on the CSA N286.7 standard, is intended to ensure (1) that errors are not introduced into safety analyses because of deficiencies in the software, (2) that an auditable documentation base is assembled that demonstrates to the regulator that the codes are of acceptable quality, and (3) that these codes are formally qualified for their intended applications. Because AECL and the Canadian nuclear utilities (i.e., Ontario Power Generation, Bruce Power, Hydro Quebec and New Brunswick Power) generally use the same safety and licensing codes, the nuclear industry in Canada has agreed to work cooperatively together towards the development, qualification and maintenance of a common set of analysis tools, referred to as the Industry Standard Toolset (IST). This paper provides an overview of the AECL Software Quality Assurance Program and the Code Validation Project, and their associated linkages to the Canadian nuclear community's Industry Standard Toolset initiative to cooperatively qualify and support commonly

The year 2000 (Y2k) Programme at AECL

International Nuclear Information System (INIS)

Pauksens, J.; Jung, D.

1998-01-01

In the nuclear industry we make, in total, very extensive use of digital computers and equipment. While use of dates in our application may not be quite so extensive as in other businesses such as banking or insurance, dates are nonetheless employed, and are important in a variety of applications. Furthermore, date-related problems can sometimes propagate into overall system failures or computer crashes. Digital system or digital infrastructure failure can have serious potential consequences in a power plant, utility, or engineering design office. This in turn can have potential impact on public safety or the reliability of power production and delivery of electrical power to the public. A concerted effort is needed, and is underway by nuclear design organizations, and the nuclear utilities in order to identify and fix or avoid the problems in the short time that remains between now and the Year 2000. AECL have a substantial Year 2000 programme underway, addressing both the infrastructure systems at AECL, and AECL's products and services. High priority is placed, in the programme, on assisting AECL's customers with the Year 2000 issue. The programme, and some of the lesson learned to date, are described in this paper. The relationship to equipment vendors' and customers' Year 2000 programs is explained, and the importance of Year 2000 programmes conducted by the customers, to address systems and equipment which are under their control, is highlighted. (authors)

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

AECL experience in fuel channel inspection

Energy Technology Data Exchange (ETDEWEB)

Van Drunen, G. [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada); Gunn, R. [Atomic Energy of Canada Limited, Mississauga, Ontario (Canada); Mayo, W.R. [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada); Scott, D.A. [Atomic Energy of Canada Limited, Mississauga, Ontario (Canada)

1999-06-01

Inspection of CANDU fuel channels (FC) is performed to ensure safe and economic reactor operation. CANDU reactor FCs have features that make them a unique non-destructive testing (NDT) challenge. The thin, 4 mm pressure-tube wall means flaws down to about 0.1 mm deep must be reliably detected and characterized. This is one to two orders of magnitude smaller than is usually considered of significant concern for steel piping and pressure vessels. A second unique feature is that inspection sensors must operate in the reactor core--often within 20 cm of highly radioactive fuel. Work on inspection of CANDU reactor FCs at AECL dates back over three decades. In that time, AECL staff have provided equipment and conducted or supervised in-service inspections in about 250 FCs, in addition to over 8000 pre-service FCs. These inspections took place at every existing CANDU reactor except those in India and Romania. Early FC inspections focussed on measurement of changes in dimensions (gauging) resulting from exposure to a combination of neutrons, stress and elevated temperature. Expansion of inspection activities to include volumetric inspection (for flaws) started in the mid-1970s with the discovery of delayed hydride cracking in Pickering 3 and 4 rolled joints. Recognition of other types of flaw mechanisms in the 1980s led to further expansion in both pre-service and in-service inspections. These growing requirements, to meet regulatory as well as economic needs, led to the development of a wide spectrum of inspection technology that now includes tests for hydrogen concentration, structural integrity of core components, flaws, and dimensional change. This paper reviews current CANDU reactor FC inspection requirements. The equipment and techniques developed to satisfy these requirements are also described. The paper concludes with a discussion of work in progress in AECL aimed at providing state-of-the-art FC inspection services. (author)

DEMONSTRATION SOLIDIFICATION TESTS CONDUCTED ON RADIOACTIVELY CONTAMINATED ORGANIC LIQUIDS AT THE AECL WHITESHELL LABORATORIES

International Nuclear Information System (INIS)

Ryz, R. A.; Brunkow, W. G.; Govers, R.; Campbell, D.; Krause, D.

2002-01-01

The AECL, Whiteshell Laboratory (WL) near Pinawa Manitoba, Canada, was established in the early 1960's to carry out AECL research and development activities for higher temperature versions of the CANDU(reg s ign) reactor. The initial focus of the research program was the Whiteshell Reactor-1 (WR-1) Organic Cooled Reactor (OCR) that began operation in 1965. The OCR program was discontinued in the early 1970's in favor of the successful heavy-water-cooled CANDU system. WR-1 continued to operate until 1985 in support of AECL nuclear research programs. A consequence of the Federal government's recent program review process was AECL's business decision to discontinue research programs and operations at the Whiteshell Laboratories and to consolidate its' activities at the Chalk River Laboratories. As a result, AECL received government concurrence in 1998 to proceed to plan actions to achieve closure of WL. The planning actions now in progress address the need to safely and effectively transition the WL site from an operational state, in support of AECL's business, to a shutdown and decommissioned state that meets the regulatory requirements for a licensed nuclear site. The decommissioning program that will be required at WL is unique within AECL and Canada since it will need to address the entire research site rather than individual facilities declared redundant. Accordingly, the site nuclear facilities are being systematically placed in a safe shutdown state and planning for the decommissioning work to place the facilities in a secure monitoring and surveillance state is in progress. One aspect of the shutdown activities is to deal with the legacy of radioactively contaminated organic liquid wastes. Use of a polymer powder to solidify these organic wastes was identified as one possibility for improved interim storage of this material pending final disposition

Evaluation of AECL catalysts for hydrogen fuel-cell applications. Paper no. IGEC-1-073

International Nuclear Information System (INIS)

Li, J.; Suppiah, S.; Li, H.; Kutchcoskie, K.J.; Strikwerda, S.

2005-01-01

AECL has been engaged in the promotion of the nuclear-hydrogen economy, which envisions that hydrogen fuel cells will generate power using hydrogen as fuel produced by nuclear energy. Since AECL's catalysts developed for the production, upgrading and detritiation of heavy water are very similar to commercial fuel-cell catalysts, a program was initiated to evaluate AECL catalysts for fuel-cell applications. As a first step in this effort, a half-cell test facility was set up to characterize the performance of catalysts for hydrogen fuel cells. This paper outlines the results obtained from cathodic reduction of oxygen in a 0.5 M sulphuric acid solution on a rotating disc electrode at 65 o C. The performance of the catalysts was characterized using standard electrochemical methods including cyclic voltammetry, Voltammogram/Tafel plots and short-term stability plots. Several monometallic Pt and Pt-based bimetallic catalysts were tested and compared with a commercially available catalyst for fuel-cell applications. AECL's monometallic Pt catalysts showed comparable or better activities than commercial catalysts with similar Pt loading. An AECL Pt-based bimetallic catalyst has shown superior performance to a monometallic Pt catalyst with similar Pt loading. Evaluation of various catalyst formulations is ongoing on the half-cell facility at AECL. Further investigation of promising catalysts identified from half-cell test is also being carried out in single fuel cell on test stations under normal fuel-cell operating conditions. (author)

AECL's support to operating plants world wide

International Nuclear Information System (INIS)

Azeez, S.; Kakaria, B.K.; Hinchley, E.M.

1998-01-01

Through their operating records, CANDU reactors have established themselves as a successful and cost-effective source of electricity in Canada and abroad. They have proven to be safe, reliable and economical. A variety of factors have contributed to the enviable CANDU record, such as a sound design based on proven principles supported by effective development programs, along with dedicated plant owners committed to excellence in safely maintaining and operating their plants. Atomic Energy of Canada Limited (AECL), the CANDU designer, has continuously maintained a close relationship with owners/operators of the plants in Canada, Argentina, Romania and South Korea. AECL and the plant operators have all benefited from this strengthening relationship by sharing experience and information. CANDU plant operators have been required to respond decisively to the economic realities of downward cost pressures and deregulation. Operating, Maintenance and Administration (OM and A) costs are being given a new focus as plant owners review each cost element to improve the economic returns from their investments. Amongst the three main OM and A constituents, plant maintenance costs are the most variable and have the largest influence on effective plant operations. The correlation between effective plant maintenance and high capacity factors shows clearly the importance of proactive maintenance planning to reduce the frequency and duration of forced plant outages and their negative impacts on plant economics. This paper describes the management processes and organizational structures m AECL that support plant operations and maintenance in operating CANDU plants with cost effective products and services. (author)

A bibliography of AECL publications on reactor safety

International Nuclear Information System (INIS)

Hawley, N.J.

1979-12-01

AECL Publications on Reactor Safety in CANDU Reactors are listed in this bibliography. The listing is chronological and the accompanying index is by subject. The bibliography will be brought up to date annually. (auth)

A bibliography of AECL publications on environmental research

International Nuclear Information System (INIS)

Hawley, N.J.

1978-12-01

Publications in the open literature on environmental research performed by AECL personnel are listed chronologically with the first entry dated 1951. It is intended that the bibliography should be brought up to date yearly. (author)

The Y2K program for scientific-analysis computer programs at AECL

International Nuclear Information System (INIS)

Popovic, J.; Gaver, C.; Chapman, D.

1999-01-01

The evaluation of scientific-analysis computer programs for year-2000 compliance is part of AECL' s year-2000 (Y2K) initiative, which addresses both the infrastructure systems at AECL and AECL's products and services. This paper describes the Y2K-compliance program for scientific-analysis computer codes. This program involves the integrated evaluation of the computer hardware, middleware, and third-party software in addition to the scientific codes developed in-house. The project involves several steps: the assessment of the scientific computer programs for Y2K compliance, performing any required corrective actions, porting the programs to Y2K-compliant platforms, and verification of the programs after porting. Some programs or program versions, deemed no longer required in the year 2000 and beyond, will be retired and archived. (author)

The Y2K program for scientific-analysis computer programs at AECL

International Nuclear Information System (INIS)

Popovic, J.; Gaver, C.; Chapman, D.

1999-01-01

The evaluation of scientific analysis computer programs for year-2000 compliance is part of AECL's year-2000 (Y2K) initiative, which addresses both the infrastructure systems at AECL and AECL's products and services. This paper describes the Y2K-compliance program for scientific-analysis computer codes. This program involves the integrated evaluation of the computer hardware, middleware, and third-party software in addition to the scientific codes developed in-house. The project involves several steps: the assessment of the scientific computer programs for Y2K compliance, performing any required corrective actions, porting the programs to Y2K-compliant platforms, and verification of the programs after porting. Some programs or program versions, deemed no longer required in the year 2000 and beyond, will be retired and archived. (author)

AECL's participation in the commissioning of Point Lepreau generating station unit 1

International Nuclear Information System (INIS)

Chawla, S.; Singh, K.; Yerramilli, S.

1983-05-01

Support from Atomic Energy of Canada Ltd. (AECL) to Point Lepreau during the commissioning program has been in the form of: seconded staff for commissioning program management, preparation of commissioning procedures, and hands-on commissioning of several systems; analysis of test results; engineering service for problem solving and modifications; design engineering for changes and additions; procurement of urgently-needed parts and materials; technological advice; review of operational limits; interpretation of design manuals and assistance with and preparation of submissions to regulatory authorities; and development of equipment and procedures for inspection and repairs. This, together with AECL's experience in the commissioning of other 600 MWe stations, Douglas Point and Ontario Hydro stations, provides AECL with a wide range of expertise for providing operating station support services for CANDU stations

Final report of the AECL/SKB Cigar Lake analog study. AECL research No. AECL-10851

Energy Technology Data Exchange (ETDEWEB)

Cramer, J J; Smellie, J A.T. [eds.

1994-07-15

AECL has conducted natural analog studies on the Cigar Lake uranium deposit in northern Saskatchewan since 1984 as part of the Canadian Nuclear Fuel Waste Management Program. This report provides background information and summarizes the results of the study, emphasizing the analog aspects and the implications of modelling activities related to the performance assessment of disposal concepts for nuclear fuel wastes developed in both Canada and Sweden. The study was undertaken to obtain an understanding of the process involved in, and the effects of, steady-state water-rock interaction and trace-element migration in and around the deposit, including paleo-migration processes since the deposit was formed. To achieve these objectives, databases and models were produced to evaluate the equilibrium thermodynamic codes and databases; the role of colloids, organics, and microbes in transport processes for radionuclides; and the stability of UO2 and the influence of radiolysis on UO2 dissolution and radionuclide migration.

Compendium of the data used with the SYVAC3-CC3 system model. AECL research No. AECL-11013

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-12-31

AECL is evaluating a concept for disposing of nuclear fuel waste from CANDU reactors deep in plutonic rock of the Canadian Shield. As part of this evaluation, models of the physical, chemical, geological, and biological processes that could occur in a sealed disposal vault designed to limit transport of contaminants to the accessible environment were developed. The mathematical models of the transport of radionuclides and toxic chemicals from nuclear fuel waste are incorporated into a computer model named the Systems Variability Analysis Code, Generation 3, and Canadian Concept Model, Generation 3 (SYVAC3-CC3). The report presents the data in the master database used by SYVAC3-CC3 for the postclosure assessment of deep geological disposal, derived from a major program of laboratory and field studies conducted by AECL Research over the past 15 years. The data represents characteristics of a hypothetical vault, certain geologic characteristics of the Whiteshell Research Area, and a general surface environment with a human population living a rural lifestyle on a portion of the Canadian Shield in central Canada.

AECL strategy for surface-based investigations of potential disposal sites and the development of a geosphere model for a site

Energy Technology Data Exchange (ETDEWEB)

Whitaker, S H; Brown, A; Davison, C C; Gascoyne, M; Lodha, G S; Stevenson, D R; Thorne, G A; Tomsons, D [AECL Research, Whiteshell Labs., Pinawa, MB (Canada)

1994-05-01

The objective of this report is to summarize AECL`s strategy for surface-based geotechnical site investigations used in screening and evaluating candidate areas and candidate sites for a nuclear fuel waste repository and for the development of geosphere models of sites. The report is one of several prepared by national nuclear fuel waste management programs for the Swedish Nuclear Fuel and Waste Management Co. (SKB) to provide international background on site investigations for SKB`s R and D programme on siting.The scope of the report is limited to surface-based investigations of the geosphere, those done at surface or in boreholes drilled from surface. The report discusses AECL`s investigation strategy and the methods proposed for use in surface-based reconnaissance and detailed site investigations at potential repository sites. Site investigations done for AECL`s Underground Research Laboratory are used to illustrate the approach. The report also discusses AECL`s strategy for developing conceptual and mathematical models of geological conditions at sites and the use of these models in developing a model (Geosphere Model) for use in assessing the performance of the disposal system after a repository is closed. Models based on the site data obtained at the URL are used to illustrate the approach. Finally, the report summarizes the lessons learned from AECL`s R and D program on site investigations and mentions some recent developments in the R and D program. 120 refs, 33 figs, 7 tabs.

AECL's advanced CANDU reactor - the ACR

International Nuclear Information System (INIS)

Alizadeh, Ala; Allsop, Peter; Hedges, Ken; Hopwood, Jerry; Yu, Stephen

2003-01-01

The ACR, the next generation CANDU design, represents the next step in development of the CANDU family of designs. AECL has achieved significant incremental improvements to the mid-size CANDU 6 nuclear power plant through successive projects, both in design and in project delivery. Building on this knowledge base, AECL is continuing to adapt the CANDU design to develop the ACR. This paper summarizes the ACR design features, which include major improvements in economics, inherent safety characteristics, performance and construction methods. Aimed at producing electrical power at a capital cost significantly less than that of the current reactor designs, the ACR is an evolutionary design based on the very successful CANDU 6 reactor. The new ACR product is specifically designed to produce power at a cost competitive with other forms of power generation while achieving short construction times, improved safety, international licensability, high investor returns, and low investor risk. It achieves these targets by taking advantage of the latest advances in both pressure-tube and pressure-vessel reactor technologies and experience. The flexibility and development potential of the fuel channel approach also enables designs to be developed that address priorities identified in international long-term specification programs such as the US Department of Energy (DOE) sponsored Generation IV program and IAEA hosted INPRO program. ACR-700 can be built in 36 months with a 48 month project duration, and deliver a lifetime capacity factor in excess of 90%. Overall, the ACR design represents a balance of proven design basis and innovations to give step improvements in safety, reliability and economics. The ACR development program, now well into the detail design stage, includes parallel formal licensing in the USA and Canada. Based on the status of the ACR design and AECL's on-going experience delivering reactor projects on-time and on-budget, the first ACR could be in service by

AECL hot-cell facilities and post-irradiation examination services

International Nuclear Information System (INIS)

Schankula, M.H.; Plaice, E.L.; Woodworth, L.G.

1998-04-01

This paper presents an overview of the post-irradiation examination (PIE) services available at AECL's hot-cell facilities (HCF). The HCFs are used primarily to provide PIE support for operating CANDU power reactors in Canada and abroad, and for the examination of experimental fuel bundles and core components irradiated in research reactors at the Chalk River Laboratories (CRL) and off-shore. A variety of examinations and analyses are performed ranging from non-destructive visual and dimensional inspections to detailed optical and scanning electron microscopic examinations. Several hot cells are dedicated to mechanical property testing of structural materials and to determine the fitness-for-service of reactor core components. Facility upgrades and the development of innovative examination techniques continue to improve AECL's PIE capabilities. (author)

AECL hot-cell facilities and post-irradiation examination services

International Nuclear Information System (INIS)

Schankula, M.H.; Plaice, E.L.; Woodworth, L.G.

1995-01-01

This paper presents an overview of the post-irradiation examination (PIE) services available at AECL's hot-cell facilities (HCF). The HCFs are used primarily to provide PIE support for operating CANDU power reactors in Canada and abroad, and for the examination of experimental fuel bundles and core components irradiated in research reactors at the Chalk River Laboratories (CRL) and off-shore. A variety of examinations and analysis are performed ranging from non-destructive visual and dimensional inspections to detailed optical and scanning electron microscopic examinations. Several hot cells are dedicated to mechanical property testing of structural materials and to determine the fitness-for-service of reactor core components. Facility upgrades and the development of innovative examination techniques continue to improve AECL's PIE capabilities. (author)

The AECL operator companion

International Nuclear Information System (INIS)

Lupton, L.R.; Anderson, L.L.; Basso, R.A.J.

1989-11-01

As CANDU plants become more complex, and are operated under tighter constraints and for longer periods between outages, plant operations staff will have to absorb more information to correctly and rapidly respond to upsets. A development program is underway at AECL to use expert systems and interactive media tools to assist operations staff of existing and future CANDU plants. The complete system for plant information access and display, on-line advice and diagnosis, and interactive operating procedures is called the Operator Companion. A prototype, consisting of operator consoles, expert systems and simulation modules in a distributed architecture, is currently being developed to demonstrate the concepts of the Operator Companion

Interface code between WIMS-AECL and RFSP-IST for coupling computing

International Nuclear Information System (INIS)

Xu Liangwang; Liu Yu; Jia Baoshan

2007-01-01

A code based on the protocols of Telnet and FTP is developed with C++ for coupling computing between WIMS-AECL and RFSP-IST. the input document of WIMS-AECL and RFSP-ISP cna be generated automatically and be submitted to server, the output document will be downloaded by the end of computing. the function of analyzing standard output document is also included in this code. After simple updating, this code can meet the requirement of other code using input document, e.g. CATHENA. A pilot study of the relation between void fraction and reactivity in TACR, some valuable conclusions has been achieved. (authors)

Follow-up of AECL employees involved in the decontamination of NRU in 1958

International Nuclear Information System (INIS)

Werner, M.M.; Myers, D.K.; Morrison, D.P.

1982-09-01

In May 1958 the NRU reactor hall was badly contaminated by a damaged fuel rod that broke apart during its removal from the reactor. Radioactive fission products were spread around the reactor hall and into adjacent areas when a piece of the fuel rod fell into the maintenance pit and burned. AECL staff and others completed the decontamination in 2 1/2 months. This paper reports the results of a follow-up study of the AECL participants. No statistically significant increases in deaths from cancer or other diseases were found in this group

Validation of WIMS-AECL/(MULTICELL)/RFSP system by the results of phase-B test at Wolsung-II unit

Energy Technology Data Exchange (ETDEWEB)

Hong, In Seob; Min, Byung Joo; Suk, Ho Chun [Korea Atomic Energy Research Institute, Taejon (Korea)

1999-03-01

The object of this study is the validation of WIMS-AECL lattice code which has been proposed for the substitution of POWDERPUFS-V(PPV) code. For the validation of this code, WIMS-AECL/(MULTICELL)/RFSP (lattice calculation/(incremental cross section calculation)/core calculation) code system has been used for the Post-Simulation of Phase-B physics Test at Wolsung-II unit. This code system had been used for the Wolsong-I and Point Lepraeu reactors, but after a few modifications of WIMS-AECL input values for Wolsong-II, the results of WIMS-AECL/RFSP code calculations are much improved to those of the old ones. Most of the results show good estimation except moderator temperature coefficient test. And the verification of this result must be done, which is one of the further work. 6 figs., 15 tabs. (Author)

AECL's mixed waste management program

International Nuclear Information System (INIS)

Peori, R.; Hulley, V.

2006-01-01

Every nuclear facility has it, they wish that they didn't but they have generated and do possess m ixed waste , and until now there has been no permanent disposition option; it has been for the most been simply maintained in interim storage. The nuclear industry has been responsibly developing permanent solutions for solid radioactive waste for over fifty years and for non-radioactive, chemically hazardous waste, for the last twenty years. Mixed waste (radioactive and chemically hazardous waste) however, because of its special, duo-hazard nature, has been a continuing challenge. The Hazardous Waste and Segregation Program (HW and SP) at AECL's CRL has, over the past ten years, been developing solutions to deal with their own in-house mixed waste and, as a result, have developed solutions that they would like to share with other generators within the nuclear industry. The main aim of this paper is to document and describe the early development of the solutions for both aqueous and organic liquid wastes and to advertise to other generators of this waste type how these solutions can be implemented to solve their mixed waste problems. Atomic Energy of Canada Limited (AECL) and in particular, CRL has been satisfactorily disposing of mixed waste for the last seven years. CRL has developed a program that not only disposes of mixed waste, but offers a full service mixed waste management program to customers within Canada (that could eventually include U.S. sites as well) that has developed the experience and expertise to evaluate and optimize current practices, dispose of legacy inventories, and set up an efficient segregation system to reduce and effectively manage, both the volumes and expense of, the ongoing generation of mixed waste for all generators of mixed waste. (author)

AECL's concept for the disposal of nuclear fuel waste and the importance of its implementation

International Nuclear Information System (INIS)

Allan, C.J.

1993-07-01

Since 1978, Canada has been investigating a concept for permanently dealing with the nuclear fuel waste from Canadian CANDU (Canada Deuterium Uranium) nuclear generating stations. The concept is based on disposing of the waste in a vault excavated 500 to 1000 m deep in intrusive igneous rock of the Canadian Shield. AECL Research will soon be submitting an environmental impact statement (EIS) on the concept for review by a Panel through the federal environmental assessment and review process (EARP). In accordance with AECL Research's mandate and in keeping with the detailed requirements of the review Panel, AECL Research has conducted extensive studies on a wide variety of technical and socio-economic issues associated with the concept. If the concept is accepted, we can and should continue our responsible approach and take the next steps towards constructing a disposal facility for Canada's used nuclear fuel waste

Microbial analysis of the buffer/container experiment at AECL's underground research laboratory

International Nuclear Information System (INIS)

Stroes-Gascoyne, S.

1996-07-01

The Buffer/Container Experiment (BCE) was carried out at AECL's Underground Research Laboratory (URL) for 2.5 years to examine the in situ performance of compacted buffer material in a single emplacement borehole under vault-relevant conditions. During decommissioning of this experiment, numerous samples were taken for microbial analysis to determine if the naturally present microbial population in buffer material survived the conditions (i.e., compaction, heat and desiccation) in the BCE and to determine which group(s) of microorganisms would be dominant in such a simulated vault environment. Such knowledge will be very useful in assessing the potential effects of microbial activity on the concept for deep disposal of Canada's nuclear fuel waste, proposed by AECL. 46 refs., 31 tabs., 35 figs

Thermalhydraulic analyses of AECL's spent fuel dry storage systems

International Nuclear Information System (INIS)

Moffett, R.; Sabourin, G.

1995-01-01

This paper presents the validation of one- and three-dimensional thermalhydraulic models to be used to evaluate the thermal performance of AECL's MACSTOR and CANSTOR spent fuel dry storage modules. For this purpose, we compared analytical results to results of experiments conducted at AECL's Whiteshell Laboratories where mockups of the MACSTOR module and of a CANDU fuel storage basket were tested. The paper shows improvements to a simple one-dimensional model of the MACSTOR mock-up used previously. The replacement of constant heat transfer coefficients by free convection correlations, the addition of a storage cylinder model, and the addition of a radiation heat transfer model improved the predictions of concrete and storage cylinder temperatures. The paper also presents a new three-dimensional model for flow and heat transfer in the MACSTOR mock-up developed using CFDS-FLOW3D and -RAD3D computer programs. CFDS-FLOW3D code can estimate loss coefficients in complex geometry to an accuracy better than standard engineering correlations. The flow and temperature fields predicted using CFDS-FLOW3D are consistent with the measurements made during MACSTOR mock-up experiments (author). 5 refs., 4 tabs., 9 figs

Experience with remediating radiostrontium-contaminated ground water and surface water with versions of AECL's CHEMIC process

International Nuclear Information System (INIS)

Vijayan, S.

2006-01-01

Numerous approaches have been developed for the remediation of radiostrontium ( 90 Sr) contaminated ground water and surface water. Several strontium-removal technologies have been assessed and applied at AECL's (Atomic Energy of Canada Limited) Chalk River Laboratories. These include simple ion exchange (based on non-selective natural zeolites or selective synthetic inorganic media), and precipitation and filtration with or without ion exchange as a final polishing step. AECL's CHEMIC process is based on precipitation-microfiltration and ion-exchange steps. This paper presents data related to radiostrontium removal performance and other operational experiences including troubleshooting with two round-the-clock, pilot-scale water remediation plants based on AECL's CHEMIC process at the Chalk River Laboratories site. These plants began operation in the early 1990s. Through optimization of process chemistry and operation, high values for system capability and system availability factors, and low concentrations of 90 Sr in the discharge water approaching drinking water standard can be achieved. (author)

Validation of MCNP and WIMS-AECL/DRAGON/RFSP for ACR-1000 applications

International Nuclear Information System (INIS)

Bromley, Blair P.; Adams, Fred P.; Zeller, Michael B.; Watts, David G.; Shukhman, Boris V.; Pencer, Jeremy

2008-01-01

This paper gives a summary of the validation of the reactor physics codes WIMS-AECL, DRAGON, RFSP and MCNP5, which are being used in the design, operation, and safety analysis of the ACR-1000 R . The standards and guidelines being followed for code validation of the suite are established in CSA Standard N286.7-99 and ANS Standard ANS-19.3-2005. These codes are being validated for the calculation of key output parameters associated with various reactor physics phenomena of importance during normal operations and postulated accident conditions in an ACR-1000 reactor. Experimental data from a variety of sources are being used for validation. The bulk of the validation data is from critical experiments in the ZED-2 research reactor with ACR-type lattices. To supplement and complement ZED-2 data, qualified and applicable data are being taken from other power and research reactors, such as existing CANDU R units, FUGEN, NRU and SPERT research reactors, and the DCA critical facility. MCNP simulations of the ACR-1000 are also being used for validating WIMS-AECL/ DRAGON/RFSP, which involves extending the validation results for MCNP through the assistance of TSUNAMI analyses. Code validation against commissioning data in the first-build ACR-1000 will be confirmatory. The code validation is establishing the biases and uncertainties in the calculations of the WIMS-AECL/DRAGON/RFSP suite for the evaluation of various key parameters of importance in the reactor physics analysis of the ACR-1000. (authors)

Status and Plans for work on pressure tube creep at AECL

International Nuclear Information System (INIS)

Bickel, Grant A.

2013-01-01

AECL research goals: • Develop empirical models to: – regress out operating conditions/extrinsic factors – rank relative strain behavior of measured in-service pressure tubes; • Correlate the ranked strains to manufacturing variables and the microstructure to: – Develop mechanistic insights – Optimize manufacturing/microstructure for improved pressure tube performance

AECL's advanced code program

Energy Technology Data Exchange (ETDEWEB)

McGee, G.; Ball, J. [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada)

2012-07-01

This paper discusses the advanced code project at AECL.Current suite of Analytical, Scientific and Design (ASD) computer codes in use by Canadian Nuclear Power Industry is mostly developed 20 or more years ago. It is increasingly difficult to develop and maintain. It consist of many independent tools and integrated analysis is difficult, time consuming and error-prone. The objectives of this project is to demonstrate that nuclear facility systems, structures and components meet their design objectives in terms of function, cost, and safety; demonstrate that the nuclear facility meets licensing requirements in terms of consequences of off-normal events; dose to public, workers, impact on environment and demonstrate that the nuclear facility meets operational requirements with respect to on-power fuelling and outage management.

Controlled drill ampersand blast excavation at AECL's Underground Research Laboratory

International Nuclear Information System (INIS)

Kuzyk, G.W.; Onagi, D.P.; Thompson, P.M.

1996-01-01

A controlled drill and blast method has been developed and used to excavate the Underground Research Laboratory, a geotechnical facility constructed by Atomic Energy of Canada Limited (AECL) in crystalline rock. It has been demonstrated that the method can effectively reduce the excavation disturbed zone (EDZ) and is suitable for the construction of a used fuel disposal vault in the plutonic rock of the Canadian Shield

AECL strategy for surface-based investigations of potential disposal sites and the development of a geosphere model for a site

International Nuclear Information System (INIS)

Whitaker, S.H.; Brown, A.; Davison, C.C.; Gascoyne, M.; Lodha, G.S.; Stevenson, D.R.; Thorne, G.A.; Tomsons, D.

1994-05-01

The objective of this report is to summarize AECL's strategy for surface-based geotechnical site investigations used in screening and evaluating candidate areas and candidate sites for a nuclear fuel waste repository and for the development of geosphere models of sites. The report is one of several prepared by national nuclear fuel waste management programs for the Swedish Nuclear Fuel and Waste Management Co. (SKB) to provide international background on site investigations for SKB's R and D programme on siting.The scope of the report is limited to surface-based investigations of the geosphere, those done at surface or in boreholes drilled from surface. The report discusses AECL's investigation strategy and the methods proposed for use in surface-based reconnaissance and detailed site investigations at potential repository sites. Site investigations done for AECL's Underground Research Laboratory are used to illustrate the approach. The report also discusses AECL's strategy for developing conceptual and mathematical models of geological conditions at sites and the use of these models in developing a model (Geosphere Model) for use in assessing the performance of the disposal system after a repository is closed. Models based on the site data obtained at the URL are used to illustrate the approach. Finally, the report summarizes the lessons learned from AECL's R and D program on site investigations and mentions some recent developments in the R and D program. 120 refs, 33 figs, 7 tabs

Co-operative projects with AECL in the fields of hydrogeology and geochemistry

International Nuclear Information System (INIS)

1985-01-01

The report covers collaborative study with Atomic Energy of Canada Limited on geological aspects of waste disposal in crystalline rocks. A field test of the sinusoidal hydraulic pressure pulse method was carried out at the URL site to try to define hydraulic properties of major horizontal fractures. The trials were generally successful and observable sine and square wave signals were transmitted. Owing to the limited scale of the programme, and some equipment problems, the results proved difficult to interpret, although the speed and flexibility of the method was demonstrated. A second aspect of collaboration was to be the field comparison of the AECL and NERC/BGS borehole geochemical probes. In the event, the AECL probe development programme was curtailed and a Swedish design selected for purchase. Effort thus switched to technical comparison of the SGAB probe with the NERC/BGS design. Since both are still at various development points the collaboration was limited to technical exchange. The results are presented. (author)

The use of HANDIDET{reg_sign} non-electric detonator assemblies to reduce blast-induced overpressure at AECL`s Underground Research Laboratory

Energy Technology Data Exchange (ETDEWEB)

Onagi, D.P.; Keith, S.G.; Kuzyk, G.W. [AECL, Pinawa, Manitoba (Canada). Underground Research Lab.; Proudfoot, D.F. [ICI Explosives Canada, North Delta, British Columbia (Canada)

1996-12-01

A number of aspects of the Canadian concept for nuclear fuel waste disposal are being assessed by Atomic Energy of Canada Limited (AECL) in a series of experiments at its Underground Research Laboratory (URL) near Lac du Bonnet, Manitoba, Canada. One of the major objectives of the work being carried out at the URL is to develop and evaluate the methods and technology to ensure safe, permanent disposal of Canada`s nuclear fuel waste. In 1994, AECL excavated access tunnels and a laboratory room for the Quarried Block Fracture Migration Experiment (QBFME) at the 240 Level of the URL. This facility will be used to study the transport of radionuclides in natural fractures in quarried blocks of granite under in-situ groundwater conditions. The experiment is being carried out under a cooperative agreement with the Japan Atomic Energy Research Institute. The excavation of the QBFME access tunnels and laboratory was carried out using controlled blasting techniques that minimized blast-induced overpressure which could have damaged or interrupted other ongoing experiments in the vicinity. The majority of the blasts used conventional long delay non-electric detonators but a number of blasts were carried out using HANDIDET 250/6000 non-electric long delay detonator assemblies and HTD{reg_sign} non-electric short delay trunkline detonator assemblies. The tunnel and laboratory excavation was monitored to determine the levels of blast-induced overpressure. This paper describes the blasting and monitoring results of the blasts using HANDIDET non-electric detonator assemblies and the effectiveness of these detonators in reducing blast-induced overpressure.

Comparison of Wims-Aecl / Dragon / RFSP and MCNP results with Zed-2 measurements for control device worth and reactor kinetics - 037

International Nuclear Information System (INIS)

Pencer, J.; Choy Wong, F.; Bromley, B.P.; Atfield, J.; Zeller, M.

2010-01-01

This paper summarizes comparisons between MCNP5 and WIMS-AECL / DRAGON / RFSP calculations and experimental results obtained from the Zero Energy Deuterium (ZED-2) critical facility at AECL Chalk River Laboratories. MCNP5 and WIMS-AECL / DRAGON / RFSP were used to calculate reactivity worths for two reactivity devices, a mechanical zone controller (MZC) and shut-off rod (SOR) in a lattice similar to that of the ACR-1000 R . WIMS-AECL / DRAGON / RFSP was also used to obtain kinetics parameters for a transient based on a rod drop of a ZED-2 standby absorber rod (SAR). ZED-2 experiments were performed using 43-element ACR Low Enriched Uranium (ACR-LEU) fuel bundles with H 2 O- or air-cooled fuel bundles arranged in a 24-cm pitch square lattice. Calculations with MCNP5 gave biases in device worths that were within 0.2 mk of measured values, while WIMS-AECL / DRAGON / RFSP gave values that were within 0.3 mk of measured values. Transient analyses using the CERBERUS module within RFSP yielded a total delayed neutron fraction (β) that was within 4% of the value derived by point kinetics analysis of experimental data. The corresponding delayed photo-neutron fraction (β photo-neutron ) from CERBERUS was within 5% of that derived by point kinetics. This study has helped quantify the agreement between calculation and measurement for codes that are used in the safety analysis of the ACR-1000 reactor. Results demonstrate good agreement in code predictions. (authors)

AECL experience with low-level radioactive waste technologies

International Nuclear Information System (INIS)

Buckley, L.P.; Charlesworth, D.H.

1988-08-01

Atomic Energy of Canada Limited (AECL), as the Canadian government agency responsible for research and development of peaceful uses of nuclear energy, has had experience in handling a wide variety of radioactive wastes for over 40 years. Low-level radioactive waste (LLRW) is generated in Canada from nuclear fuel manufacturers and nuclear power facilities, from medical and industrial uses of radioisotopes and from research facilities. The technologies with which AECL has strength lie in the areas of processing, storage, disposal and safety assessment of LLRW. While compaction and incineration are the predominant methods practised for solid wastes, purification techniques and volume reduction methods are used for liquid wastes. The methods for processing continue to be developed to improve and increase the efficiency of operation and to accommodate the transition from storage of the waste to disposal. Site-specific studies and planning for a LLRW disposal repository to replace current storage facilities are well underway with in-service operation to begin in 1991. The waste will be disposed of in an intrusion-resistant underground structure designed to have a service life of over 500 years. Beyond this period of time the radioactivity in the waste will have decayed to innocuous levels. Safety assessments of LLRW disposal are performed with the aid of a series of interconnected mathematical models developed at Chalk River specifically to predict the movement of radionuclides through and away from the repository after its closure and the subsequent health effects of the released radionuclides on the public. The various technologies for dealing with radioactive wastes from their creation to disposal will be discussed. 14 refs

Radiation protection aspects of AECL's retube/refurbishment projects

International Nuclear Information System (INIS)

Zhuang, Y.; Boss, C.R.; Pontikakis, N.

2007-01-01

In contrast to the construction of a new nuclear reactor, Retube/Refurbishment of nuclear reactors that have been in operation for many years will involve fabrication of a new core in a radiation environment. Careful planning of the radiation protection (RP) program is crucial to ensure the protection of workers and the environment, and the success of the projects. This paper describes the key RP activities currently underway in AECL's Retube/Refurbishment projects, covering RP during retubing tooling and system designs, retubing work planning, retubing operation, and waste transfer and management. The discussion will focus on RP initiatives from engineering design aspects of the projects. (author)

New capabilities of the lattice code WIMS-AECL

International Nuclear Information System (INIS)

Altiparmakov, Dimitar

2008-01-01

The lattice code WIMS-AECL has been restructured and rewritten in Fortran 95 in order to increase the accuracy of its responses and extend its capabilities. Significant changes of computing algorithms have been made in the following two areas: geometric calculations and resonance self-shielding. Among various geometry enhancements, the code is no longer restricted to deal with single lattice cell problems. The multi-cell capability allows modelling of various lattice structures such as checkerboard lattices, a de-fuelled channel, and core-reflector interface problems. The new resonance method performs distributed resonance self-shielding including the skin effect. This paper describes the main code changes and presents selected code verification results. (authors)

AECL research programmes in materials science

International Nuclear Information System (INIS)

Cox, B.; Eastwood, T.A.; Mitchell, I.V.; Dutton, R.

1980-10-01

The high capacity factors achieved by CANDU nuclear power reactors can be attributed in part to the careful attention which has been paid in the concept and design phases to the selection of materials. Improved tolerance of these materials to the hostile conditions of a reactor core depends upon our understanding of such phenomena as radiation damage, corrosion and cracking. This report is an introduction to some of the fundamental and underlying research programmes that have evolved at the AECL laboratories in response to this need. The interactions of energetic atomic particles with solids on a microscopic scale are considered, first under the general heading of radiation effects, followed by sections on energy loss processes, ion channeling, and crystal lattice defects. The latter section leads into the important programmes on deformation processes (creep and growth) in zirconium. The final section discusses the extensive work on the oxidation and environmental cracking of zirconium alloys. (auth)

Research reactor fuel development at AECL

International Nuclear Information System (INIS)

Sears, D.F.; Wang, N.

2000-09-01

This paper reviews recent U 3 Si 2 and U-Mo dispersion fuel development activities at AECL. The scope of work includes fabrication development, irradiation testing, post-irradiation examination and performance qualification. U-Mo alloys with a variety of compositions, ranging from 6 to 10 wt % Mo, have been fabricated with high purity and homogeneity in the product. The alloys and powders were characterized using optical and scanning electron microscopy, chemical analysis, and X-ray diffraction and neutron diffraction analysis. U-Mo powder samples have been supplied to the Argonne National Laboratory for irradiation testing in the ATR reactor. Low-enriched uranium fuel elements containing U-7 wt % Mo and U-10 wt % Mo with loadings up to 4.5 gU/cm 3 have been fabricated at CRL for irradiation testing in the NRU reactor. The U-Mo fuel elements will be tested in NRU at linear powers up to 145 kW/m, and to 85 atom % 235 U burnup. (author)

AECL's progress in DUPIC fuel development

International Nuclear Information System (INIS)

Sullivan, J.D.; Ryz, M.A.; Lee, J.W.

1997-01-01

Previous papers described progress in choosing a fabrication route for the DUPIC (Direct Use of Spent PWR Fuel in CANDU) fuel cycle [1], details of the OREOX (Oxidation Reduction of Oxide fuel) process, and preliminary results of out-cell and small-scale in-cell experiments [2]. AECL's project to develop the DUPIC fuel cycle has now progressed to the stage of fabricating DUPIC fuel elements for irradiation testing in a research reactor. Because of the high radiation fields around the spent PWR fuel, all work is being done in hot cells. The equipment used for fabrication of the DUPIC fuel elements is described in this paper. The commissioning, in-cell installation and current status of the fabrication process are also described and plans for the completion of this phase of the DUPIC project are outlined. The goal of this phase of the project is demonstration of the technical feasibility of the DUPIC fuel cycle. (author)

Research reactor fuel development at AECL

International Nuclear Information System (INIS)

Sears, D.F.; Wang, N.

2000-01-01

This paper reviews recent U 3 Si 2 and U-Mo dispersion fuel development activities at AECL. The scope of work includes fabrication development, irradiation testing, postirradiation examination and performance qualification. U-Mo alloys with a variety of compositions, ranging from 6 to 10 wt % Mo, have been fabricated with high purity and homogeneity in the product. The alloys and powders were characterized using optical and scanning electron microscopy, chemical analysis, and X-ray diffraction and neutron diffraction analysis. U-Mo powder samples have been supplied to the Argonne National Laboratory for irradiation testing in the ATR reactor. Low-enriched uranium fuel elements containing U-7 wt % Mo and U-10 wt % Mo with loadings up to 4.5 gU/cm 3 have been fabricated at CRL for irradiation testing in the NRU reactor. The U-Mo fuel elements will be tested in NRU at linear powers up to 145 kW/m, and to 85 atom % 235 U burnup. (author)

Advanced fuel development at AECL: What does the future hold for CANDU fuels/fuel cycles?

Energy Technology Data Exchange (ETDEWEB)

Kupferschmidt, W.C.H. [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada)

2013-07-01

This paper outlines advanced fuel development at AECL. It discusses expanding the limits of fuel utilization, deploy alternate fuel cycles, increase fuel flexibility, employ recycled fuels; increase safety and reliability, decrease environmental impact and develop proliferation resistant fuel and fuel cycle.

The Atomic Energy of Canada Limited (AECL) employee health study

International Nuclear Information System (INIS)

Myers, D.K.; Werner, M.M.

1985-01-01

A preliminary examination of records relating to past Chalk River employees provides some reassurance that large numbers of cancer deaths that might be related to occupational radiation exposure do not exist in the groups of employees studied to the end of 1982. The lack of reliable information on deaths of ex-employees who left AECL for other employment prevented the inclusion of this group in this preliminary study. This information will presumably be obtained during the course of the more comprehensive Atomic Energy of Canada Ltd. employee health study. 6 refs

Sensitivity of 238U resonance absorption to library multigroup structure as calculated by WIMS-AECL

International Nuclear Information System (INIS)

Laughton, P.J.; Donnelly, J.V.

1995-01-01

In simulations of the TRX-1 experimental lattice, WIMS-AECL overpredicts, relative to MCNP, resonance absorption in neutron-energy groups containing the three large, low-lying resonances of 238 U when a standard ENDF/B-V-based library is used. A total excess in these groups of 4.0 neutron captures by 238 U per thousand fission neutrons has been observed. Similar comparisons are made in this work for the MIT-4 experimental lattice and simplified CANDU lattice cells containing 37-element fuel, with and without heavy-water coolant. Eleven different 89-group cross-section libraries were constructed for WIMS-AECL from ENDF/B-V data: only the neutron-energy-group boundaries used in generating multigroup cross sections and the Goldstein-Cohen correction factors differ from one library to the next. The first library uses the original 89-group structure, and the other ten involve energy groups of varying widths centred on the three large, low-lying resonances of 238 U. For TRX-1, some reduction in total discrepancy in 238 U capture can be achieved by using a new structure, although the improvement is small. The discrepancies in 238 U capture are of the same order for the MIT-4 case as those observed for TRX-1 for both the original group structure and the ten new structures. The WIMS-AECL calculation of 238 U resonance absorption in the same ranges of energy for the simplified CANDU 37-element lattice are in better agreement with MCNP than they are for TRX-1 and MIT-4: when the original structure is used, WIMS-AECL underpredicts total capture rate by 238 U in the energy range of interest by only 0.56 per thousand fission neutrons (coolant present) and 0.88 per thousand fission neutrons (voided coolant channel). The discrepancies are reduced when some of the new structures are used. For almost all of the cases considered here-TRX-1, MIT-4 and CANDU with coolant-better group-by-group agreement of 238 U capture around the 6.67-eV resonance is achieved by using a new library

Studies on groundwater flow and radionuclide migration at underground environments. Final report of collaboration research between JAERI and AECL

International Nuclear Information System (INIS)

Ogawa, Hiromichi; Nagao, Seiya; Yamaguchi, Tetsuji

2001-01-01

The Japan Atomic Energy Research Institute (JAERI) conducted a collaboration program Phase II with the Atomic Energy of Canada Limited (AECL) from 1994 to 1998. The program was started to contribute the establishment of safety assessment methodology for the geological disposal of high-level radioactive wastes on the basis of the results from the Phase I program (1987-1993). The Phase II program consisted of following experimental items: (1) radionuclide migration experiments for quarried blocks (1m x 1m x 1m) of granite with natural fracture under in-situ geochemical conditions at 240 m level of Underground Research Laboratory of AECL; (2) study on the effects of dissolved organic materials extracted from natural groundwaters on radionuclide migration; (3) study on groundwater flow using environmental isotopes at two different geologic environments; (4) development of groundwater flow and radionuclide transport model for heterogeneous geological media. The mobility of radionuclides was retarded in the fracture by the deep geological conditions and the fracture paths. The groundwater humic substances with high molecular size were enhanced for the mobility of radionuclides in the sand and granitic media due to the complexation. The application of 36 Cl and 129 I for the analysis on the long-term groundwater flow can be validated on the basis of investigation at the URL site. Moreover, the geostatistical model for the analysis on groundwater flow and radionuclide migration was developed, and was able to describe the groundwater flow and the migration of environmental tracers at AECL sites. This report summaries the results of the Phase II program between JAERI and AECL. (author)

Studies on groundwater flow and radionuclide migration at underground environments. Final report of collaboration research between JAERI and AECL

Energy Technology Data Exchange (ETDEWEB)

Ogawa, Hiromichi; Nagao, Seiya; Yamaguchi, Tetsuji [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment] [and others

2001-01-01

The Japan Atomic Energy Research Institute (JAERI) conducted a collaboration program Phase II with the Atomic Energy of Canada Limited (AECL) from 1994 to 1998. The program was started to contribute the establishment of safety assessment methodology for the geological disposal of high-level radioactive wastes on the basis of the results from the Phase I program (1987-1993). The Phase II program consisted of following experimental items: (1) radionuclide migration experiments for quarried blocks (1m x 1m x 1m) of granite with natural fracture under in-situ geochemical conditions at 240 m level of Underground Research Laboratory of AECL; (2) study on the effects of dissolved organic materials extracted from natural groundwaters on radionuclide migration; (3) study on groundwater flow using environmental isotopes at two different geologic environments; (4) development of groundwater flow and radionuclide transport model for heterogeneous geological media. The mobility of radionuclides was retarded in the fracture by the deep geological conditions and the fracture paths. The groundwater humic substances with high molecular size were enhanced for the mobility of radionuclides in the sand and granitic media due to the complexation. The application of {sup 36}Cl and {sup 129}I for the analysis on the long-term groundwater flow can be validated on the basis of investigation at the URL site. Moreover, the geostatistical model for the analysis on groundwater flow and radionuclide migration was developed, and was able to describe the groundwater flow and the migration of environmental tracers at AECL sites. This report summaries the results of the Phase II program between JAERI and AECL. (author)

Implementing the AECL decommissioning quality assurance program at the Chalk River and Whiteshell Laboratories

International Nuclear Information System (INIS)

Colotelo, C.A.; Attas, E.M.; Stephens, M.E.

2006-01-01

This paper describes the approach and progress in developing, implementing and maintaining a quality assurance (QA) program for decommissioning at the nuclear facilities managed by Atomic Energy of Canada Limited (AECL). Decommissioning activities conducted by AECL are varied in nature, so the QA program must provide adequate flexibility, while maintaining consistency with accepted quality standards. Well-written documentation adhering to the applicable decommissioning standards is a key factor. Manager commitment and input during the writing of the documentation are also important to ensure relevance of the QA program and effectiveness of implementation. Training in the use of the quality assurance plan and procedures is vital to the understanding of the QA program. Beyond the training aspect there is a need for the quality assurance program to be supported by a QA subject expert who is able to advise the group in implementing the Quality Program with consistency over the range of decommissioning work activities and to provide continual assessment of the quality assurance program for efficiency and effectiveness, with a concomitant continuous improvement process. (author)

Rationalization and future planning for AECL's research reactor capability

International Nuclear Information System (INIS)

Slater, J.B.

1990-01-01

AECL's research reactor capability has played a crucial role in the development of Canada's nuclear program. All essential concepts for the CANDU reactors were developed and tested in the NRX and NRU reactors, and in parallel, important contributions to basic physics were made. The technical feasibility of advanced fuel cycles and of the organic-cooled option for CANDU reactors were also demonstrated in the two reactors and the WR-1 reactor. In addition, an important and growing radio-isotope production industry was established and marketed on a world-wide basis. In 1984, however, it was recognized that a review and rationalization of the research reactor capability was required. The commercial success of the CANDU reactor system had reduced the scope and size of the required development program. Limited research and development funding and competition from other research facilities and programs, required that the scope be reduced to a support basis essential to maintain strategic capability. Currently, AECL, is part-way through this rationalization program and completion should be attained during 1992/93 when the MAPLE reactor is operational and decisions on NRX decommissioning will be made. A companion paper describes some of the unique operational and maintenance problems which have resulted from this program and the solutions which have been developed. Future planning must recognize the age of the NRU reactor (currently 32 years) and the need to plan for eventual replacement. Strategy is being developed and supporting studies include a full technical assessment of the NRU reactor and the required age-related upgrading program, evaluation of the performance characteristics and costs of potential future replacement reactors, particularly the advanced MAPLE concept, and opportunities for international co-operation in developing mutually supportive research programs

A study of the mortality of AECL employees. V

International Nuclear Information System (INIS)

Gribbin, M.A.; Howe, G.R.; Weeks, J.L.

1992-09-01

A study has been underway since 1980 on the mortality of past and present AECL employees. The study population consists of 13,491 persons, 9997 males and 3494 females, for a total of 262,403.5 person-years at risk. During the period 1950-1985, 1299 deaths occurred in this population. The number of female deaths (121) is too few for detailed analysis, but the 1178 deaths in the male population represent a useful basis for this study. The present report examines mortality patterns in the AECL cohort between 1950 and 1985 by comparing the observed mortality with that expected in the general population for three groups of workers: those with no exposure, those with up to 50 mSv, and those with more than 50 mSv. Comparisons among the three groups of employees are discussed. The number of deaths is fewer than would be expected on the basis of general population statistics for both males who were exposed to ionizing radiation and those who were not exposed. The findings were similar for the 'all cancer' and 'all other deaths' groupings. In the group of exposed males, elevated Standardized Mortality Ratios (SMRs) are seen for non-Hodgkin's lymphoma and for buccal cavity, rectum and rectosigmoid junction, and prostate cancers. There are elevated SMRs for lymphatic and myeloid leukemias and for large intestine, prostate, brain and biliary system cancers in the 'unexposed' male group. The number of cases identified in all of these cancers is small and the confidence intervals are wide, such that none of the elevated SMRs is statistically significant. The report compares the findings of this study with those of similar studies published in the past decade. (Author) (28 tabs., 33 refs., 2 figs.)

Radiochemistry Lab Decommissioning and Dismantlement. AECL, Chalk River Labs, Ontario, Canada

International Nuclear Information System (INIS)

Kenny, Stephen

2008-01-01

Atomic Energy of Canada (AECL) was originally founded in the mid 1940's to perform research in radiation and nuclear areas under the Canadian Defense Department. In the mid 50's The Canadian government embarked on several research and development programs for the development of the Candu Reactor. AECL was initially built as a temporary site and is now faced with many redundant buildings. Prior to 2004 small amounts of Decommissioning work was in progress. Many reasons for deferring decommissioning activities were used with the predominant ones being: 1. Reduction in radiation doses to workers during the final dismantlement, 2. Development of a long-term solution for the management of radioactive wastes in Canada, 3. Financial constraints presented by the number of facilities shutdown that would require decommissioning funds and the absence of an approved funding strategy. This has led to the development of a comprehensive decommissioning plan that is all inclusive of AECL's current and legacy liabilities. Canada does not have a long-term disposal site; therefore waste minimization becomes the driving factor behind decontamination for decommissioning before and during dismantlement. This decommissioning job was a great learning experience for decommissioning and the associated contractors who worked on this project. Throughout the life of the project there was a constant focus on waste minimization. This focus was constantly in conflict with regulatory compliance primarily with respect to fire regulations and protecting the facility along with adjacent facilities during the decommissioning activities. Discrepancies in historical documents forced the project to treat every space as a contaminated space until proven differently. Decommissioning and dismantlement within an operating site adds to the complexity of the tasks especially when it is being conducted in the heart of the plant. This project was very successful with no lost time accidents in over one hundred

Analysis of the results for the AECL cohort in the IARC study on the radiogenic cancer risk among nuclear industry workers in fifteen countries

Energy Technology Data Exchange (ETDEWEB)

Ashmore, J.P. [Ponsonby and Associates, Manotick, Ontario (Canada); Gentner, N.E. [Consultant, Petawawa, Ontario (Canada); Osborne, R.V. [Ranasara Consultants Inc., Deep River, Ontario (Canada)

2007-03-31

Over the last two decades there have been attempts to estimate the risks from occupational exposure in the nuclear industry by epidemiological assessments on cohorts of workers. However, generally low doses and relatively small worker populations have limited the precision of such studies. In 1995 the International Agency for Research on Cancer (IARC) completed a study that involved workers from facilities in the USA, UK and AECL. In 2005, IARC completed a further study involving nuclear workers from 15 countries including Canada. Surprisingly, the risk ascribed to the Canadian cohort for all cancers excluding leukaemia, driven by the AECL component, was significantly higher than the cohort as a whole. The work described in this report is an attempt to unravel what might have accounted for the divergence between the results for the AECL cohort and the others.

Analysis of the results for the AECL cohort in the IARC study on the radiogenic cancer risk among nuclear industry workers in fifteen countries

International Nuclear Information System (INIS)

Ashmore, J.P.; Gentner, N.E.; Osborne, R.V.

2007-01-01

Over the last two decades there have been attempts to estimate the risks from occupational exposure in the nuclear industry by epidemiological assessments on cohorts of workers. However, generally low doses and relatively small worker populations have limited the precision of such studies. In 1995 the International Agency for Research on Cancer (IARC) completed a study that involved workers from facilities in the USA, UK and AECL. In 2005, IARC completed a further study involving nuclear workers from 15 countries including Canada. Surprisingly, the risk ascribed to the Canadian cohort for all cancers excluding leukaemia, driven by the AECL component, was significantly higher than the cohort as a whole. The work described in this report is an attempt to unravel what might have accounted for the divergence between the results for the AECL cohort and the others

Some highlights of research and development at AECL

International Nuclear Information System (INIS)

Langford, W.J.; Rae, H.K.

1980-06-01

The research and development programs of AECL have as their goal the strengthening of the knowledge and ability necessary to achieve national objectives in the field of nuclear energy. These objectives include a nuclear reactor system appropriate to Canada's industrial capabilities, now realized, and the extension of that system, through scientific and technological development, to serve the nation's needs for the forseeable future. The Company's programs are carefully integrated and focused to use the available funding to maximum advantage. The research facilities on which the program depends are among the best in the world, and support a full spectrum of research from fundamental nuclear physics to full-scale power reactor component irradiation and testing. In this report it has only been possible to high-light some important facets of the programs in each of the principal areas currently employing our energies. (auth)

Final report of the AECL/SKB Cigar Lake analog study

International Nuclear Information System (INIS)

Cramer, J.J.

1994-07-01

The Cigar Lake uranium deposit is located in northern Saskatchewan, Canada. The 1.3-billion-year-old deposit is located at a depth of about 450 m below surface in a water-saturated sandstone at the unconformity contact with the high-grade metamorphic rocks of the Canadian Shield. The uranium mineralization, consisting primarily of uraninite (UO 2 ), is surrounded by a clay-rich halo in both sandstone and basement rocks, and remains extremely well preserved and intact. The average grade of the mineralization is ∼ 8 wt.% U; locally grades are as high as ∼ 55 wt.%U. The Cigar lake deposit has many features that parallel those being considered within the Canadian concept for disposal of nuclear fuel waste. Specifically, the deposit provides analog information relevant to the stability of UO 2 fuel waste, the performance of clay-based barriers, radionuclide migration, colloid formation, radiolysis, fission-product geochemistry and general aspects of water-rock interaction. The main geochemical studies on this deposit focus on the evolution of groundwater compositions in the deposit and on their redox chemistry with respect to the uranium, iron and sulphide systems. Since 1984, through cooperation from the owners of the Cigar lake deposit, analog studies have been conducted. AECL, with support from Ontario Hydro under the auspices of the CANDU Owners Group, initiated international participation in 1989 through collaboration with the Swedish Nuclear Fuel and Waste Management Company (SKB) and, more recently, with the Los Alamos National Laboratory (LANL). This report gives the results of the various studies carried out during the 3-year collaboration between AECL and SKB, as well as a summary of the LANL study. It provides detailed information on the generated databases and models, and integrates this information into conclusions for use in safety assessment of the Canadian, Swedish and United States disposal concepts. 15 refs., 25 figs., 55 tabs

The AECL reactor development programme

International Nuclear Information System (INIS)

Menelely, D.A.

1997-01-01

The modem CANDU-PHWR power reactor is the result of more than 50 years of evolutionary design development in Canada. It is one of only three commercially successful designs in the world to this date. The basis for future development is the CANDU 6 and CANDU 9 models. Four of the first type are operating and four more will go an line before the end of this decade. The CANDU 9 is a modernized single-unit version of the twelve large multi-unit plants operated by Ontario Hydro. All of these plants use proven technology which resulted from research, development, design construction, and operating experience over the past 25 years. Looking forward another 25 years, AECL plans to retain all of the essential features that distinguish today's CANDU reactors (heavy water moderation, on-power fuelling simple bundle design, horizontal fuel channels, etc.). The end product of the planned 25-year development program is more than a specific design - it is a concept which embodies advanced features expected from ongoing R and D programs. To carry out the evolutionary work we have selected seven main areas for development: Safety Technology, Fuel and Fuel Cycles, Fuel Channels, Systems and Components, Heavy Water and Tritium Information Technology, and Construction. There are three strategic measures of success for each of these work areas: improved economics, advanced fuel cycle utilization, and enhanced safety/plant robustness. The paper describes these work programs and the overall goals of each of them. (author)

Validation of DRAGON code in connection with WIMS-AECL/RFSP code system based on ENDF/B-VI library and two group model

International Nuclear Information System (INIS)

Hong, In Seob; Suk, Ho Chun; Kim, Soon Young; Jo, Chang Keun

2002-06-01

The major objective of this research is to validate the incremental cross section property of DRAGON code in connection with WIMS-AECL/DRAGON/RFSP code system with ENDF/B-VI library and full 2G calculation model. The direct comparison between the incremental cross section results calculated by DRAGON with ENDF/B-VI and ENDF/B-V and MULTICELL with ENDF/B-V indicate that there are not much differences between the incremental cross sections of DRAGON with ENDF/B-V and ENDF/B-VI, but there exists large discrepancies between the results of DRAGON and those of MULTICELL. In the analysis of the difference between calculated and measured reactivity worths of various types of control devices during Phase-B Post-Simulation of Wolsong Units 2, 3 and 4, WIMS-AECL/DRAGON/RFSP analysis well agrees with those of previous WIMS-AECL /MULTICELL/RFSP analysis within very small differences. From those results, we can conclude that DRAGON code can be used as a general purpose incremental cross section generation tool for not only the natural uranium fuel but also slightly enriched fuel such as RU or SEU, to cover the shortcomings of natural uranium based MULTICELL code

Final report of the AECL/SKB Cigar Lake analog study

International Nuclear Information System (INIS)

Cramer, J.

1994-05-01

The Cigar Lake uranium deposit is located in northern Saskatchewan, Canada. The 1.3-billion-year-old deposit is located at a depth of about 450 m below surface in a water-saturated sandstone at the unconformity contact with the high-grade metamorphic rocks of the Canadian Shield. The Cigar Lake deposit has many features that parallel those being considered within the Canadian concept for disposal of nuclear fuel waste. The study of these natural structures and processes provides valuable insight toward the eventual design and site selection of a nuclear fuel waste repository. The main feature of this analog is the absence of any indication on the surface of the rich uranium ore 450 m below. This indicates that the combination of natural barriers has been effective in isolating the uranium ore from the surface environment. More specifically, the deposit provides analog information relevant to the stability of UO 2 fuel waste, the performance of clay-based barriers, radionuclide migration, colloid formation, radiolysis, fission-product geochemistry and general aspects of water-rock interaction. The main geochemical studies on this deposit focus on the evolution of groundwater compositions in the deposit and on their redox chemistry with respect to the uranium, iron and sulphide systems. Since 1984, through cooperation from the owners of the Cigar Lake deposit, analog studies have been conducted. AECL, with support from Ontario Hydro under the auspices of the CANDU Owners Group, initiated international participation in 1989 through collaboration with the Swedish Nuclear Fuel and Waste Management Company (SKB) and, more recently, with the Los Alamos National Laboratory (LANL). This report gives the results of the various studies carried out during the 3-year collaboration between AECL and SKB, as well as a summery of the LANL study. It provides detailed information on the generated databases and models, and integrates this information into conclusions for use in safety

AECL international standard problem ISP-41 FU/1 follow-up exercise (Phase 1): Containment Iodine Computer Code Exercise: Parametric Studies

International Nuclear Information System (INIS)

Ball, J.; Glowa, G.; Wren, J.; Ewig, F.; Dickenson, S.; Billarand, Y.; Cantrel, L.; Rydl, A.; Royen, J.

2001-06-01

This report describes the results of the second phase of International Standard Problem (ISP) 41, an iodine behaviour code comparison exercise. The first phase of the study, which was based on a simple Radioiodine Test Facility (RTF) experiment, demonstrated that all of the iodine behaviour codes had the capability to reproduce iodine behaviour for a narrow range of conditions (single temperature, no organic impurities, controlled pH steps). The current phase, a parametric study, was designed to evaluate the sensitivity of iodine behaviour codes to boundary conditions such as pH, dose rate, temperature and initial I- concentration. The codes used in this exercise were IODE (IPSN), IODE (NRIR), IMPAIR (GRS), INSPECT (AEAT), IMOD (AECL) and LIRIC (AECL). The parametric study described in this report identified several areas of discrepancy between the various codes. In general, the codes agree regarding qualitative trends, but their predictions regarding the actual amount of volatile iodine varied considerably. The largest source of the discrepancies between code predictions appears to be their different approaches to modelling the formation and destruction of organic iodides. A recommendation arising from this exercise is that an additional code comparison exercise be performed on organic iodide formation, against data obtained from intermediate-scale studies (two RTF (AECL, Canada) and two CAIMAN facility (IPSN, France) experiments have been chosen). This comparison will allow each of the code users to realistically evaluate and improve the organic iodide behaviour sub-models within their codes. (authors)

ZZ CANDULIB-AECL, Burnup-Dependent ORIGEN-S Cross-Section Libraries for Candu Reactor Fuels

International Nuclear Information System (INIS)

2002-01-01

1 - Historical background and information: - 28-element fuel cross-section library: Format: Designed for use with the ORIGEN-S isotope generation and depletion code. Materials: Co, Ge, As, Se, Br, Kr, Rb, Sr, Y, Zr, Nb, Mo, Tc, Ru, Rh, Pd, Ag, Cd, In, Sn, Sb, Te, I, Xe, Cs, Ba, La, Ce, Pr, Nd, Pm, Sm, Eu, Gd, Tb, Dy, Ho, Er, Lu, Ta, W, Re, Au, Th, Pa, U, Np, Pu, Am, Cm. Origin: ENDSF, ENDF/B-IV, -V and -VI Weighting spectrum: determined using WIMS-AECL transport code. - 37-element fuel cross-section library: Format: Designed for use with the ORIGEN-S isotope generation and depletion code. Materials: Co, Ge, As, Se, Br, Kr, Rb, Sr, Y, Zr, Nb, Mo, Tc, Ru, Rh, Pd, Ag, Cd, In, Sn, Sb, Te, I, Xe, Cs, Ba, La, Ce, Pr, Nd, Pm, Sm, Eu, Gd, Tb, Dy, Ho, Er, Lu, Ta, W, Re, Au, Th, Pa, U, Np, Pu, Am, Cm. Origin: ENDSF, ENDF/B-IV, -V and -VI Weighting spectrum: determined using WIMS-AECL transport code. In 1995, updated ORIGEN-S cross-section libraries were created as part of a program to upgrade and standardize the computer codes and nuclear data employed for used fuel characterization. This effort was funded through collaboration between Atomic Energy of Canada Limited and the Canadian Nuclear Power Utilities, under the Candu Owners Group (COG). The updated cross sections were generated using the WIMS-AECL lattice code and ENDF/B-V and -VI based data to provide cross section consistency with reactor physics codes. 2 - Application of the data: The libraries in this data collection are designed for characterising used fuel from Candu pressurized heavy water reactors. Two libraries are provided: one for the standard 28-element fuel bundle design, the other for the 37-element fuel bundle design. The libraries were generated for typical reactor operating conditions. The libraries are designed for use with the ORIGEN-S isotope generation and depletion code. 3 - Source and scope of data: The Candu libraries are updated with cross sections from a variety of different sources. Capture

AECL R and D's role in promoting nuclear research and education

International Nuclear Information System (INIS)

Sadhankar, R.

2009-01-01

Nuclear renaissance has created new opportunities for new technology development and has also brought along the challenge of meeting the growing demand of trained personnel in the nuclear science and engineering. Towards meeting this challenge, AECL R and D organization is actively promoting and supporting the creation of nuclear research capabilities at the universities and also effectively leveraging the R and D at the universities. It has also put in place several new initiatives to attract and develop the talented young people for careers in nuclear science and engineering. This paper describes various interactions and collaborations with the universities that supports the nuclear R and D at the universities and develop highly qualified personnel for the future nuclear R and D needs. (author)

AECL IMPELA electron beam industrial irradiators

International Nuclear Information System (INIS)

Labrie, J.P.; Drewell, N.H.; Ebrahim, N.A.; Lawrence, C.B.; Mason, V.A.; Ungrin, J.; White, B.F.

1989-01-01

A family of industrial irradiators is being developed by AECL to cover an electron-beam energy range from 5 to 18 MeV at beam powers between 20 and 250 kW. The IMPELA family of irradiators is designed for push button, reliable operation. The major irradiator components are modular, allowing for later upgrades to meet increased demands in either electron or X-ray mode. Interface between the control system, irradiator availability and dose quality assurance is in conformance with the most demanding specifications. The IMPELA irradiators use a klystron-driven, standing-wave, L-band accelerator structure with direct injection from a rugged, triode electron gun. Direct control of the accelerating field during the beam pulse ensures constant output beam energy, independent of beam power. The first member of the family, the IMPELA 10/50 (10 MeV, 50 kW), is in the final stages of assembly at Chalk River Nuclear Laboratories. The IMPELA 10/50 is constructed around a 3.25 m long, high-power-capacity accelerator structure operated at a duty factor of 5%. Beam loading exceeds 60%. The rf power is provided by a 2 MW/150 kW modulated-anode klystron protected from load mismatches by a circulator. This prototype will be used to demonstrate the reliability and dose uniformity targets of the IMPELA family. Full beam operation of the IMPELA 10/50 is scheduled for early 1989. (orig.)

Antibiotics from bacillus subtilis AECL90 - effect of trace elements and carbohydrates on antibiotic production

International Nuclear Information System (INIS)

Malik, M.A.; Shaukat, G.A.; Ahmed, M.S.

1990-01-01

Three types of antibiotics S, X and F characteristically bioactive against staphylococcic, xanthomonas and fungi are elaborated by Bacillus Subtilis AECL 69 when grown in molasses peptone malt extract sucrose. No antibiotic production was observed when molasses was omitted from the growth medium. A mineral salt mixture was devised that could replace molasses and restore the production of antibiotics. Influence of various carbohydrates on the production of antibiotics was also studied. Mannose and mannitol had inhibitory effect on the antibiotic production. (author)

Sensitivity analysis on various parameters for lattice analysis of DUPIC fuel with WIMS-AECL code

Energy Technology Data Exchange (ETDEWEB)

Roh, Gyu Hong; Choi, Hang Bok; Park, Jee Won [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1998-12-31

The code WIMS-AECL has been used for the lattice analysis of DUPIC fuel. The lattice parameters calculated by the code is sensitive to the choice of number of parameters, such as the number of tracking lines, number of condensed groups, mesh spacing in the moderator region, other parameters vital to the calculation of probabilities and burnup analysis. We have studied this sensitivity with respect to these parameters and recommend their proper values which are necessary for carrying out the lattice analysis of DUPIC fuel.

Sensitivity analysis on various parameters for lattice analysis of DUPIC fuel with WIMS-AECL code

Energy Technology Data Exchange (ETDEWEB)

Roh, Gyu Hong; Choi, Hang Bok; Park, Jee Won [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1997-12-31

The code WIMS-AECL has been used for the lattice analysis of DUPIC fuel. The lattice parameters calculated by the code is sensitive to the choice of number of parameters, such as the number of tracking lines, number of condensed groups, mesh spacing in the moderator region, other parameters vital to the calculation of probabilities and burnup analysis. We have studied this sensitivity with respect to these parameters and recommend their proper values which are necessary for carrying out the lattice analysis of DUPIC fuel.

Comparison of MCNP and WIMS-AECL/RFSP calculations with high temperature substitution experiments in ZED-2 using CANFLEX-L VRF

International Nuclear Information System (INIS)

Pencer, J.; Bromley, B.P.; Watts, D.G.; Carlson, P.; Rauket, A.; Zeller, M.

2009-01-01

This paper summarizes comparisons of calculation results from MCNP5 and WIMS-AECL / RFSP with experimental results obtained from the Zero Energy Deuterium (ZED-2) critical facility, examining CANFLEX Low Void Reactivity Fuel (CANFLEX-LVRF) in heated channels, substituted into a reference lattice and cooled under ACR-like coolant conditions, with H 2 O, air, or CO 2 as an air substitute. CANFLEX-LVRF shares features in common with the ACR-1000 fuel, notably an increase in enrichment (over natural uranium) in the outer elements of the fuel bundle, and presence of a neutron absorber in the central element. The reference and substituted fuel channels were arranged in a 24.5-cm hexagonal lattice in order to provide neutron similarity to the 24-cm square lattice pitch of the ACR-1000. These results therefore provide useful data for validation of the reactor physics toolset for use in ACR-1000 applications. For the mixed lattices, results for both MCNP5 and WIMS-AECL / RFSP show small biases in k eff , ranging from -7 mk to -5 mk, small biases in coolant void reactivity, ranging from -1 mk to +0.5 mk, and good agreement for copper activation rate distributions (based on calculated neutron flux). Bare core MCNP and WIMS-AECL stand-alone results, based on substitution analysis, also show small biases in k eff , ranging from -6 mk to -0.4 mk, and small biases in coolant void reactivity, ranging from -0.3 mk to +3.7 mk. This validation exercise thus gives good agreement between measurement and calculation and provides confidence in the accuracy of the physics toolset. (author)

Fretting wear of steam generator tubes: high-temperature tests on AECL rig

International Nuclear Information System (INIS)

Guerout, F.; Zbinden, M.

1993-07-01

The R and DD has undertaken the study of fretting-wear of Alloy 600 S.G. tubes which occurs by contact with migrating items. The test series was performed in Canada at AECL Research (Atomic Energy of Canada Limited) as part of an exchange program. Four types of configuration were envisaged: a tube-to-drilled hole support contact which provides reference results and three types of tube-to-support contacts which simulate the tube fretting-wear induced by a welding rod, a threaded rod and a knife-edge rod support. This programme is completed by the study of the contact between a S.G. tube and a neighbouring S.G. tube which has been broken after plugging. (authors). 1 tab., 3 refs

AECL's research and development program in environmental science and technology

International Nuclear Information System (INIS)

Cornett, R.J.

1998-07-01

AECL's radiological research and development (R and D) program encompasses work on sources of radiation exposure, radionuclide transport through the environment and potential impacts on biota and on human health. The application of the radiation protection knowledge and technology developed in this program provides cradle-to-grave management for CANDU and related nuclear technologies. This document provides an overview of the Environmental Science and Technology (ES and T) program which is one of the technical areas of R and D within the radiological R and D program. The ES and T program uses science from three main areas: radiochemistry, mathematical modelling and environmental assessment. In addition to providing an overview of the program, this summary also gives specific examples of recent technical work in each of the three areas. These technical examples illustrate the applied nature of the ES and T program and the close coupling of the program to CANDU customer requirements. (author)

Decommissioning of AECL Whiteshell Laboratories: progress from first five years of legacy funding

International Nuclear Information System (INIS)

Swartz, R.S.; Bilinsky, D.M.; Harding, J.W.; Ridgway, W.R.

2011-01-01

In 2006, the Government of Canada adopted a new long-term strategy to deal with the nuclear legacy liabilities and initiated a five-year start-up phase. The objective is to safely and cost-effectively reduce these liabilities, and associated risks, based on sound waste management and environmental principles in the best interests of Canadians. AECL's Whiteshell Laboratories is part of the long-term strategy and decommissioning activities are underway. Several redundant non-nuclear buildings have been removed/decommissioned, and redundant nuclear facilities (hot cell facilities, radiochemical laboratories) are being decontaminated and prepared for demolition. This paper describes the progress in the first five-year funding period (2006 April to 2011 March). (author)

AECL's underground research laboratory: technical achievements and lessons learned

International Nuclear Information System (INIS)

Ohta, M.M.; Chandler, N.A.

1997-03-01

During the development of the research program for the Canadian Nuclear Fuel Waste Management Program in the 1970's, the need for an underground facility was recognized. AECL constructed an Underground Research Laboratory (URL) for large-scale testing and in situ engineering and performance-assessment-related experiments on key aspects of deep geological disposal in a representative geological environment. Ale URL is a unique geotechnical research and development facility because it was constructed in a previously undisturbed portion of a granitic pluton that was well characterized before construction began, and because most of the shaft and experimental areas are below the water table. The specific areas of research, development and demonstration include surface and underground characterization; groundwater and solute transport; in situ rock stress conditions; temperature and time-dependent deformation and failure characteristics of rock; excavation techniques to minimize damage to surrounding rock and to ensure safe working conditions; and the performance of seals and backfills. This report traces the evolution of the URL and summarizes the technical achievements and lessons learned during its siting, design and construction, and operating phases over the last 18 years. (author)

Antibiotics from bacillus subtilis AECL69 8. isolation and purification of a complex of antibacterial antibiotics x

International Nuclear Information System (INIS)

Ahmad, M.S.; Malik, M.A.; Shaukat, G.A.

1996-01-01

A bacterial strain bacillus subtilis AECL69 produces two anti bacterial antibiotics in a specified complex or synthetic medium. One of the antibiotics is characteristically active against Xanthomonas citri. Procedures have been described to isolate and purify a complex of xanthmonas antibiotics from the fermented complex broths, and from the fermented synthetic medium as well. Paper chromatography coupled with bioautography has shown that the complex of xanthomonas antibiotics has at least three components. The three components were indicated irrespective of the fact whether it was isolated from the fermented complex or synthetic broth. (author)

Development, irradiation testing and PIE of UMo fuel at AECL

International Nuclear Information System (INIS)

Sears, D.F.

2005-01-01

This paper reviews recent U-Mo dispersion fuel development, irradiation testing and postirradiation examination (PIE) activities at AECL. Low-enriched uranium fuel alloys and powders have been fabricated at Chalk River Labs, with compositions ranging from U-7Mo to U-10Mo. The bulk alloys and powders were characterized using optical and scanning electron microscopy, chemical analysis, X-ray diffraction and neutron diffraction analysis. The analyses confirmed that the powders were of high quality, and in the desired gamma phase. Subsequently, kilogram quantities of DU-Mo and LEU-Mo powder have been manufactured for commercial customers. Mini-elements have been fabricated with LEU-7Mo and LEU-10Mo dispersed in aluminum, with a nominal loading of 4.5 gU/cm 3 . These have been irradiated in the NRU reactor at linear powers up to 100 kW/m. The mini-elements achieved 60 atom% 235 U burnup in 2004 March, and the irradiation is continuing to a planned discharge burnup of 80 atom% 235 U. Interim PIE has been conducted on mini-elements that were removed after 20 atom% 235 U burnup. The PIE results are presented in this paper. (author)

Decommissioning of AECL Whiteshell laboratories - 16311

International Nuclear Information System (INIS)

Koroll, Grant W.; Bilinsky, Dennis M.; Swartz, Randall S.; Harding, Jeff W.; Rhodes, Michael J.; Ridgway, Randall W.

2009-01-01

Whiteshell Laboratories (WL) is a Nuclear Research and Test Establishment near Winnipeg, Canada, operated by AECL since the early 1960's and now under decommissioning. WL occupies approximately 4400 hectares of land and employed more than 1000 staff up to the late-1990's, when the closure decision was made. Nuclear facilities at WL included a research reactor, hot cell facilities and radiochemical laboratories. Programs carried out at the WL site included high level nuclear fuel waste management research, reactor safety research, nuclear materials research, accelerator technology, biophysics, and industrial radiation applications. In preparation for decommissioning, a comprehensive environmental assessment was successfully completed [1] and the Canadian Nuclear Safety Commission issued a six-year decommissioning licence for WL starting in 2003 - the first decommissioning licence issued for a Nuclear Research and Test Establishment in Canada. This paper describes the progress in this first six-year licence period. A significant development in 2006 was the establishment of the Nuclear Legacy Liabilities Program (NLLP), by the Government of Canada, to safely and cost effectively reduce, and eventually eliminate the nuclear legacy liabilities and associated risks, using sound waste management and environmental principles. The NLLP endorsed an accelerated approach to WL Decommissioning, which meant advancing the full decommissioning of buildings and facilities that had originally been planned to be decontaminated and prepared for storage-with-surveillance. As well the NLLP endorsed the construction of enabling facilities - facilities that employ modern waste handling and storage technology on a scale needed for full decommissioning of the large radiochemical laboratories and other nuclear facilities. The decommissioning work and the design and construction of enabling facilities are fully underway. Several redundant non-nuclear buildings have been removed and redundant

Past and future fracturing in AECL Research areas in the superior province of the Canadian Precambrian Shield, with emphasis on the Lac du Bonnet Batholith

Energy Technology Data Exchange (ETDEWEB)

Brown, A; Everitt, R A; Martin, C D; Davison, C C [Atomic Energy of Canada Ltd., Pinawa, MB (Canada). Whiteshell Labs.

1995-10-01

The likelihood that future fracturing, arising from geologic causes, could occur in the vicinity of a nuclear fuel waste repository in plutonic rock of the Canadian Precambrian Shield, is examined. The report discusses the possible causes of fracturing (both past and future) in Shield rocks. The report then examines case histories of fracture formation in Precambrian plutonic rocks in AECL`s Research Areas, especially the history of the Lac du Bonnet Batholith, in the Whiteshell Area, Manitoba. Initially, fractures can be introduced into intrusive plutonic rocks during crystallization and cooling of an intrusive magma. These fractures are found at all size scales; as late residual magma dyking, hydraulic fracturing by retrograde boiling off of hydrothermal fluids, and, in some cases, through local differential cooling. Subsequent fracturing is largely caused by changes in environmental temperature and stress field, rather than by alteration of the material behaviour of the rock. Pluton emplacement during orogeny is commonly accompanied by uplift and erosional exhumation, altering both the tectonic and the lithostatic stresses, the rock temperature gradient and the pore fluid characteristics.

Simulating thermal behavior of AECL's spent fuel dry storage system with CATHENA

International Nuclear Information System (INIS)

Sabourin, G.

1998-01-01

This paper documents the comparisons between CATHENA predictions and temperature measurements taken at the Gentilly-2 NPP spent fuel dry storage facility and in a mock--up of a storage basket placed inside a storage cylinder. It also presents CATHENA temperature predictions related to the storage of spent fuel in MACSTOR modules as planned for Ignalina NPP, Lithuania. CATHENA has been chosen because it can simulate many noncondensable gases including air and helium, and because of its great flexibility in the representation of the MACSTOR module geometry. The results of the simulations show good agreement with the experimental measurements. The two comparisons indicate that CATHENA can be used to simulate heat transfer from the fuel to the external air circuit of the spent fuel dry storage system. For the Ignalina MACSTOR module, containing RBMK fuel having higher heat release than typical CANDU fuel, CATHENA predicts that the maximum fuel temperature is expected to be around 240 deg C, giving an acceptable margin below the maximum allowed temperature of 300 deg C. In conclusion, this paper shows that the thermalhydraulic code CATHENA can accurately predict the thermal behavior AECL's air cooled spent fuel dry storage system. (author)

The use of HANDIDET reg-sign non-electric detonator assemblies to reduce blast-induced overpressure at AECL's Underground Research Laboratory

International Nuclear Information System (INIS)

Onagi, D.P.; Keith, S.G.; Kuzyk, G.W.

1996-01-01

A number of aspects of the Canadian concept for nuclear fuel waste disposal are being assessed by Atomic Energy of Canada Limited (AECL) in a series of experiments at its Underground Research Laboratory (URL) near Lac du Bonnet, Manitoba, Canada. One of the major objectives of the work being carried out at the URL is to develop and evaluate the methods and technology to ensure safe, permanent disposal of Canada's nuclear fuel waste. In 1994, AECL excavated access tunnels and a laboratory room for the Quarried Block Fracture Migration Experiment (QBFME) at the 240 Level of the URL. This facility will be used to study the transport of radionuclides in natural fractures in quarried blocks of granite under in-situ groundwater conditions. The experiment is being carried out under a cooperative agreement with the Japan Atomic Energy Research Institute. The excavation of the QBFME access tunnels and laboratory was carried out using controlled blasting techniques that minimized blast-induced overpressure which could have damaged or interrupted other ongoing experiments in the vicinity. The majority of the blasts used conventional long delay non-electric detonators but a number of blasts were carried out using HANDIDET 250/6000 non-electric long delay detonator assemblies and HTD reg-sign non-electric short delay trunkline detonator assemblies. The tunnel and laboratory excavation was monitored to determine the levels of blast-induced overpressure. This paper describes the blasting and monitoring results of the blasts using HANDIDET non-electric detonator assemblies and the effectiveness of these detonators in reducing blast-induced overpressure

Retrofit of AECL CAN6 seals into the Pickering shutdown cooling pumps

International Nuclear Information System (INIS)

Rhodes, D.; Metcalfe, R.; Brown, G.

1997-01-01

The existing mechanical seals in the shutdown cooling (SDC) pumps at the eight-unit Pickering Nuclear Generating Station have caused as least seven forced outages in the last fifteen years. The SDC pumps were originally intended to run only during shutdowns, mostly at low pressure, except for short periods during routine testing of SDC isolation valves while the plant is operating at full pressure to verify that the emergency core injection system is available. Unfortunately, in practice, some SDC pumps must be run much more frequently than this to prevent overheating or freezing of components in the system while the plant is at power. This more severe service has decreased seal lifetime from about 8000 running hours to about 3000 running hours. Rather than tackling the difficult task of eliminating on-power running of the pumps, Pickering decided to install a more robust seal design that could withstand this. Through the process of competitive tender, AECL's CAN6 seal was chosen. This seal has a successful history in similarly demanding conditions in boiling water reactors in the USA. To supplement this and demonstrate there would be no 'surprises,' a 2000-hour test program was conducted. Testing consisted of simulating all the expected conditions, plus some special tests under abnormal conditions. This has given assurance that the seal will operate reliably in the Pickering shutdown cooling pumps. (author)

Retrofit of AECL CAN6 seals into the Pickering shutdown cooling pumps

International Nuclear Information System (INIS)

Rhodes, D.; Metcalfe, R.; Brown, G.; Kiameh, P.; Burchett, P.

1997-01-01

The existing mechanical seals in the shutdown cooling (SDC) pumps at the eight-unit Pickering Nuclear Generating Station have caused at least seven forced outages in the last fifteen years. The SDC pumps were originally intended to run only during shutdowns, mostly at low pressure, except for short periods during routine testing of SDC isolation valves while the plant is operating at full pressure to verify that the emergency core injection system is available. Unfortunately, in practice, some SDC pumps must be run much more frequently than this to prevent overheating or freezing of components in the system while the plant is at power. This more severe service has decreased seal lifetime from about 8000 running hours to about 3000 running hours. Rather than tackling the difficult task of eliminating on-power running of the pumps, Pickering decided to install a more robust seal design that could withstand this. Through the process of competitive tender, AECL's CAN6 seal was chosen. This seal has a successful history in similarly demanding conditions in boiling water reactors in the USA. To supplement this and demonstrate there would be no 'surprises,' a 2000-hour test program was conducted. Testing consisted of simulating all the expected conditions, plus some special tests under abnormal conditions. This has given assurance that the seal will operate reliably in the Pickering shutdown cooling pumps. (author)

AECL'S approach to managing long term liabilities at Chalk River Laboratories. Annex II

International Nuclear Information System (INIS)

Audet, M.C.

2006-01-01

Chalk River Laboratories (CRL) is a large nuclear research and development/ industrial site operated by Atomic Energy of Canada Limited (AECL). Construction of the site started in 1944, and it now includes over 100 buildings/facilities operating in various nuclear fields. A well developed decommissioning programme exists at CRL, with progress being made on decommissioning older redundant buildings, in parallel with ongoing site operations and development. The decommissioning programme is predicated on the assumption that the current nuclear operations will continue over a 100 year operating period, but with a decline towards the end of the period. Although decommissioning and remediation work will be carried out throughout the operational period, residual levels of activity remaining in a few areas will require institutional control (IC) for an assumed period of 300 years. The intention is to complete all necessary active remediation work before the start of the IC period and thereafter rely only on passive means to reduce residual contamination to levels that do not require IC measures. The latter include environmental monitoring, active and passive controls to prevent intrusion, and management controls to prohibit access or development. A formal information and records management programme at CRL has been initiated. (author)

Simulating thermal behavior of AECL's spent fuel dry storage system with CATHENA

Energy Technology Data Exchange (ETDEWEB)

Sabourin, G. [Atomic Energy of Canada Limited, Montreal, PQ (Canada)

1998-07-01

This paper documents the comparisons between CATHENA predictions and temperature measurements taken at the Gentilly-2 NPP spent fuel dry storage facility and in a mock--up of a storage basket placed inside a storage cylinder. It also presents CATHENA temperature predictions related to the storage of spent fuel in MACSTOR modules as planned for Ignalina NPP, Lithuania. CATHENA has been chosen because it can simulate many noncondensable gases including air and helium, and because of its great flexibility in the representation of the MACSTOR module geometry. The results of the simulations show good agreement with the experimental measurements. The two comparisons indicate that CATHENA can be used to simulate heat transfer from the fuel to the external air circuit of the spent fuel dry storage system. For the Ignalina MACSTOR module, containing RBMK fuel having higher heat release than typical CANDU fuel, CATHENA predicts that the maximum fuel temperature is expected to be around 240 deg C, giving an acceptable margin below the maximum allowed temperature of 300 deg C. In conclusion, this paper shows that the thermalhydraulic code CATHENA can accurately predict the thermal behavior AECL's air cooled spent fuel dry storage system. (author)

Research on radionuclide migration under subsurface geochemical conditions. JAERI/AECL Phase II Collaborative Program Year 1 (joint research)

International Nuclear Information System (INIS)

1998-11-01

A radionuclide migration experiment program for fractured rocks was performed under the JAERI/AECL Phase-II Collaborative Program on research and development in radioactive waste management. The program started in the fiscal year 1993, as a five-year program consists of Quarried block radionuclide migration program, Speciation of long-lived radionuclides in groundwater, Isotopic hydrogeology and Groundwater flow model development. During the first year of the program (Program Year 1: March 18, 1994 - September 30, 1994), a plan was developed to take out granite blocks containing part of natural water-bearing fracture from the wall of the experimental gallery at the depth of 240 m, and literature reviews were done in the area of the speciation of long-lived radionuclides in groundwater, isotopic hydrogeology and the groundwater flow model development to proceed further work for the Program Year 2. (author)

The contribution of AECL CommercialProducts to nuclear medicine and radiation processing

International Nuclear Information System (INIS)

Beddoes, J.M.

1980-02-01

A review is given of the technology of the uses of radiation equipment and radioisotopes, in which field Canada has long been a world leader. AECL CommercialProducts has pioneered many of the most important applications. The development and sale of Co-60 radiation teletherapy units for cancer treatment is a familiar example of such an application, and CommercialProducts dominates the world market. Another such example is the marketing of Mo-99, which is produced in the reactors at Chalk River, and from which the short-lived daughter Tc-99 is eluted as required for use in in-vivo diagnosis. New products coming into use for this purpose include Tl-201, I-123, Ga-67 and In-111, all produced in the TRIUMF cyclotron in Vancouver, while I-125 continues to be in demand for in-vitro radioimmunoassays. Radioisotopes continue to play an important part in manufacturing, where their well-known uses include controlling thickness, contents, etc., in production, and industrial radiography. The application of large industrial irradiators for the sterilization of medical products is now a major world industry for which Commercial Products is the main manufacturer. Isotopes are also used in products such as smoke detectors. Isotopes continue to find extensive use as tracers, both in industrial applications and in animal and plant biology studies. Some more recent uses include pest control by the 'sterile male' technique and neutron activation and delayed neutron counting in uranium assay. (auth)

Comparison of MCNP and WIMS-AECL/RFSP calculations against critical heavy water experiments in ZED-2 with CANFLEX-LVRF and CANFLEX-LEU fuels

International Nuclear Information System (INIS)

Bromley, B. P.; Watts, D. G.; Pencer, J.; Zeller, M.; Dweiri, Y.

2009-01-01

This paper summarizes calculations of MCNP5 and WIMS-AECL/RFSP compared against measurements in coolant void substitution experiments in the ZED-2 critical facility with CANFLEX R-LEU/RU (Low Enriched Uranium, Recovered Uranium) reference fuels and CANFLEX-LVRF (Low Void Reactivity Fuel) test fuel, and H 2 O/air coolants. Both codes are tested for the prediction of the change in reactivity with complete voiding of all fuel channels, and that for a checkerboard voiding pattern. Understanding these phenomena is important for the ACR-1000 R reactor. Comparisons are also made for the prediction of the axial and radial neutron flux distributions, as measured by copper foil activation. The experimental data for these comparisons were obtained from critical mixed lattice / substitution experiments in AECL's ZED-2 critical facility using CANFLEX-LEU/RU and CANFLEX-LVRF fuel in a 24-cm square lattice pitch at 25 degrees C. Substitution analyses were performed to isolate the properties (buckling, bare critical lattice dimensions) of the CANFLEX-LVRF fuel. This data was then used to further test the lattice physics codes. These comparisons establish biases/uncertainties and errors in the calculation of k eff , coolant void reactivity, checkerboard coolant void reactivity, and flux distributions. Results show small to modest biases in void reactivity and very good agreement for flux distributions. The importance of boundary conditions and the modeling of un-moderated fuel in the critical experiments are demonstrated. This comparison study provides data that supports code validation and gives good confidence in the reactor physics tools used in the design and safety analysis of the ACR-1000 reactor. (authors)

Validation of Non-Invasive Waste Assay System (Gamma Box Counter) Performance at AECL Whiteshell Laboratories - 13136

International Nuclear Information System (INIS)

Attas, E.M.; Bialas, E.; Rhodes, M.J.

2013-01-01

Low-level radioactive waste (LLW) in solid form, resulting from decommissioning and operations activities at AECL's Whiteshell Laboratories (WL), is packaged in B-25 and B-1000 standard waste containers and characterized before it is shipped to an on-site interim storage facility, pending AECL decisions on long term management of its LLW. Assay of the waste packages before shipment contributes to an inventory of the interim storage facility and provides data to support acceptance at a future repository. A key characterization step is a gamma spectrometric measurement carried out under standard conditions using an automated, multi-detector Waste Assay System (WAS), purchased from Antech Corporation. A combination of ORTEC gamma acquisition software and custom software is used in this system to incorporate multiple measurements from two collimated high-resolution detectors. The software corrects the intensities of the gamma spectral lines for geometry and attenuation, and generates a table of calculated activities or limits of detection for a user-defined list of radioisotopes that may potentially be present. Validation of WAS performance was a prerequisite to routine operation. Documentation of the validation process provides assurance of the quality of the results produced, which may be needed one or two decades after they were generated. Aspects of the validation included setting up a quality control routine, measurements of standard point sources in reproducible positions, study of the gamma background, optimization of user-selectable software parameters, investigation of the effect of non-uniform distribution of materials and radionuclides, and comparison of results with measurements made using other gamma detector systems designed to assay bulk materials. The following key components of the validation process have been established. A daily quality control routine has been instituted, to verify stability of the gamma detector operation and the background levels

Current status of the waste identification program at AECL's Chalk River Laboratories

International Nuclear Information System (INIS)

Csullog, G.W.; Edwards, N.W.; TerHuurne, M.A.

1998-01-01

The management of routine operating waste by Waste Management and Decommissioning (WM and D) at Atomic Energy of Canada Limited's (AECL) Chalk River Laboratories (CRL) is supported by the Waste Identification (WI) Program. The principal purpose of the WI Program is to minimize the cost and the effort associated with waste characterization and waste tracking, which are needed to optimize waste handling, storage and disposal. The major steps in the WI Program are: (1) identify and characterize the processes that generate the routine radioactive wastes accepted by WM and D - radioisotope production, radioisotope use, reactor operation, fuel fabrication, et cetera (2) identify and characterize the routine blocks of waste generated by each process or activity - the initial characterization is based on inference (process knowledge) (3) prepare customized, template data sheets for each routine waste block - templates contain information such as package type, waste material, waste type, solidifying agent, the average non-radiological contaminant inventory, the average radiological contaminant inventory, and the waste class (4) ensure generators 'use the right piece of paper with the right waste' when they transfer waste to WM and D - that is they use the correct template data sheets to transfer routine wastes, by: identifying and marking waste collection points in the generator's facility; ensuring that generators implement effective waste collection/segregation procedures; implementing standard procedures to transfer waste to WM and D; and, auditing waste collection and segregation within a generator's facility (5) determine any additional waste block characterization requirements (is anything needed beyond the original characterization by process knowledge?) This paper describes the WI Program, it provides an example of its implementation, and it summarizes the current status of its implementation for both CRL and non-CRL waste generators. (author)

AECL'S (Atomic Energy Canada Limited) R and D program in health and environmental sciences

International Nuclear Information System (INIS)

Osborne, R.V.

1996-01-01

Radiological protection is a fundamental requirement in any nuclear technology endeavour. It is also an area where public concerns are often expressed. If protection is inadequate, or is believed to be so, or if concerns are not addressed, the beneficial application of nuclear technologies is inhibited. Historically. AECL, as the driver of nuclear technology in Canada, has ensured that the growing Canadian nuclear industry and other users of the technology have a sound technical base to support, explain and confirm all aspects of radiological protection. Meeting this need has meant developing and maintaining R%D programs in environmental sciences, health physics, radiation biology, and radiological health matters in general. The programs undertaken encompass the links from sources of radiation exposure and radionuclides to potential impact on biota and on human health. The behaviours of radionuclides released to the atmosphere, surface waters, or ground waters are examined and described quantitatively to enable predictions to be made of the radiation doses received in different parts of the biosphere and by people. Radiation properties and human physiological and biokinetic processes are studied to provide quantitative links from exposure to radiation dose in tissues and organs. Biological processes involved in determining whether there are any consequences to health from small absorbed doses are identified at levels ranging from molecular level, to cells in tissue culture, and animals. Throughout the programs, required measurement technologies are developed. The results of the R%D have contributed to radiological protection programs being soundly based and, equally important, are being seen to be soundly based. (author)

WIMS-AECL/RFSP code validation of reactivity calculations following a long shutdown using the simple-cell history-based method

International Nuclear Information System (INIS)

Ardeshiri, F.; Donnelly, J.V.; Arsenault, B.

1998-01-01

The purpose of this analysis is to validate the Reactor Fuelling Simulation Program (RFSP) using the simple-cell model (SCM) history-based method in a startup simulation following a reactor shutdown period. This study is part of the validation work for history-based calculations, using the WIMS-AECL code with the ENDF/B-V library, and the SCM linked to the RFSP code. In this work, the RFSP code with the SCM history-based method was used to track a 1-year period of the Point Lepreau reactor operating history, that included a 12-day reactor shutdown and subsequent startup. Measured boron and gadolinium concentrations were used in the RFSP simulations, and the predicted values of core reactivity were compared to the reference (pre-shutdown) value. The discrepancies in core reactivity are shown to be better than ±2 milli-k at any time, and better than about ±0.5 milli-k towards the end of the startup transient. The results of this analysis also show that the calculated maximum channel and bundle powers are within an acceptable range during both the core-follow and the reactor startup simulations. (author)

List of publications 1986-1987

International Nuclear Information System (INIS)

1988-03-01

This list includes all the scientific and technical publications of Atomic Energy of Canada Limited - reports, reprints of journal articles, and translations - issued from 1986 April to 1987 December. Together with the earlier cumulative lists (AECL-5000, AECL-5001, AECL-5002, AECL--5003, AECL--5004, AECL--5005), it provides a complete catalogue of publications in the AECL-series. In the future, lists will be produced at twelve month intervals. The titles and other bibliographic information are arranged in several categories, each devoted to a broad subject area. In addition, each document is identified with an AECL number (for example, AECL-12345) which should be used in ordering reports and making enquiries

Variations in the response of AECL random coil seals as a function of the angular position of the probe

International Nuclear Information System (INIS)

Silk, M.G.

1986-04-01

The AECL random coil seal is to be used as a Nuclear Safeguards seal to deter and detect tampering with nuclear material in store. To be effective the ultrasonic signature from the seal must remain constant and be different from that of other seals. Angular variations in the ultrasonic response from certain seals have, however, been observed and the programme of study reported here has been carried out in order to clarify the source of this variation. It is shown that the variation observed may most probably be attributed to the ultrasonic probes used in the investigation and, in particular, to deviation of the probe beam from circularity. However it is probable that the angle of the beam with respect to the probe case (squint) is also a contributory factor. In addition, to reduce the degree of angular variation it is important to exclude air bubbles and to ensure that the coil is placed as centrally in the beam as possible. It is anticipated that the exclusion of air bubbles will be easier in the field than in the laboratory studies. The need to place the seal reasonably centrally with respect to the beam places some minor limits on the coil design and also makes it essential that the probe fits closely into its holder in the seal as any slackness may give rise to signature variations. (author)

Past and future fracturing in AECL Research areas in the superior province of the Canadian Precambrian Shield, with emphasis on the Lac du Bonnet Batholith

International Nuclear Information System (INIS)

Brown, A.; Everitt, R.A.; Martin, C.D.; Davison, C.C.

1995-10-01

The likelihood that future fracturing, arising from geologic causes, could occur in the vicinity of a nuclear fuel waste repository in plutonic rock of the Canadian Precambrian Shield, is examined. The report discusses the possible causes of fracturing (both past and future) in Shield rocks. The report then examines case histories of fracture formation in Precambrian plutonic rocks in AECL's Research Areas, especially the history of the Lac du Bonnet Batholith, in the Whiteshell Area, Manitoba. Initially, fractures can be introduced into intrusive plutonic rocks during crystallization and cooling of an intrusive magma. These fractures are found at all size scales; as late residual magma dyking, hydraulic fracturing by retrograde boiling off of hydrothermal fluids, and, in some cases, through local differential cooling. Subsequent fracturing is largely caused by changes in environmental temperature and stress field, rather than by alteration of the material behaviour of the rock. Pluton emplacement during orogeny is commonly accompanied by uplift and erosional exhumation, altering both the tectonic and the lithostatic stresses, the rock temperature gradient and the pore fluid characteristics

Prospecting for success in the American market

International Nuclear Information System (INIS)

Thomas, Ron.

1992-01-01

AECL Technologies is a US subsidiary of AECL originally set up to obtain licensing of CANDU reactors in the US, as well as to market technology. AECL Technologies has been successful in marketing digital control technology and software development, and also design and consulting services. Dry storage of spent fuel represents a large future opportunity. AECL hopes to sell CANDU reactors in the USA after the turn of the century. AECL Technologies did about $4.2 million worth of business in 1991

Annual report 1993-1994

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-12-31

Established in 1952 as a Crown corporation, AECL reports to Parliament through the Ministry of Natural Resources. Its mandate is to undertake research into nuclear energy and prepare and develop its commercial applications. AECL`s mission is to secure the maximum economic benefit for Canada from CANDU technology and associated research and development - the CANDU business. AECL`s accomplishments include the development of products and services which, through diligent marketing efforts, are now in use worldwide. The corporation`s world-renowned flagship product, the CANDU reactor, currently satisfies 16% of Canada`s electricity requirements and is a key component of the energy programs in five other countries. AECL`s vision over the next 20 years is to: be a world-leading supplier of full-scope nuclear power capability; be a long-term business with at least a quarter share of the emerging global market for the next generation of nuclear power plants; have a comprehensive ongoing research program to: maintain at the highest levels the performance and safety of operating CANDU plants; advance the CANDU technology and the science that underlies it; develop knowledge on the health effects of radiation and on the safety and environmental impacts of nuclear reactor operation. AECL currently employees 4000 people. With headquarters in Ottawa, AECL operates two research laboratories, one in Ontario and one in Manitoba, and engineering and design offices in Ontario, Quebec, Saskatchewan, and New Brunswick, as well as offices abroad. AECL has a subsidiary, AECL Technologies Inc., situated in Washington, DC.

Annual report 1994-1995

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-12-31

Established in 1952 as a Crown corporation, AECL reports to Parliament through the Ministry of Natural Resources. Its mandate is to undertake research into nuclear energy and prepare and develop its commercial applications. AECL`s objective is to secure the maximum economic benefit for Canada from CANDU technology and the associated research and development. AECL`s accomplishments include the development of products and services which are now in use worldwide. The corporation`s world-renowned flagship product, the CANDU reactor, supplies almost one-fifth of Canada`s electricity requirements and is an important component of the energy programs in five other countries. Building upon these achievements, AECL continues to consolidate its position as a world-leading supplies of full-scope nuclear power capabilities with expectations to capture a substantial share of the emerging global nuclear power market. The immediate goals are to meet the customers` requirements in the delivery of current projects, to ensure that operating CANDU stations continue to maintain a high level of performance, to secure further CANDU sales, to garner increased revenues from further commercialization of CANDU technology, and to serve the Government of Canada`s nuclear policy initiatives. AECL currently employs 3900 people in a variety of locations, including two major research laboratories located in Ontario and Manitoba, as well as business, engineering and design offices in Ottawa, Toronto, Montreal, Saskatoon and Fredericton. AECL has two subsidiaries, AECL Technologies Inc., in Washington, DC, and AECL Technologies B.V., in the Hague, Netherlands, and maintains a significant presence in South Korea, as well as several smaller offices in other countries.

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

AECL's use of FMEA and OPEX for field service tooling and process development, implementation and improvement: a model for the future

International Nuclear Information System (INIS)

Cox, E.; Dam, R.F.; Wilson, E.

2008-01-01

Failure Modes and Effects Analysis (FMEA) is a systematic and rigorous process applied to new or complex systems to predict system failures and assist with the development of mitigating strategies. The process is especially beneficial when applied to higher-risk applications such as nuclear systems. FMEA may be used for design verification and maintenance program development. For field service tooling, FMEA is complimented well by operating experience (OPEX) and continuous improvement initiatives. FMEA is generally conducted while developing systems and processes to ensure safe and successful implementation, while OPEX is fed back into the system design and operation to improve those systems and processes for subsequent field applications. This paper will explore these techniques as they have been applied to AECL's CANDUclean system. The portable CANDUclean system is employed to mechanically clean the inside of steam generator (SG) tubes in CANDU nuclear power plants. During normal plant operation, the steam generator tubes in the heat transport system develop a build-up of magnetite on their internal diameter, which decreases heat transfer efficiency, impedes SG maintenance activities and increases the radiation fields in and around the boilers. As part of a regular plant aging management routine, the CANDUclean system is used to remove the magnetite layers. The nature of this work includes risks to personnel safety, however by continually applying FMEA and other improvement initiatives, safety and system effectiveness are maximized. This paper will provide an overview of the integrated continuous improvement approach applied to the CANDUclean system and consider the value of strategies when applied to field service tooling and CANDU systems. (author)

Radioactive waste repository study

International Nuclear Information System (INIS)

1978-11-01

This is the third part of a report of a preliminary study for AECL. It summarizes the topics considered in reports AECL-6188-1 and AECL-6188-2 as requirements for an undergpound repository for disposal of wastes produced by the Canadian Nuclear Fuel Program. (author)

Annual report 1993-1994

International Nuclear Information System (INIS)

1994-01-01

Established in 1952 as a Crown corporation, AECL reports to Parliament through the Ministry of Natural Resources. Its mandate is to undertake research into nuclear energy and prepare and develop its commercial applications. AECL's mission is to secure the maximum economic benefit for Canada from CANDU technology and associated research and development - the CANDU business. AECL's accomplishments include the development of products and services which, through diligent marketing efforts, are now in use worldwide. The corporation's world-renowned flagship product, the CANDU reactor, currently satisfies 16% of Canada's electricity requirements and is a key component of the energy programs in five other countries. AECL's vision over the next 20 years is to: be a world-leading supplier of full-scope nuclear power capability; be a long-term business with at least a quarter share of the emerging global market for the next generation of nuclear power plants; have a comprehensive ongoing research program to: maintain at the highest levels the performance and safety of operating CANDU plants; advance the CANDU technology and the science that underlies it; develop knowledge on the health effects of radiation and on the safety and environmental impacts of nuclear reactor operation. AECL currently employees 4000 people. With headquarters in Ottawa, AECL operates two research laboratories, one in Ontario and one in Manitoba, and engineering and design offices in Ontario, Quebec, Saskatchewan, and New Brunswick, as well as offices abroad. AECL has a subsidiary, AECL Technologies Inc., situated in Washington, DC

An accident involving transport of radioactive materials, Canada 1994 March

Energy Technology Data Exchange (ETDEWEB)

Keeling, F; Dunn, L E.G. [Atomic Energy of Canada Ltd., Chalk River, ON (Canada)

1996-12-31

AECL-Chalk River Laboratories (CRL) located at Chalk River, Ontario, routinely ships radioisotopes in bulk to Nordion International Inc. in Kanata, Ontario. On 1994 March 22, an AECL vehicle carrying three packages containing radioisotopes collided with a tractor trailer carrying steel, approximately 15 km east of the Chalk River Laboratories. The AECL-CRL emergency response plan was activated. A series of post-accident meetings were held to evaluate the effectiveness of the plan and to address any identified deficiencies. AECL-CRL is continuing to work towards addressing the identified deficiencies. (author). 2 figs.

An accident involving transport of radioactive materials, Canada 1994 March

International Nuclear Information System (INIS)

Keeling, F.; Dunn, L.E.G.

1995-01-01

AECL-Chalk River Laboratories (CRL) located at Chalk River, Ontario, routinely ships radioisotopes in bulk to Nordion International Inc. in Kanata, Ontario. On 1994 March 22, an AECL vehicle carrying three packages containing radioisotopes collided with a tractor trailer carrying steel, approximately 15 km east of the Chalk River Laboratories. The AECL-CRL emergency response plan was activated. A series of post-accident meetings were held to evaluate the effectiveness of the plan and to address any identified deficiencies. AECL-CRL is continuing to work towards addressing the identified deficiencies. (author). 2 figs

Annual report 1994-1995

International Nuclear Information System (INIS)

1995-01-01

Established in 1952 as a Crown corporation, AECL reports to Parliament through the Ministry of Natural Resources. Its mandate is to undertake research into nuclear energy and prepare and develop its commercial applications. AECL's objective is to secure the maximum economic benefit for Canada from CANDU technology and the associated research and development. AECL's accomplishments include the development of products and services which are now in use worldwide. The corporation's world-renowned flagship product, the CANDU reactor, supplies almost one-fifth of Canada's electricity requirements and is an important component of the energy programs in five other countries. Building upon these achievements, AECL continues to consolidate its position as a world-leading supplies of full-scope nuclear power capabilities with expectations to capture a substantial share of the emerging global nuclear power market. The immediate goals are to meet the customers' requirements in the delivery of current projects, to ensure that operating CANDU stations continue to maintain a high level of performance, to secure further CANDU sales, to garner increased revenues from further commercialization of CANDU technology, and to serve the Government of Canada's nuclear policy initiatives. AECL currently employs 3900 people in a variety of locations, including two major research laboratories located in Ontario and Manitoba, as well as business, engineering and design offices in Ottawa, Toronto, Montreal, Saskatoon and Fredericton. AECL has two subsidiaries, AECL Technologies Inc., in Washington, DC, and AECL Technologies B.V., in the Hague, Netherlands, and maintains a significant presence in South Korea, as well as several smaller offices in other countries

A compilation of subsurface hydrogeologic data

International Nuclear Information System (INIS)

1986-03-01

This volume contains a continuation of the fracture data for the research sites discussed in Volume 1 which have been studied in sufficient detail to allow for analysis. The sites discussed in this volume are the following: Climax Granite Nevada Test Site; OCRD Room, Colorado School of Mines; Savannah River Plant, Aiken, South Carolina; Oracle, Arizona; Basalt Waste Isolation Project (BWIP), Hanford, Washington Underground Research Laboratory, AECL, Canada; Atikokan Research Area, AECL; Chalk River Research Area, AECL; Whiteshell Research Area, AECL. Other sources of information have been included where sufficient site specific geologic and hydrogeologic information is provided

Rock fracture dynamics research at AECL's Underground Research Laboratory: applications to geological disposal of radioactive waste

Energy Technology Data Exchange (ETDEWEB)

Young, R.P. [Univ. of Toronto, Toronto, ON (Canada); Haycox, J.R. [Applied Seismology Consultants Limited, Shrewsbury, Shropshire (United Kingdom); Martino, J. [Atomic Energy of Canada Limited, Pinawa, MB (Canada)

2011-07-01

Studies of rock fracture dynamics at AECL's Underground Research Laboratory (URL) have helped to provide a fundamental understanding of how crystalline rock responds to stresses induced from excavation, pressurization and temperature changes. The data acquired continue to provide insights into how a facility for the future geological disposal of radioactive waste could be engineered. Research into microseismic (MS), acoustic emission (AE), and ultrasonic velocity measurements has been performed on the full-scale sealed, pressurized, and heated horizontal elliptical tunnel at the Tunnel Sealing Experiment (TSX). The continuous monitoring of the experiment for 8 years provides a unique dataset for the understanding of the medium-term performance of an engineered disposal facility. This paper summarizes the results, interpretations and key findings of the experiment paying particular focus to the heating and cooling/depressurization of the chamber. Initial drilling of the tunnel and bulkheads causes microfracturing around the tunnel, mapped by MS and AEs, and is used as a benchmark for fracturing representing the excavated damaged zone (EDZ). There is no further extension to the volume during pressurization or heating of the tunnel suggesting an increase in crack density and coalescence of cracks rather than extension into unfractured rock. The dominant structure within the seismic cloud has been investigated using a statistical approach applying the three-point method. MS events in the roof exhibit a dominant pattern of sub-horizontal and shallow-dipping well defined planar features, but during cooling and depressurization a 45 degree dip normal to the tunnel axis is observed, which may be caused by movement in the rock-concrete interface due to differential cooling of the bulkhead and host rock. Cooling and depressurization of the TSX have not led to a significant increase in the number of MS or AE events. Ultrasonic results suggest the rock gets even stiffer

The effect of proposed crush tests on transport containers

International Nuclear Information System (INIS)

1984-09-01

Crush tests were performed on two AECL F112 packaging specimens, two simulated AECL-CRNL 4H packaging specimens, and on empty steel drums. The 9 m drop test was carried out on two simulated AECL-CRNL 4H packaging specimens for comparison with the effects of the crush test. The tests were filmed using high speed photography and 35mm still photographs

Factors controlling the population size of microbes in groundwater from AECL's Underground Research Laboratory

Energy Technology Data Exchange (ETDEWEB)

Stroes-Gascoyne, S.; Hamon, C. [Atomic Energy of Canada Limited, Whiteshell Labs., Pinawa, Manitoba (Canada); Mills, K. [University of Saskatoon, Saskatoon, SK (Canada); Rana, S.; Vaidyanathan, S. [Deep River Science Academy, Whiteshell Campus Summer 1997, Pinawa, Manitoba (Canada)

2001-01-01

Microbial populations in groundwaters from AECL's Underground Research Laboratory (URL) range from 10{sup 3} to 10{sup 5} cells/mL. Based on the total dissolved organic carbon (DOC), nitrate and phosphate content of these waters, populations of about 10{sup 5} to 10{sup 7} cells/mL should be possible. Upon storage of groundwater samples, total cell counts generally increase and viable cell counts always increase. A study was undertaken to determine what controls the in situ microbial population size in groundwater and what causes this population to grow upon sampling. Fresh URL groundwater was filter-sterilized, inoculated with small quantities of the unaltered water and incubated in the absence and presence of added nutrients (nitrate, phosphate and glucose). Unfiltered groundwater and R2A growth medium inoculated with unaltered groundwater, were also incubated. Microbial changes over time were followed by total and viable (on R2A medium) cell counts. Results showed that in the absence of any nutrient addition, populations grew to between 5 x 10{sup 5} to 4 x 10{sup 6} cells/mL, regardless of the initial size of the population ({approx}10{sup 1} to 10{sup 4} cells/mL), suggesting that nutrients for growth were available in the unamended groundwater. It was hypothesized that the original groundwater population was in 'equilibrium' with the underground environment, which likely included a large population of sessile cells in biofilms on fracture surfaces. Sampling of the groundwater removed the large demand on nutrient supplies by the sessile population which subsequently allowed the planktonic population to grow to a new 'equilibrium' with the available nutrients in the sample bottles. Addition of single nutrients (C, N or P) did not increase cell numbers, suggesting that more than one nutrient is limiting growth. Glucose was used very efficiently aerobically in the presence of both added N and P, but somewhat less under anaerobic

Prototype scale demonstration of CECE detritiation

International Nuclear Information System (INIS)

Sadhankar Ramesh; Cobanoglu, Macit

2004-01-01

AECL has developed and demonstrated the Combined Electrolysis and Catalytic Exchange (CECE) Process for detritiation of heavy water. Although CECE has been the subject of pilot-scale demonstrations by various organizations, AECL is the first to demonstrate this technology in an industrial prototype plant. AECL designed, built and operated a CECE demonstration facility under CAN/CSA N286 Quality Assurance Program. The facility was licensed by the Canadian nuclear regulator. This was a two-fold demonstration of the CECE technology - for upgrading (removal of light water) and for detritiation of heavy water. In 1998 June, AECL began operating the facility in upgrading mode. The design feed rate ranged up to 25 Mg/a for 95 mol% D 2 O feed water. After 18 months of operation in upgrading mode, the facility was reconfigured and operated for an additional 9 months from 2000 August in detritiation mode. Design capacity for detritiation was 5 Mg/a with a detritiation factor (DF) of 100. However, significantly higher DFs, up to 56 000, were demonstrated. Highlights of the detritiation demonstration were: Proven robustness of AECL's proprietary wetproofed catalyst for Liquid Phase Catalytic Exchange; Demonstration of a trickle-bed-recombiner for stoichiometric combination of deuterium and oxygen; Demonstration of electrolysis of highly tritiated heavy water; High process availability and controllability was demonstrated by a long interrupted run; Low emissions; Demonstration of high DF - up to 56 000 - a significant advantage of the CECE process over other approaches to detritiation; Validation of AECL's simulation code for the CECE process over a range of DFs from 100 to 50 000. Apart from the technology, AECL has expertise in all aspects of setting up a new detritiation facility including design, engineering, safety assessment, licensing support, project management and training. AECL is also the engineering and design contractor for a tritium removal facility that is under

A compilation of subsurface hydrogeologic data

International Nuclear Information System (INIS)

1986-03-01

This volume contains the permeability data for the research sites discussed in Volume 1 which have been studied in sufficient detail to allow for analysis. These sites are the following: Stripa Mine, Sweden; Finnsjon, Kamlunge, Fjallveden, Gidea, Svartboberget, Sweden; Olkiluoto, Loviisa, Lavia, Finland; Climax Granite Nevada Test Site; OCRD Room, Colorado School of Mines; Savannah River Plant, Aiken, South Carolina; Oracle, Arizona; Basalt Waste Isolation Project (BWIP), Hanford, Washington; Underground Research Laboratory, AECL, Canada; Atikokan Research Area, AECL; Chalk River Research Area, AECL; Whiteshell Research Area, AECL. Other sources of information have been included where sufficient site specific geologic and hydrogeologic information is provided

Atomic Energy of Canada Limited annual report 1989-1990

International Nuclear Information System (INIS)

1990-01-01

In 1990, after a comprehensive industry review, the Canadian government announced that steps would be taken to revitalize the nuclear industry. Canada's nuclear utilities made a commitment to bear a large share of the cost of nuclear research and development. Atomic Energy of Canada Limited (AECL) reported its first financial loss in twelve years, as anticipated at the start of the year. Four of the 20 CANDU reactors operating worldwide were in the top ten based on lifetime performance. By year-end one foreign and two domestic utilities had announced their intention to build more CANDU units. The federal government has agreed to stabilize AECL's research funding at 1989-90 levels ($31.5 million above levels planned in 1985), has authorized AECL to negotiate with New Brunswick to build Point Lepreau-2 as the prototype for the CANDU-3 reactor, and has allowed the restructuring of AECL so utility and private sector investors can become equity partners in AECL CANDU

Annual report 1997-1998

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-07-01

Atomic Energy of Canada Limited (AECL) was established in 1952 as a Crown Corporation and reports to parliament through the Minister of Natural Resources. As an annual report, financial statements are an integral element, financial analysis and review are also ongoing. AECL is very active in marketing the science culture which is key to public understanding and acceptance of the nuclear industry. In commercial operations, the CANDU is still the flagship to be marketed in many countries. AECL is the main producer of medical isotopes for the global market. AECL and MDS Nordion signed agreements to secure the ongoing supply of isotopes and to build and operate two MAPLE reactors at the Chalk River site. Activities at AECL are focused on improved economics, further enhanced safety systems and fuel cycle flexibility in the research and product development programs. Waste management and nuclear sciences i e. health and environmental sciences are ongoing studies. Site refurbishment focuses on replacing and refurbishing major facilities to meet business needs.

Annual report 1997-1998

International Nuclear Information System (INIS)

1998-01-01

Atomic Energy of Canada Limited (AECL) was established in 1952 as a Crown Corporation and reports to parliament through the Minister of Natural Resources. As an annual report, financial statements are an integral element, financial analysis and review are also ongoing. AECL is very active in marketing the science culture which is key to public understanding and acceptance of the nuclear industry. In commercial operations, the CANDU is still the flagship to be marketed in many countries. AECL is the main producer of medical isotopes for the global market. AECL and MDS Nordion signed agreements to secure the ongoing supply of isotopes and to build and operate two MAPLE reactors at the Chalk River site. Activities at AECL are focused on improved economics, further enhanced safety systems and fuel cycle flexibility in the research and product development programs. Waste management and nuclear sciences i e. health and environmental sciences are ongoing studies. Site refurbishment focuses on replacing and refurbishing major facilities to meet business needs

Progress report, physics and health sciences, physics section, 1986 January 01 - June 30

International Nuclear Information System (INIS)

1986-08-01

The two progress reports PR-PHS-P-1 (AECL-9262) and PR-PHS-HS-1 (AECL-9263) are continuations of the former series in Physics, PR-P-142, (AECL-9103) and in Health Sciences, PH-HS-20 (AECL-9102). The new series have been initiated to take into account the reorganization of the Research Company effective 1986 February 1. It is intended to issue the reports semi-annually on June 30 and December 31 covering the previous six months. The new series cover the same areas as before except that the Accelerator Physics Branch and the Mathematics and Computation Branch activities are no longer included in Physics, and the activities of the Medical Biophysics Branch at Whiteshell are now included in Health Sciences. The latest progress report on the Medical Biophysics work appeared in the WNRE report PR-WHS-73. This report (AECL-9262) covers the research, business and commercial activities of Nuclear Physics, TASCC Operations, Neutron and Solid State Physics, Theoretical Physics and the Fusion Office

List of publications: April 1982 to March 1983

International Nuclear Information System (INIS)

1983-06-01

All scientific and technical publications of Atomic Energy of Canada Ltd. issued from April 1982 to March 1983 are listed in ten broad categories. Each entry includes the AECL report series number, author(s), title, journal citation (if a reprint), pagination, issue date, and price. There are indexes by AECL and other report numbers, and authors. Directions for ordering AECL reports and a list of depository libraries are appended

Managing wastes from the atomic age and into the future: programs, plans and challenges

International Nuclear Information System (INIS)

Miller, J.M.

2011-01-01

Various types of waste are generated at Atomic Energy of Canada Limited (AECL) nuclear sites from diversified operations, including research reactor operations, radioisotope production, hot cell operations, nuclear fuel fabrication, research and development activities, facility decommissioning, environmental restoration, etc. AECL is responsible for the safe storage and long-term management of waste generated by Chalk River Laboratories (CRL), Whiteshell Laboratories (WL) and the three partially decommissioned prototype reactors, as well as for the radioactive waste received from off-site waste generators on a fee-for-service basis. As the home for the first nuclear reactor in Canada and nuclear research facilities, CRL has been a pioneer in the management of nuclear waste. Since the dawn of the nuclear era in the 1940s, CRL's waste management facilities have evolved from storage in simple sand trenches to below-ground concrete storage, to above-ground facilities offering multiple barriers of containment. To continuously improve the waste management at AECL, a formal Waste Management Program has been introduced. An important component of this Program is a focus on waste reduction and appropriate waste characterization to ensure wastes are being handled, stored and/or disposed in the most cost-effective manner. In 2006, AECL began implementing the Government of Canada-funded Nuclear Legacy Liabilities Program (NLLP) to deal with nuclear legacy liabilities at AECL sites. Approximately 200,000 to 300,000 cubic metres of waste from earlier operations at AECL requires management through the NLLP, with a yearly increase of several thousand cubic metres. Several of the NLLP projects currently underway are focused on improving the robustness of earlier management practices, as older facilities reach the end of their design life. An important element of the NLLP is the development of an Integrated Waste Plan to ensure optimal selection of enabling facilities and their

Value added services to CANDU plants

International Nuclear Information System (INIS)

Kakaria, B.K.

2003-01-01

Over the last decade or so, nuclear power plants, just like other types of electricity generating plants, have been facing a number of challenges. Depending on the operating environment of the utility, these challenges are forcing plant owners to examine all facets of the operating costs. Privatization, deregulation and economics of alternative electricity generation methods are exerting enormous pressure on nuclear power plants to streamline costs and improve their operational performance. CANDU reactors are no exception to these forces and face similar pressures. In particular, operating plants that are contemplating plant life extensions are being required to clearly demonstrate the economics of continued operation over other forms of power generation available to the utility. Improvement of capacity factors has the effect of increasing the revenues from the plant and as these revenues increase, the fixed portion of the plant costs including OM and A costs become a smaller percentage of the total revenues. Similar results can be achieved by aiming to reduce the plant OM and A costs. In reality, most well-planned intervention schemes directed at reducing OM and A costs tend to also increase the plant availability. Following plant turnover after commissioning, AECL has been supporting the CANDU owners and utilities with an assortment of products and services dealing with plant operations and outage management issues. AECL has taken the lead in arranging specialized resources, products and services by teaming with other complementary organizations to provide a complete suite of services. Recent examples of such support to operating CANDU plants will be described in the paper. AECL is responding to this changing business environment in two important ways. First, AECL is changing from simply providing a service to its clients towards providing value, something much more important. To this end, AECL is looking to other organizations to form alliances, partnerships and

Progress reports on SCWR-related development projects from Chinese universities for FY2008-2009

International Nuclear Information System (INIS)

Leung, L.K.H.

2010-02-01

Canada is participating in the international cooperative forum on system research for two designs (supercritical water-cooled reactor, SCWR, and Very High Temperature Reactor, VHTR) of the Gen-IV nuclear reactor. The forum is referred to as the Generation-IV International Forum (or GIF). The Canadian effort focuses mainly on the SCWR. Among various GIF participants, Canada is the leader of this design and has interest mainly on the pressure-tube type reactor, which is a natural extension of the existing CANDU reactor. Several critical research areas (such as material, chemistry, thermalhydraulics, instability, critical flow, etc.) have been identified in the system-research plan for supporting the SCWR design. Collaborative projects have been established between AECL and universities in China to expedite the CANDU SCWR design. These projects focus on research areas beyond the current scope of the AECL and the NSERC/NRCan/AECL collaborative research and development (CRD) project. AECL supports these projects directly and is contributing (in-kind) the results and findings to the Canadian national program. The collaboration between AECL and Chinese universities began in 2007 July. Most projects cover the duration of three years. The Chinese universities submit their annual progress reports each year prior to the project renewal. The objective of this report is to summarize the progress on collaborative projects between AECL and Chinese universities (namely the Tsinghua University, Shanghai Jiaotong University, and Xi'an Jiaotong University) over the duration of 2008 July to 2009 June. (author)

A study on the health of the employees of Atomic Energy of Canada Limited. III

International Nuclear Information System (INIS)

Johnston, L.H.; Werner, M.M.

1987-01-01

The Atomic Energy of Canada Ltd (AECL) Employee Health Study commenced in 1980 July following the issue of a Company-Wide General Notice of 1980 April by the President of Atomic Energy of Canada Limited, Mr. James Donnelly. The study was set up to determine the causes of death of the AECL study population as compared to a similar group in the general population and to determine if there is a relationship between cause of death and occupational exposure to ionising radiation. Previous AECL reports have outlined how the study has been set up and implemented. The purpose of this report is to describe the reasons for and the methods of upgrading the data base for the AECL Employee Health Study. Some description of procedures used during the first linkage and recommendations for future linkages are included

A compilation of subsurface hydrogeologic data

International Nuclear Information System (INIS)

1986-03-01

This volume contains the storage coefficient, porosity, compressibility and fracture data for the research sites discussed in Volume 1 which have been studied in sufficient detail to allow for analysis. These sites are the following: Stripa Mine, Sweden; Finnsjon, Kamlunge, Fjallveden, Gidea, Svartboberget, Sweden; Olkiluoto, Loviisa, Lavia, Finland; Climax Granite Nevada Test Site; OCRD Room, Colorado School of Mines; Savannah River Plant, Aiken, South Carolina; Oracle, Arizona; Basalt Waste Isolation Project (BWIP), Hanford, Washington; Underground Research Laboratory, AECL, Canada; Atikokan Research Area, AECL; Chalk River Research Area, AECL; Whiteshell Research Area, AECL. Other sources of information have been included where sufficient site specific geologic and hydrogeologic information is provided. The fracture data for the first three of the sites listed above are contained in this volume. The fracture data for the remaining research research sites are discussed in Volume 4

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)

Integrated plant information technology design support functionality

International Nuclear Information System (INIS)

Kim, Yeon Seung; Kim, Dae Jin; Barber, P. W.; Goland, D.

1996-06-01

This technical report was written as a result of Integrated Plant Information System (IPIS) feasibility study on CANDU 9 project which had been carried out from January, 1994 to March, 1994 at AECL (Atomic Energy Canada Limited) in Canada. From 1987, AECL had done endeavour to change engineering work process from paper based work process to computer based work process through CANDU 3 project. Even though AECL had a lot of good results form computerizing the Process Engineering, Instrumentation Control and Electrical Engineering, Mechanical Engineering, Computer Aided Design and Drafting, and Document Management System, but there remains the problem of information isolation and integration. On this feasibility study, IPIS design support functionality guideline was suggested by evaluating current AECL CAE tools, analyzing computer aided engineering task and work flow, investigating request for implementing integrated computer aided engineering and describing Korean request for future CANDU design including CANDU 9. 6 figs. (Author)

Integrated plant information technology design support functionality

Energy Technology Data Exchange (ETDEWEB)

Kim, Yeon Seung; Kim, Dae Jin [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of); Barber, P W; Goland, D [Atomic Energy Canada Ltd., (Canada)

1996-06-01

This technical report was written as a result of Integrated Plant Information System (IPIS) feasibility study on CANDU 9 project which had been carried out from January, 1994 to March, 1994 at AECL (Atomic Energy Canada Limited) in Canada. From 1987, AECL had done endeavour to change engineering work process from paper based work process to computer based work process through CANDU 3 project. Even though AECL had a lot of good results form computerizing the Process Engineering, Instrumentation Control and Electrical Engineering, Mechanical Engineering, Computer Aided Design and Drafting, and Document Management System, but there remains the problem of information isolation and integration. On this feasibility study, IPIS design support functionality guideline was suggested by evaluating current AECL CAE tools, analyzing computer aided engineering task and work flow, investigating request for implementing integrated computer aided engineering and describing Korean request for future CANDU design including CANDU 9. 6 figs. (Author).

AECL present and future

International Nuclear Information System (INIS)

Foster, J.S.

1975-08-01

This is a history of Atomic Energy of Canada Limited with forecasts of its role in enabling Canada to meet a rapidly increasing share of her energy requirements from nuclear power. Its main activities will be research and development in support of contemporary and advanced CANDU (Canada Deuterium Uranium) nuclear power systems; research into other ways to provide energy and fissile materials; and investigation into applications for nuclear energy beyond the generation of electrical power. (Author)

Safety system upgrades to a research reactor: A regulatory perspective

International Nuclear Information System (INIS)

Lamarre, G.B.; Martin, W.G.

2003-01-01

The NRU (National Research Universal) reactor, located at the Chalk River Laboratories of Atomic Energy of Canada Limited (AECL), first achieved criticality November 3, 1957. AECL continues to operate NRU for research to support safety and reliability studies for CANDU reactors and as a major supplier of medical radioisotopes. Following a detailed systematic review and assessment of NRU's design and the condition of its primary systems, AECL formally notified the Canadian Nuclear Safety Commission's (CNSC) predecessor - the Atomic Energy Control Board - in 1992 of its intention to upgrade NRU's safety systems. AECL proposed seven major upgrades to provide improvements in shutdown capability, heat removal, confinement, and reactor monitoring, particularly during and after a seismic event. From a CNSC perspective, these upgrades were necessary to meet modern safety standards. From the start of the upgrades project, the CNSC provided regulatory oversight aimed at ensuring that AECL maintained a structured approach to the upgrades. The elements of the approach include, but are not limited to, the determination of project milestones and target dates; the formalization of the design process and project quality assurance requirements; the requirements for updated documentation, including safety reports, safety notes and commissioning reports; and the approval and authorization process. This paper details, from a regulatory perspective, the structured approach used in approving the design, construction, commissioning and subsequent operation of safety system upgrades for an existing and operating research reactor, including the many challenges faced when attempting to balance the requirements of the upgrades project with AECL's need to keep NRU operating to meet its important research and production objectives. (author)

Nuclear energy. Unmasking the mystery

International Nuclear Information System (INIS)

1988-08-01

The Standing Committee on Energy, Mines and Resources of the House of Commons of Canada undertook a study of the economics of nuclear power in Canada. This is its report on the evidence it heard. It found that maintaining the nuclear power option is vital to Canada's interests. The Committee recommended that: the schedule for establishing a commercial high-level radioactive waste repository be advanced; the basic insurance coverage on nuclear facilities be raised; the federal government increase its financial support of Atomic Energy of Canada Ltd. (AECL); AECL expand its research and development activities, including non-nuclear R and D; AECL be allowed to hold a minority interest in any component of AECL that is privatized; any new entity created by privatization from AECL be required to remain under Canadian control; the Atomic Energy Control Act be altered to allow the Atomic Energy Control Board (AECB) to recover costs through licensing fees and user charges, while the AECB's parliamentary appropriation is increased to offset remaining costs of operations; membership on the AECB be increased from one to five full-time members, retaining the present four part-time members; the AECB hold its hearings in public; the name of the AECB be changed so it is more readily distinguishable from AECL; the AECB establish an office of public information; and that federal and provincial governments cooperate more closely to identify opportunities where more efficient use of electricity could be achieved and to promote those measures that can attain the greatest economic efficiency

Nuclear fuel waste disposal in Canada

International Nuclear Information System (INIS)

Dormuth, K.W.; Gillespie, P.A.

1990-05-01

Atomic Energy of Canada Limited (AECL) has developed a concept for disposing of Canada's nuclear fuel waste and is submitting it for review under Federal Environmental Assessment and Review Process. During this review, AECL intends to show that careful, controlled burial 500 to 1000 metres deep in plutonic rock of the Canadian Precambrian Shield is a safe and feasible way to dispose of Canada's nuclear fuel waste. The concept has been assessed without identifying or evaluating any particular site for disposal. AECL is now preparing a comprehensive report based on more than 10 years of research and development

Progress in developing the concept for the irradiation research facility

International Nuclear Information System (INIS)

Lee, A.G.; Bishop, W.E.; Gillespie, G.E.; Zeng, Y.

1996-04-01

At the 16th annual Canadian Nuclear Society conference, AECL presented the case for replacing the NRU reactor with an Irradiation Research Facility (IRF) to test CANDU fuels and materials and to perform advanced materials research using neutrons. AECL developed a cost estimate of $500 million for the reference IRF concept, and estimated that it would require 87 months to complete. AECL has initiated a pre-project program to develop the IRF concept and to minimize uncertainties related to feasibility and licensability, and to examine options for reducing the overall project cost before project implementation begins. (author) 10 refs., 2 figs

Radioactive waste management in Canada

International Nuclear Information System (INIS)

1990-11-01

This bibliography is a review of the Canadian literature on radioactive waste management from 1953 to the present. It incorporates the references from the previous AECL--6186 revisions, and adds the current data and some of the references that had been omitted. Publications from outside organizations of concern to the Canadian Nuclear Fuel Waste Program are included in addition to AECL Research reports and papers. This report is intended as an aid in the preparation of the Concept Assessment Document and is complementary to AECL Research's internal document-ready references on the MASS-11 word processing systems

Nuclear fuel waste disposal in Canada

International Nuclear Information System (INIS)

Dormuth, K.W.; Gillespie, P.A.

1990-05-01

Atomic Energy of Canada Limited (AECL) has developed a concept for disposing of Canada's nuclear fuel waste and is submitting it for review under the Federal Environmental Assessment and Review Process. During this review, AECL intends to show that careful, controlled burial 500 to 1000 metres deep in plutonic rock of the Canadian Precambrian Shield is a safe and feasible way to dispose of Canada's nuclear fuel waste. The concept has been assessed without identifying or evaluating any particular site for disposal. AECL is now preparing a comprehensive report based on more than 10 years of research and development

Analysis of DCA experimental data

International Nuclear Information System (INIS)

Min, B. J.; Kim, S. Y.; Ryu, S. J.; Seok, H. C.

2000-01-01

The lattice characteristics of DCA are calculated with WIMS-ATR code to validate WIMS-AECL code for the lattice analysis of CANDU core by using experimental data of DCA at JNC. Analytical studies of some critical experiments had been performed to analyze the effects of fuel composition. Different items of reactor physics such as local power peaking factor (LPF), effective multiplication factor (Keff) and coolant void reactivity were calculated for two coolant void fractions (0% and 100%). LPFs calculated by WIMS-ATR code are in close agreement with the experimental results. LPFs calculated by WIMS-AECL code with WINFRITH and ENDF/B-V libraries have similar values for both libraries but the differences between experimental data and calculated results by WIMS-AECL code are larger than those of WIMS-ATR code. The maximum difference between the values calculated by WIMS-ATR and experimental values of LPFs are within 1.3%. The coupled code systems WIMS-ATR and CITATION used in this analysis predict Keff within 1% ΔK and coolant void reactivity within 4 % ΔK/K in all cases. The coolant void reactivity of uranium fuel is found to be positive. To validate WIMS-AECL code, the core characteristics of DCA shall be calculated by WIMS-AECL and CITATION codes in the future

SYSTMS: Systematic approach for the development of strategies for maintenance and surveillance

International Nuclear Information System (INIS)

Yang, J.X.; McCrea, L.; Dam, R.F.; Nickerson, J.H.

2004-01-01

As part of AECL's Integrated PLiM program, the SYSTMS TM tool has been developed to assist in applying the Systematic Assessment of Maintenance (SAM) technology. SYSTMS builds upon AECL's experience in this area, capturing lessons learned to result in an efficient and effective assessment of system maintenance in NPPs. An important feature of SYSTMS is that it provides analysts with needed information that is easy to review and select for inclusion in the system maintenance assessment. This is accomplished through the use of maintenance templates which can be built and tracked using SYSTMS or imported from AECL's own Maintenance Template Database. This database was developed originally to capture information gathered in SAM studies for use in future studies. It has grown to become a central tool for organizing and integrating aging related knowledge from both within AECL and from outside resources. The SYSTMS tool and the Maintenance Template Database work together to provide an effective tool for performing SAM assessments. This combination also becomes an integral part of the Asset Management program development and System based Adaptive Maintenance Program applications. This paper looks at the features of the SYSTMS tool and Maintenance Database, and discusses how these tools are an important part of the AECL Integrated PLiM products and services. (author)

Microbial analysis of the buffer/container experiment at AECL`s Underground Research Laboratory

Energy Technology Data Exchange (ETDEWEB)

Stroes-Gascoyne, S; Hamon, C J; Haveman, S A; Delaney, T L [Atomic Energy of Canada Ltd., Pinawa, MB (Canada). Whiteshell Labs; Pedersen, K; Ekendahl, S; Jahromi, N; Arlinger, J; Hallbeck, L [Univ. of Goeteborg, (Sweden). Dept. of General and Marine Microbiology; Daumas, S; Dekeyser, K [Guiges Recherche Appliquee en Microbiologie, Aix-en-Provence, (France)

1996-05-01

The Buffer/Container experiment was carried out for 2.5 years to examine the in-situ performance of compacted buffer material in a single emplacement borehole under vault-relevant conditions. During decommissioning of this experiment, numerous samples were taken for microbial analysis to determine if the naturally present microbial population in buffer material survived to conditions and to determine which groups of microorganisms would be dominant in such a simulated vault environment. Microbial analyses were initiated within 24 hour of sampling for all types of samples taken. The culture results showed an almost universal disappearance of viable microorganisms in the samples taken from near the heater surface. The microbial activity measurements confirmed the lack of viable organisms with very weak or no activity measured in most of these samples. Generally, aerobic heterotrophic culture conditions gave the highest mean colony-forming units (CFU) values at both 25 and 50 C. Under anaerobic conditions, and especially at 50 C, lower mean CFU values were obtained. In all samples analyzed, numbers of sulfate reducing bacteria were less than 1000 CFU/g dry material. Methanogens were either not present or were found in very low numbers. Anaerobic sulfur oxidizing bacteria were found in higher numbers in most sample types with sufficient moisture. The statistical evaluation of the culture data demonstrated clearly that the water content was the variable limiting the viability of the bacteria present, and not the temperature. 68 refs, 35 figs, 37 tabs.

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

Learning from experience. Feedback to design

International Nuclear Information System (INIS)

Hopwood, J.M.; Shalaby, B.A.; Keil, H.

1997-01-01

AECL has been the designer of 25 commercial scale CANDU reactors now in operation, with more under construction. AECL has taken the evolutionary approach in developing its current designs, the CANDU 6 and CANDU 9 Nuclear Power Plants. An integral part of this approach is to emphasize feedback of experience to the designers, in a continuous improvement process. AECL has implemented a formal process of gathering and responding to feedback from: NPP operation, construction and commissioning; regulatory input; R and D results: as well as paying close attention to market input. A number of recent examples of design improvement via this feedback process are described

Annual report 1993-94 (Atomic Energy of Canada Ltd., Ottawa)

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-12-31

Annual report of AECL, the legal name of Atomic Energy of Canada Limited. This annual report presents information on research, CANDU, and AECL around the world. A financial review is included, along with management responsibility, an Auditor`s report, financial statements, a five-year financial summary, and a list of directors and locations.

Radioactive waste management in Canada

International Nuclear Information System (INIS)

Hawley, N.J.

1986-09-01

This bibliography is an up-date to AECL-6186(Rev 3), 1952-1982, 'Radioactive Waste Management in Canada AECL Publications and Other Literature' compiled by Dianne Wallace. Canadian publications from outside contractors concerning the Canadian Nuclear Fuel Waste Management Program are included in addition to Atomic Energy of Canada Limited reports and papers. 252 refs

Qualification of FEAST 3.0 and FEAT 4.0 computer codes

International Nuclear Information System (INIS)

Xu, Z.; Lai, L.; Sim, K.-S.; Huang, F.; Wong, B.

2005-01-01

FEAST (Finite Element Analysis for Stresses) is an AECL computer code used to assess the structural integrity of the CANDU fuel element. FEAST models the thermo-elastic, thermo-elasto-plastic and creep deformations in CANDU fuel. FEAT (Finite Element Analysis for Temperature) is another AECL computer code and is used to assess the thermal integrity of fuel elements. FEAT models the steady-state and transient heat flows in CANDU fuel, under conditions such as flux depression, end flux peaking, temperature-dependent thermal conductivity, and non-uniform time-dependent boundary conditions. Both computer programs are used in design and qualification analyses of CANDU fuel. Formal qualifications (including coding verification and validation) of both codes were performed, in accordance with AECL software quality assurance (SQA) manual and procedures that are consistent with CSA N286.7-99. Validation of FEAST 3.0 shows very good agreement with independent analytical solutions or measurements. Validation of FEAT 4.0 also shows very good agreement with independent WIMS-AECL calculations, analytical solutions, ANSYS calculations and measurement. (author)

Qualification of FEAST 3.0 and FEAT 4.0 computer codes

Energy Technology Data Exchange (ETDEWEB)

Xu, Z.; Lai, L.; Sim, K.-S.; Huang, F.; Wong, B. [Atomic Energy of Canada Limited, Mississauga, Ontario (Canada)

2005-07-01

FEAST (Finite Element Analysis for Stresses) is an AECL computer code used to assess the structural integrity of the CANDU fuel element. FEAST models the thermo-elastic, thermo-elasto-plastic and creep deformations in CANDU fuel. FEAT (Finite Element Analysis for Temperature) is another AECL computer code and is used to assess the thermal integrity of fuel elements. FEAT models the steady-state and transient heat flows in CANDU fuel, under conditions such as flux depression, end flux peaking, temperature-dependent thermal conductivity, and non-uniform time-dependent boundary conditions. Both computer programs are used in design and qualification analyses of CANDU fuel. Formal qualifications (including coding verification and validation) of both codes were performed, in accordance with AECL software quality assurance (SQA) manual and procedures that are consistent with CSA N286.7-99. Validation of FEAST 3.0 shows very good agreement with independent analytical solutions or measurements. Validation of FEAT 4.0 also shows very good agreement with independent WIMS-AECL calculations, analytical solutions, ANSYS calculations and measurement. (author)

Rock stability considerations for siting and constructing a KBS-3 repository. Based on experiences from Aespoe HRL, AECL's URL, tunnelling and mining

International Nuclear Information System (INIS)

Martin, C.D.; Christiansson, Rolf; Soederhaell, J.

2001-12-01

Over the past 25 years the international nuclear community has carried out extensive research into the deep geological disposal of nuclear waste in hard rocks. In two cases this research has resulted in the construction of dedicated underground research facilities: SKB's Aespoe Hard Rock Laboratory, Sweden and AECL's Underground Research Laboratory, Canada. Both laboratories are located in hard rocks considered representative of the Fennoscandian and Canadian Shields, respectively. This report is intended to synthesize the important rock mechanics findings from these research programs. In particular the application of these finding to assessing the stability of underground openings. As such the report draws heavily on the published results from the SKB's ZEDEX Experiment in Sweden and AECL's Mine- by Experiment in Canada. The objectives of this report are to: 1. Describe, using the current state of knowledge, the role rock engineering can play in siting and constructing a KBS-3 repository. 2. Define the key rock mechanics parameters that should be determined in order to facilitate repository siting and construction. 3. Discuss possible construction issues, linked to rock stability, that may arise during the excavation of the underground openings of a KBS-3 repository. 4. Form a reference document for the rock stability analysis that has to be carried out as a part of the design works parallel to the site investigations. While there is no unique or single rock mechanics property or condition that would render the performance of a nuclear waste repository unacceptable, certain conditions can be treated as negative factors. Outlined below are major rock mechanics issues that should be addressed during the siting, construction and closure of a nuclear waste repository in Sweden in hard crystalline rock. During the site investigations phase, rock mechanics information will be predominately gathered from examination and testing of the rock core and mapping of the

List of publications 1994 January - 1995 December

Energy Technology Data Exchange (ETDEWEB)

Lim, M J; Dament, M; Barrie, B

1996-07-01

AECL`s mandate is to undertake research into nuclear energy and from that develop commercial applications. Its objective is to secure the maximum economic benefit for Canada from CANDU technology and the associated research and development. Among our most important products are scientific reports, publications and conference presentations. This document fists our publications for 1994-95. (author).

Technologies in support of CANDU development

International Nuclear Information System (INIS)

Turner, C.; Tapping, B.

2005-01-01

Atomic Energy of Canada, Ltd. (AECL) has significant research and development (R and D) programs designed to meet the needs of both existing CANDU reactors and new and evolving CANDU plant designs. These R and D programs cover a wide range of technology, from chemistry and materials support through to inspection and life management tools. Emphasis is placed on effective technology development programs for fuel channels, feeders and steam generators to ensure their operation through design life, and beyond. This paper specifically addresses how the R and D has been applied in the production of longer-lived pressure tubes for the most recent CANDU 6 reactors, and how this technology forms the basis for the pressure tubes of the Advanced CANDU Reactor (ACR). Similarly, AECL has developed solutions for other critical components such as calandria tubes, feeder pipe and steam generators. The paper also discusses how the R and D knowledge has been integrated into aging management databases and health monitoring tools. Since 1997, AECL has been working with CANDU utilities on comprehensive and integrated CANDU Plant Life Management (PLiM) programs for successful and reliable plant operation through design life and beyond. AECL has developed and implemented an advanced chemistry monitoring and diagnostic system, called ChemAND which allows on-line access by the operators to current and past chemistry conditions enabling appropriate responses and facilitating planning of shutdown maintenance actions. An equivalent tool for monitoring, trending and diagnosing thermal and mechanical data has also been developed; this tool is called ThermAND. AECL is developing the Maintenance Information, Monitoring, and Control (MIMC) system, which provide information to the user for condition-based decision-making in maintenance. To enable more effective inspections, surveillance and data collection, AECL has developed unique one-off tooling to carry out unanticipated inspection and repair

Rock stability considerations for siting and constructing a KBS-3 repository. Based on experiences from Aespoe HRL, AECL's URL, tunnelling and mining

Energy Technology Data Exchange (ETDEWEB)

Martin, C.D. [Univ. of Alberta, Edmonton (Canada); Christiansson, Rolf [Swedish Nuclear Fuel and Waste Management Co., Stockholm (Sweden); Soederhaell, J. [VBB VIAK AB, Stockholm (Sweden)

2001-12-01

Over the past 25 years the international nuclear community has carried out extensive research into the deep geological disposal of nuclear waste in hard rocks. In two cases this research has resulted in the construction of dedicated underground research facilities: SKB's Aespoe Hard Rock Laboratory, Sweden and AECL's Underground Research Laboratory, Canada. Both laboratories are located in hard rocks considered representative of the Fennoscandian and Canadian Shields, respectively. This report is intended to synthesize the important rock mechanics findings from these research programs. In particular the application of these finding to assessing the stability of underground openings. As such the report draws heavily on the published results from the SKB's ZEDEX Experiment in Sweden and AECL's Mine- by Experiment in Canada. The objectives of this report are to: 1. Describe, using the current state of knowledge, the role rock engineering can play in siting and constructing a KBS-3 repository. 2. Define the key rock mechanics parameters that should be determined in order to facilitate repository siting and construction. 3. Discuss possible construction issues, linked to rock stability, that may arise during the excavation of the underground openings of a KBS-3 repository. 4. Form a reference document for the rock stability analysis that has to be carried out as a part of the design works parallel to the site investigations. While there is no unique or single rock mechanics property or condition that would render the performance of a nuclear waste repository unacceptable, certain conditions can be treated as negative factors. Outlined below are major rock mechanics issues that should be addressed during the siting, construction and closure of a nuclear waste repository in Sweden in hard crystalline rock. During the site investigations phase, rock mechanics information will be predominately gathered from examination and testing of the rock core and

Qualification plan for the Genmod-PC computer program

International Nuclear Information System (INIS)

Richardson, R.B.; Wright, G.M.; Dunford, D.W.; Linauskas, S.H.

2002-07-01

Genmod-PC is an internal dosimetry code that uses Microsoft Windows operating system, and that currently calculates radionuclide doses and intakes for an adult male. This report provides a plan for specifying the quality assurance measures that conform to the recommendations of the Canadian Standards Association, as well as AECL procedural requirements for a legacy computer program developed at AECL. (author)

Maintenance - a design perspective

International Nuclear Information System (INIS)

Hedges, K.R.

1992-01-01

The paper describes how the CANDU-3 has incorporated, at the design stage, maintenance requirements such as component accessibility, standardization, ease of replacement, reduction in the number of components, and simplified component design. AECL is also active in the planned rehabilitation of the four units at Ontario Hydro's Bruce A nuclear generating station. In addition to conceptual design and development, detailed design and analysis, procurement and site assistance, AECL's Sheridan Park Laboratory will provide important development and mockup facilities. An AECL research and development program on reactor maintenance includes the identification and characterization of aging and degrading mechanisms, the tailoring of developed products to plant requirements, and the identification of areas of international cooperation and information exchange. 3 tabs., 1 fig

MOX fuel fabrication at AECL

International Nuclear Information System (INIS)

Dimayuga, F.C.; Jeffs, A.T.

1995-01-01

Atomic Energy of Canada Limited's mixed-oxide (MOX) fuel fabrication activities are conducted in the Recycle Fuel Fabrication Laboratories (RFFL) at the Chalk River Laboratories. The RFFL facility is designed to produce experimental quantities of CANDU MOX fuel for reactor physics tests or demonstration irradiations. From 1979 to 1987, several MOX fuel fabrication campaigns were run in the RFFL, producing various quantities of fuel with different compositions. About 150 bundles, containing over three tonnes of MOX, were fabricated in the RFFL before operations in the facility were suspended. In late 1987, the RFFL was placed in a state of active standby, a condition where no fuel fabrication activities are conducted, but the monitoring and ventilation systems in the facility are maintained. Currently, a project to rehabilitate the RFFL and resume MOX fuel fabrication is nearing completion. This project is funded by the CANDU Owners' Group (COG). The initial fabrication campaign will consist of the production of thirty-eight 37-element (U,Pu)O 2 bundles containing 0.2 wt% Pu in Heavy Element (H.E.) destined for physics tests in the zero-power ZED-2 reactor. An overview of the Rehabilitation Project will be given. (author)

CANDU technology for generation III + AND IV reactors

International Nuclear Information System (INIS)

Torgerson, D.F.

2005-01-01

Atomic Energy of Canada Limited (AECL) is the original developer of the CANDU?reactor, one of the three major commercial power reactor designs now used throughout the world. For over 60 years, AECL has continued to evolve the CANDU design from the CANDU prototypes in the 1950s and 1960s through to the second generation reactors now in operation, including the Generation II+ CANDU 6. The next phase of this evolution, the Generation III+ Advanced CANDU ReactorTM (ACRTM), continues the strategy of basing next generation technology on existing CANDU reactors. Beyond the ACR, AECL is developing the Generation IV CANDU Super Critical Water Reactor. Owing to the evolutionary nature of these advanced reactors, advanced technology from the development programs is also being applied to operating CANDU plants, for both refurbishments and upgrading of existing systems and components. In addition, AECL is developing advanced technology that covers the entire life cycle of the CANDU plant, including waste management and decommissioning. Thus, AECL maintains state-of-the-art expertise and technology to support both operating and future CANDU plants. This paper outlines the scale of the current core knowledge base that is the foundation for advancement and support of CANDU technology. The knowledge base includes advancements in materials, fuel, safety, plant operations, components and systems, environmental technology, waste management, and construction. Our approach in each of these areas is to develop the underlying science, carry out integrated engineering scale tests, and perform large-scale demonstration testing. AECL has comprehensive R and D and engineering development programs to cover all of these elements. The paper will show how the ongoing expansion of the CANDU knowledge base has led to the development of the Advanced CANDU Reactor. The ACR is a Generation III+ reactor with substantially reduced costs, faster construction, and enhanced passive safety and operating

Advanced CANDU reactor pre-licensing progress

International Nuclear Information System (INIS)

Popov, N.K.; West, J.; Snell, V.G.; Ion, R.; Archinoff, G.; Xu, C.

2005-01-01

The Advanced CANDU Reactor (ACR) is an evolutionary advancement of the current CANDU 6 reactor, aimed at producing electrical power for a capital cost and at a unit-energy cost significantly less than that of the current reactor designs. The Canadian Nuclear Safety Commission (CNSC) staff are currently reviewing the ACR design to determine whether, in their opinion, there are any fundamental barriers that would prevent the licensing of the design in Canada. This CNSC licensability review will not constitute a licence, but is expected to reduce regulatory risk. The CNSC pre-licensing review started in September 2003, and was focused on identifying topics and issues for ACR-700 that will require a more detailed review. CNSC staff reviewed about 120 reports, and issued to AECL 65 packages of questions and comments. Currently CNSC staff is reviewing AECL responses to all packages of comments. AECL has recently refocused the design efforts to the ACR-1000, which is a larger version of the ACR design. During the remainder of the pre-licensing review, the CNSC review will be focused on the ACR-1000. AECL Technologies Inc. (AECLT), a wholly-owned US subsidiary of AECL, is engaged in a pre-application process for the ACR-700 with the US Nuclear Regulatory Commission (USNRC) to identify and resolve major issues prior to entering a formal process to obtain standard design certification. To date, the USNRC has produced a Pre-Application Safety Assessment Report (PASAR), which contains their reviews of key focus topics. During the remainder of the pre-application phase, AECLT will address the issues identified in the PASAR. Pursuant to the bilateral agreement between AECL and the Chinese nuclear regulator, the National Nuclear Safety Administration (NNSA) and its Nuclear Safety Center (NSC), NNSA/NSC are reviewing the ACR in seven focus areas. The review started in September 2004, and will take three years. The main objective of the review is to determine how the ACR complies

Waste management program at Atomic Energy of Canada Limited

Energy Technology Data Exchange (ETDEWEB)

Wong, P.C.F.; Chan, N.; Hawrelluk, K. [Atomic Energy of Canada Limited, Chalk River, ON (Canada)

2011-07-01

The Atomic Energy of Canada Limited (AECL) Waste Management Program establishes requirements for waste management activities at AECL sites in Canada. It ensures that activities involving planning for, handling, processing, transporting, storage and long-term management of wastes are performed in a manner that protects the workers, the public, and the environment, and are in compliance with applicable regulatory and licence requirements. The program translates applicable legal requirements into program requirements appropriate for AECL, and assists AECL management in implementing those requirements. The Waste Management Program was formally established at AECL in 2007 as one of the nuclear programs. The activities conducted in the first two years (2007 - 09) were mainly focused on program development. Currently the program is executing the waste management improvement initiatives based on the Waste Management Program Improvement Plan. During the program implementation, close collaboration between the Waste Management Program and other departments resulted in improved waste management performance at Chalk River Laboratories (CRL). This included increased segregation of the waste at the source, reduction in waste generation, improved labeling and identification of waste packages, improved recyclables collection and initiating recycling of selected hazardous wastes. In accordance with pollution prevention, the quantities and degree of hazard of wastes requiring long-term management shall be minimized, following the principles of Prevent, Reduce, Reuse, and Recycle. The annual volume of solid waste generated is one of the key indicators for waste management performance. AECL has been successful in reduction of operational waste and diversion of materials for recycling at CRL. From 2007 to 2010, the annual volume of solid waste, including inactive and radioactive wastes, generated from routine operations at CRL decreased by 26%, and the annual amount of recyclables sent

Waste management program at Atomic Energy of Canada Limited

International Nuclear Information System (INIS)

Wong, P.C.F.; Chan, N.; Hawrelluk, K.

2011-01-01

The Atomic Energy of Canada Limited (AECL) Waste Management Program establishes requirements for waste management activities at AECL sites in Canada. It ensures that activities involving planning for, handling, processing, transporting, storage and long-term management of wastes are performed in a manner that protects the workers, the public, and the environment, and are in compliance with applicable regulatory and licence requirements. The program translates applicable legal requirements into program requirements appropriate for AECL, and assists AECL management in implementing those requirements. The Waste Management Program was formally established at AECL in 2007 as one of the nuclear programs. The activities conducted in the first two years (2007 - 09) were mainly focused on program development. Currently the program is executing the waste management improvement initiatives based on the Waste Management Program Improvement Plan. During the program implementation, close collaboration between the Waste Management Program and other departments resulted in improved waste management performance at Chalk River Laboratories (CRL). This included increased segregation of the waste at the source, reduction in waste generation, improved labeling and identification of waste packages, improved recyclables collection and initiating recycling of selected hazardous wastes. In accordance with pollution prevention, the quantities and degree of hazard of wastes requiring long-term management shall be minimized, following the principles of Prevent, Reduce, Reuse, and Recycle. The annual volume of solid waste generated is one of the key indicators for waste management performance. AECL has been successful in reduction of operational waste and diversion of materials for recycling at CRL. From 2007 to 2010, the annual volume of solid waste, including inactive and radioactive wastes, generated from routine operations at CRL decreased by 26%, and the annual amount of recyclables sent

Epp names new interim execs to head Atomic Energy Canada

International Nuclear Information System (INIS)

1992-01-01

Federal Energy Minister Jake Epp has named Mrs. Marnie Paiken as acting chairman and Bruce Howe as acting president of AECL (formerly Atomic Energy Canada Ltd.), the federal Crown corporation charged with the development and utilization of nuclear energy. Both appointments were made necessary by the resignations of Robert Ferchat as chairman and Stanley Hatcher as president, each citing deep differences in their respective approaches to the management of the corporation. Mrs. Paiken has been a member of AECL's board since 1985, and previously served as acting chairman from March 1989 to July 1990. Howe has been deputy minister of the federal energy department since 1988, a position he will retain while carrying out his duties as president of AECL. A search has begun to find permanent replacements

Developing the MAPLE materials test reactor concept

International Nuclear Information System (INIS)

Lee, A.G.; Lidstone, R.F.; Donnelly, J.V.

1992-05-01

MAPLE-MTR is a new multipurpose research facility being planned by AECL Research as a possible replacement for the 35-year-old NRU reactor. In developing the MAPLE-MTR concept, AECL is starting from the recent design and licensing experience with the MAPLE-X10 reactor. By starting from technology developed to support the MAPLE-X10 design and adapting it to produce a concept that satisfies the requirements of fuel channel materials testing and fuel irradiation programs, AECL expects to minimize the need for major advances in nuclear technology (e.g., fuel, heat transfer). Formulation of the MAPLE-MTR concept is at an early stage. This report describes the irradiation requirements of the research areas, how these needs are translated into design criteria for the project and elements of the preliminary design concept

Public opinion research in Canada: Incorporating the messages

International Nuclear Information System (INIS)

David Lisle

2001-01-01

The development and use of nuclear technology in Canada, similar to other countries, has been influenced by public perceptions that are often based on limited information. Most individuals find it challenging to decide among the apparent conflicting claims and allegations related to nuclear power. To meet the challenges of public acceptance, AECL develops and implements strategies designed to increase awareness and understanding of the issues associated with nuclear technology. AECL's public communication programs have evolved over several decades. This reflects the changing nature of public concerns related to nuclear energy. With ever increasing requirements for public involvement in the decision-making process, AECL has designed and successfully implemented effective communication and consultation processes to build and maintain public support for nuclear projects. Public communication programs have also been developed and implemented by the provincial utilities that own and operate CANDU reactors, by the Canadian Nuclear Association and by the Canadian Nuclear Society. Often public education and information programs have been a collaborative effort involving a number of the key stakeholders in Canada's nuclear industry. AECL's public communication initiatives are designed to address the fears and myths surrounding the nuclear industry. The company is committed to providing information on its programs and it responds in a timely fashion to requests from the public. Due to the highly competitive nature of the nuclear industry, there is some proprietary information that is restricted and cannot be released. Consultations with the shareholder and with other key stakeholders on communication plans are an integral component of the design and implementation process. AECL public affairs staff provides advice and assistance to various government and industry communication committees. (author)

Advanced pressure tube sampling tools

International Nuclear Information System (INIS)

Wittich, K.C.; King, J.M.

2002-01-01

Deuterium concentration is an important parameter that must be assessed to evaluate the Fitness for service of CANDU pressure tubes. In-reactor pressure tube sampling allows accurate deuterium concentration assessment to be made without the expenses associated with fuel channel removal. This technology, which AECL has developed over the past fifteen years, has become the standard method for deuterium concentration assessment. AECL is developing a multi-head tool that would reduce in-reactor handling overhead by allowing one tool to sequentially sample at all four axial pressure tube locations before removal from the reactor. Four sets of independent cutting heads, like those on the existing sampling tools, facilitate this incorporating proven technology demonstrated in over 1400 in-reactor samples taken to date. The multi-head tool is delivered by AECL's Advanced Delivery Machine or other similar delivery machines. Further, AECL has developed an automated sample handling system that receives and processes the tool once out of the reactor. This system retrieves samples from the tool, dries, weighs and places them in labelled vials which are then directed into shielded shipping flasks. The multi-head wet sampling tool and the automated sample handling system are based on proven technology and offer continued savings and dose reduction to utilities in a competitive electricity market. (author)

Operating experience with gamma ray irradiators

International Nuclear Information System (INIS)

Fraser, F.M.; Ouwerkerk, T.

1980-01-01

The experience of Atomic Energy of Canada, Limited (AECL) with radioisotopes dates back to the mid-1940s when radium was marketed for medical purposes. Cobalt-60 came on the scene in 1949 and within a few years a thriving business in cancer teletherapy machines and research irradiators was developed. AECL's first full-scale cobalt-60 gamma ray sterilizer for medical products was installed in 1964. AECL now has over 50 plants and 30 million curies in service around the world. Sixteen years of design experience in cobalt-60 sources, radiation shielding, safety interlock systems, and source pass mechanisms have made gamma irradiators safe, reliable, and easy to operate. This proven technology is being applied in promising new fields such as sludge treatment and food preservation. Cesium-137 is expected to be extensively utilized as the gamma radiation source for these applications

New applications of radioisotopes

International Nuclear Information System (INIS)

Beddoes, J.M.

1982-06-01

The Radiochemical Company of Atomic Energy of Canada Ltd. is developing new uses for radioisotpes. This paper discusses three of them. The first is positron emission tomography. AECL, together with the Montreal Neurological Institute, has developed a new PET scanner, the Therascan 3128. A second area of interest is radiopharmaceuticals, which AECL is beginning to produce in patient-ready form. Finally, investigations are being carried out into the use of cobalt 60 gamma sources as food and waste irradiators

Cernovoda construction on target for Unit 1 startup in 1994

International Nuclear Information System (INIS)

Anon.

1992-01-01

AECL and the Italian company Ansaldo have formed a joint venture to complete the first unit of the five-unit station at Cernovoda, with AECL assuming overall project management. Financing of the project is being provided jointly, with $315 million form the Canadian Export Development Corp. and $175 million from the Italian government. First criticality is scheduled for October 1994, and connection to the grid in December 1994. When complete, Cernovoda will supply 30% of Romania's electricity

The Maple reactor project

International Nuclear Information System (INIS)

Malkoske, G.R.; Labrie, J.-P.

2003-01-01

MDS Nordion supplies the majority of the world's reactor-produced medical isotopes. These isotopes are currently produced in the NRU reactor at AECL's Chalk River Laboratories (CRL). Medical isotopes and related technology are relied upon around the world to prevent, diagnose and treat disease. The NRU reactor, which has played a key role in supplying medical isotopes to date, has been in operation for over 40 years. Replacing this aging reactor has been a priority for MDS Nordion to assure the global nuclear medicine community that Canada will continue to be a dependable supplier of medical isotopes. MDS Nordion contracted AECL to construct two MAPLE reactors dedicated to the production of medical isotopes. The MDS Nordion Medical Isotope Reactor (MMIR) project started in September 1996. This paper describes the MAPLE reactors that AECL has built at its CRL site, and will operate for MDS Nordion. (author)

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

Realizing the benefits of improved plant monitoring in DCC upgrade applications

International Nuclear Information System (INIS)

Stephens, K.L.

2001-01-01

The basic design of current CANDU control centres was established in the early 1970's and plants constructed since then have maintained the same basic design. Over the ensuing years AECL and utility owners have implemented an evolutionary approach to ensuing years AECL and utility owners have implemented an evolutionary approach to control centre improvements. This continues to be the approach as refurbishment and retrofits are being considered for aging CANDU plants. The Advanced Control Centre information System (ACCIS), AECL's plant display system product, can be applied in an evolutionary manner within the control centre. ACCIS provides users with the advanced information necessary to meet the key operational goals of safety and production. AECL is presently deploying ACCIS in the Qinshan Unit l and 2 Control Centres and the Training Simulator. In this installation ACCIS provides supplemental display capabilities together with an integrated DCC/ACCIS annunciation function. This solution provides a working example of how ACCIS could be applied in a retrofit situation and provides useful information on its utilization in future retrofits. This paper describes ACCIS functionality, particularly focusing on features and functions critical to providing improved monitoring. The applications of these functions are described within the context of the Qinshan Plant Display System (QPDS) installation. This information is then extended to its application within future retrofits. (author)

Legacy program acquires special equipment for CRL spent fuel. Canadian arm of Rolls Royce delivers unique machines

International Nuclear Information System (INIS)

Boyd, F.

2012-01-01

Six years ago the federal government accepted its responsibility for the radioactive waste that has resulted from the six decades of nuclear research and development conducted by Atomic Energy of Canada Limited and its predecessor operator of the Chalk River Laboratories (CRL) the National Research Council (1944 - 1952). Nuclear research and development and, particularly, reactor operation at CRL has resulted in outdated and unused research facilities and buildings and a wide variety of buried and stored radioactive waste. In 2006 the federal government established the Nuclear Legacy Liabilities Program (NLLP) with an initial funding of $520 million. The mandate of the NLLP is to deal with the radioactive waste arising from the nuclear research and development program of AECL and also prototype reactors in which it was involved. The timeline for the NLLP extends several decades into the future. The NLLP is implemented through a partnership of Natural Resources Canada (NRCan) and AECL. NRCan is responsible for policy direction and oversight, while AECL is responsible for program implementation and all licences, facilities and lands. About 70 percent of the liabilities from AECL activities are at CRL. Other sites that will be restored under the NLLP are: the Whiteshell Laboratories and Underground Research Laboratory in Manitoba; NPD and Douglas Point reactors in Ontario; and the Gentilly 1 reactor in Quebec. (author)

Econometric analysis and energy substitution

International Nuclear Information System (INIS)

Phillips, G.J.

1981-09-01

As part of its long-term assessment of new applications for nuclear energy, AECL is becoming acquainted with the techniques of mathematical modelling as used in the areas of energy and economics. Early in 1980, a contract was arranged with DataMetrics Limited of Calgary to prepare an econometric model of the manufacturing sector for Ontario, and to provide AECL with all the information necessary to understand the theory, derivation, and use of the model. This report summarizes the results of this exercise

Tritium handling experience at Atomic Energy of Canada Limited

Energy Technology Data Exchange (ETDEWEB)

Suppiah, S.; McCrimmon, K.; Lalonde, S.; Ryland, D.; Boniface, H.; Muirhead, C.; Castillo, I. [Atomic Energy of Canad Limited - AECL, Chalk River Laboratories, Chalk River, ON (Canada)

2015-03-15

Canada has been a leader in tritium handling technologies as a result of the successful CANDU reactor technology used for power production. Over the last 50 to 60 years, capabilities have been established in tritium handling and tritium management in CANDU stations, tritium removal processes for heavy and light water, tritium measurement and monitoring, and understanding the effects of tritium on the environment. This paper outlines details of tritium-related work currently being carried out at Atomic Energy of Canada Limited (AECL). It concerns the CECE (Combined Electrolysis and Catalytic Exchange) process for detritiation, tritium-compatible electrolysers, tritium permeation studies, and tritium powered batteries. It is worth noting that AECL offers a Tritium Safe-Handling Course to national and international participants, the course is a mixture of classroom sessions and hands-on practical exercises. The expertise and facilities available at AECL is ready to address technological needs of nuclear fusion and next-generation nuclear fission reactors related to tritium handling and related issues.

Electron processing of fibre-reinforced advanced composites

Energy Technology Data Exchange (ETDEWEB)

Singh, A.; Saunders, C.B.; Barnard, J.W.; Lopata, V.J.; Kremers, W.; McDougall, T.E.; Chung, M.; Tateishi, Miyoko [Atomic Energy of Canada Ltd., Pinawa, MB (Canada). Whiteshell Labs.

1996-08-01

Advanced composites, such as carbon-fibre-reinforced epoxies, are used in the aircraft, aerospace, sporting goods, and transportation industries. Though thermal curing is the dominant industrial process for advanced composites, electron curing of similar composites containing acrylated epoxy matrices has been demonstrated by our work. The main attraction of electron processing technology over thermal technology is the advantages it offers which include ambient temperature curing, reduced curing times, reduced volatile emissions, better material handling, and reduced costs. Electron curing technology allows for the curing of many types of products, such as complex shaped, those containing different types of fibres and up to 15 cm thick. Our work has been done principally with the AECL`s 10 MeV, 1 kW electron accelerator; we have also done some comparative work with an AECL Gammacell 220. In this paper we briefly review our work on the various aspects of electron curing of advanced composites and their properties. (Author).

Nuclear medicine tomorrow

International Nuclear Information System (INIS)

Marko, A.M.

1986-04-01

The purpose of this Workshop was to discuss and promote future nuclear medicine applications. Atomic Energy of Canada Limited (AECL) is determined to assist in this role. A major aim of this gathering was to form an interface that was meaningful, representative of the two entities, and above all, on-going. In the opening address, given by Mr. J. Donnelly, President of AECL, this strong commitment was emphasized. In the individual sessions, AECL participants outlined R and D programs and unique expertise that promised to be of interest to members of the nuclear medicine community. The latter group, in turn, described what they saw as some problems and needs of nuclear medicine, especially in the near future. These Proceedings comprise the record of the formal presentations. Additionally, a system of reporting by rapporteurs insured a summary of informal discussions at the sessions and brought to focus pertinent conclusions of the workshop attendees

The contract for the completion and commissioning of Cernavoda NPP - Unit

International Nuclear Information System (INIS)

2001-01-01

On May 18, 2001 the commercial contract for the completion and commissioning of the Cernavoda NPP Unit 2 has been signed by Nuclearelectrica National Company (SNN SA) and its partners, AECL-Canada and ANSALDO-Italy. This contract represents a continuation of the cooperation with AECL-Canada (the owner of the licence and the designer of the nuclear part of Cernavoda NPP Unit1) and ANSALDO-Italy (the designer of the conventional part of Cernavoda NPP Unit1). The completion is scheduled to last for 54 months (4.5 years) since the date the contract takes effect and the nuclear reactor start-up (the first criticality) is scheduled for the 49 th month. The total negotiated cost for the completion was estimated to amount to 689 million dollars, against the 750 million dollars initially estimated. The works at the site will be managed by an integrated staff team of specialized personnel form AECL-Canada (111 positions), ANSALDO-Italy (72 positions) and Romania (1200 positions)

The AECL research and development program

International Nuclear Information System (INIS)

Hart, R.G.; Woods, A.D.B.

1980-02-01

The research and development program of the Atomic Energy of Canada Research Company is briefly described. Goals and objectives are emphasized, some recent highlights are given and the importance of technology transfer is discussed. A short representative bibliography is included. (auth)

Materials research in AECL, Spring 1970

Energy Technology Data Exchange (ETDEWEB)

NONE

1970-05-15

This report gives a summary of materials research at Atomic Energy of Canada Limited. The topics covered in this report include engineering design with brittle materials, texture and mechanical properties of zirconium alloy tubing, structural damage by ion bombardment, research on silicon carbide, shallow phosphorus diffusion in p-type silicon and scanning electron microscopy. CRNL facilities for the examination of irradiated materials is also discussed.

AECL research programs in life sciences

International Nuclear Information System (INIS)

Marko, A.M.

1981-04-01

The present report summarizes the current research activities in life sciences in the Atomic Energy of Canada Limited-Research Company. The research is carried out at its two main research sites: the Chalk River Nuclear Laboratories and the Whiteshell Nuclear Research Establishment. The summaries cover the following areas of research: radiation biology, medical biophysics, epidemiology, environmental research and dosimetry. (author)

Materials research in AECL, Spring 1970

International Nuclear Information System (INIS)

1970-05-01

This report gives a summary of materials research at Atomic Energy of Canada Limited. The topics covered in this report include engineering design with brittle materials, texture and mechanical properties of zirconium alloy tubing, structural damage by ion bombardment, research on silicon carbide, shallow phosphorus diffusion in p-type silicon and scanning electron microscopy. CRNL facilities for the examination of irradiated materials is also discussed

AECL programs in basic physics research

International Nuclear Information System (INIS)

Bartholomew, G.A.; Dolling, G.; Harvey, M.; Milton, J.C.D.

1982-02-01

This report describes the CRNL program of research into the basic properties of atomic nuclei and condensed matter (liquids and solids). Brief descriptions are given of some of the current experimental programs done principally at the NRU reactor and MP tandem accelerator, the associated theoretical studies, and some highlights of past achievements

AECL research programs in systems chemistry

International Nuclear Information System (INIS)

Lister, D.H.; Pathania, R.S.

1984-05-01

Research programs in Systems Chemistry are aimed at preserving the integrity of the many working systems in CANDU reactors and at minimizing chemistry-induced problems such as radiation field growth or fouling of surfaces. The topics of main concern are the chemistry and corrosion of steam generators, for it is in this general area that the potential for serious problems is very real

Food for thought in a world of hunger and disease

International Nuclear Information System (INIS)

Thomas, R.

1990-01-01

The numerous benefits and safety of food irradiation are emphasized in this article. Canada is the world's largest supplier of industrial irradiators. Some 25 irradiators used to irradiate food have been supplied by Nordion. A full-scale pilot plant operates at Institut Armand Frappier in Laval, Quebec, and another food irradiation research facility has been established by Agriculture Canada at Ste. Hyacinthe. AECL conducts research on food irradiation at its Whiteshell Laboratories. AECL is also developing industrial electron accelerators that could be used to irradiate food

Darlington up and running

International Nuclear Information System (INIS)

Show, Don

1993-01-01

We've built some of the largest and most successful generating stations in the world. Nonetheless, we cannot take our knowledge and understanding of the technology for granted. Although, I do believe that we are getting better, building safer, more efficient plants, and introducing significant improvements to our existing stations. Ontario Hydro is a large and technically rich organization. Even so, we realize that partnerships with others in the industry are absolutely vital. I am thinking particularly of Atomic Energy of Canada Limited. We enjoy a very close relationship with Aecl, and their support was never more important than during the N/A Investigations. In recent years, we've strengthened our relationship with Aecl considerably. For example, we recently signed an agreement with Aecl, making available all of the Darlington 900 MW e design. Much of the cooperation between Ontario Hydro and Aecl occurs through the CANDU Engineering Authority and the CANDU Owners Group (CO G). These organizations are helping both of US to greatly improve cooperation and efficiency, and they are helping ensure we get the biggest return on our CANDU investments. CO G also provides an important information network which links CANDU operators in Canada, here in Korea, Argentina, India, Pakistan and Romania. In many respects, it is helping to develop the strong partnerships to support CANDU technology worldwide. We all benefit in the long run form sharing information and resources

Disposal of Canada's nuclear fuel waste

International Nuclear Information System (INIS)

Dormuth, K.W.; Nuttall, K.

1994-01-01

In 1978, the governments of Canada and Ontario established the Nuclear Fuel Waste Management program. As of the time of the conference, the research performed by AECL was jointly funded by AECL and Ontario Hydro through the CANDU owners' group. Ontario Hydro have also done some of the research on disposal containers and vault seals. From 1978 to 1992, AECL's research and development on disposal cost about C$413 million, of which C$305 was from funds provided to AECL by the federal government, and C$77 million was from Ontario Hydro. The concept involves the construction of a waste vault 500 to 1000 metres deep in plutonic rock of the Canadian Precambrian Shield. Used fuel (or possibly solidified reprocessing waste) would be sealed into containers (of copper, titanium or special steel) and emplaced (probably in boreholes) in the vault floor, surrounded by sealing material (buffer). Disposal rooms might be excavated on more than one level. Eventually all excavated openings in the rock would be backfilled and sealed. Research is organized under the following headings: disposal container, waste form, vault seals, geosphere, surface environment, total system, assessment of environmental effects. A federal Environmental Assessment Panel is assessing the concept (holding public hearings for the purpose) and will eventually make recommendations to assist the governments of Canada and Ontario in deciding whether to accept the concept, and how to manage nuclear fuel waste. 16 refs., 1 tab., 3 figs

Proceedings of the workshop on applied mathematics

Energy Technology Data Exchange (ETDEWEB)

Lee, H C; Couture, M; Douglas, S; Leivo, H P

1992-10-01

The Workshop on Applied Mathematics was held at the Cockcroft Centre, Deep River, Ontario, 1992 February 7-8. The purpose of the workshop was to provide a forum for applied mathematicians to survey the use and to discuss the future of applied mathematics at AECL Research. There were 57 participants at the workshop A total of eight 30-minute and 25 15-minute talks were presented describing mathematical techniques used in the whole range of activities at AECL Research, from numerical simulation of fluid flow through eddy current testing to quantum algebra and accelerator physics.

Proceedings of the workshop on applied mathematics

International Nuclear Information System (INIS)

Lee, H.C.; Couture, M.; Douglas, S.; Leivo, H.P.

1992-10-01

The Workshop on Applied Mathematics was held at the Cockcroft Centre, Deep River, Ontario, 1992 February 7-8. The purpose of the workshop was to provide a forum for applied mathematicians to survey the use and to discuss the future of applied mathematics at AECL Research. There were 57 participants at the workshop A total of eight 30-minute and 25 15-minute talks were presented describing mathematical techniques used in the whole range of activities at AECL Research, from numerical simulation of fluid flow through eddy current testing to quantum algebra and accelerator physics

A study of the health of the employees of Atomic Energy of Canada Limited

International Nuclear Information System (INIS)

Weeks, J.L.; Johnston, L.H.

1984-09-01

The Atomic Energy of Canada Limited Employee Health Study is a program that was established in 1980 to determine, over the long term, the causes of death in a population consisting of some 14 000 AECL employees and past employees. In a previous report (AECL-6813) the steps taken to set up the study were described. The present report is a description of the way in which the study was implemented, and includes discussion of some recent developments that have had a bearing on epidemiological studies of the health of radiation workers

Fuels for Canadian research reactors

International Nuclear Information System (INIS)

Feraday, M.A.

1993-01-01

This paper includes some statements and remarks concerning the uranium silicide fuels for which there is significant fabrication in AECL, irradiation and defect performance experience; description of two Canadian high flux research reactors which use high enrichment uranium (HEU) and the fuels currently used in these reactors; limited fabrication work done on Al-U alloys to uranium contents as high as 40 wt%. The latter concerns work aimed at AECL fast neutron program. This experience in general terms is applied to the NRX and NRU designs of fuel

Romanian-Canadian joint program for qualification of FCN as a CANDU fuel supplier

International Nuclear Information System (INIS)

Galeriu, C.A.; Andrei, G.; Bailescu, A.

1995-01-01

RENEL (Romania Power Authority), the co-ordinator of Romanian Nuclear Program, have decided to improve, starting 1990 the existing capability to produce CANDU nuclear fuel at FCN Pitesti. The objective of the program was defined with AAC (AECL - ANSALDO Consortium) for the qualification of FCN fuel plant according to Canadian Z299.2 standard. The Qualification Program was performed under AAC Work Order C-003. The co-ordination was assumed by AECL, as overall Design Authority. ZPI (Zircatec Precision Industries Inc., Canada), were designated to supply technical assistance, equipments and know how where necessary. After a preliminary verification of the FCN fuel plant, including the processes and system investigation, performed under AECL and ZPI assistance, the Qualification Program was defined in all details. The upgrading of documentation on all aspects required by Z299.2 was performed. Few processes needed to be reconsidered and equipment was delivered by ZPI or other suppliers. This includes mainly welding equipments and special inspection equipments. Health Physics was practically fully reconsidered. New equipment and practice were adapted to provide adequate control on health conditions. Every manufacturing and inspection process was checked to determine their performance during a Qualification Run based on acceptance criteria which have been established in the Qualification Plan. Manufacturing Demonstration Run was an important step to prove that all plant functions have been accomplished during the fabrication of 200 fuel bundles. These bundles have been fully accepted and 66 of them have been loaded in the first charge of Unit 1 Cemavoda NPS. The surveillance and audit actions made by AECL and ZPI during this period confirmed the FCN capability to operate an adequate system meeting the to required quality assurance standard. The very open attitude of AECL, Zircatec and FCN staff have stimulated the progress of the project and a successful achievement of the

Comparison between Canadian probabilistic safety assessment methods formulated by Atomic Energy of Canada limited and probabilistic risk assessment methods

International Nuclear Information System (INIS)

Shapiro, H.S.; Smith, J.E.

1989-01-01

The procedures used by Atomic Energy of Canada Limited (AECL) to perform probabilistic safety assessments (PRAs) differ somewhat from conventionally accepted probabilistic risk assessment (PRA) procedures used elsewhere. In Canada, PSA is used by AECL as an audit tool for an evolving design. The purpose is to assess the safety of the plant in engineering terms. Thus, the PSA procedures are geared toward providing engineering feedback so that necessary changes can be made to the design at an early stage, input can be made to operating procedures, and test and maintenance programs can be optimized in terms of costs. Most PRAs, by contrast, are performed in plants that are already built. Their main purpose is to establish the core melt frequency and the risk to the public due to core melt. Also, any design modification is very expensive. The differences in purpose and timing between PSA and PRA have resulted in differences in methodology and scope. The PSA procedures are used on all plants being designed by AECL

The development of maple technology for materials testing, isotope production, and neutron-beam applications

International Nuclear Information System (INIS)

Lidstone, R.F.; Gillespie, G.E.; Lee, A.G.; Bishop, W.E.

1996-01-01

AECL has been developing MAPLE technology to meet Canadian and international requirements for high-performance research reactors. MAPLE refers to a family of open-tank-in-pool reactors that employ compact H 2 O-cooled cores within D 2 O vessels to efficiently furnish neutrons to various types of irradiation facilities. The initial focus was on a 10-MW t Canadian facility for radioisotope production, the HANARO multipurpose-reactor project, and an associated R and D program. Recently, AECL began to develop the concept for a new Canadian Irradiation Research Facility (IRF) which will support the continued evolution of CANDU (CANadian Deuterium Uranium) technology and generate neutrons for basic and applied materials science. Additionally, AECL is currently developing a standardized MAPLE research-centre design with integrated neutron-application facilities; various reactor-core options have been optimized for different combinations of utilization: a 19-site core for neutron-beam applications and ancillary isotope production, a 31-site core for multipurpose materials testing and neutron-beam applications, and twin 18-site cores for high-flux neutron-beam applications. (author)

Atomic Energy of Canada study says nuclear cheaper power for oilsands

Energy Technology Data Exchange (ETDEWEB)

Anon

2003-07-01

The Canadian Energy Research Institute, an independent research organization, reports in a study sponsored by AECL, a federal Crown corporation, that nuclear power is cheaper than gas in creating steam if prices for natural gas remain above $US 3.50 per million BTU. Oil sands producers use natural gas to create steam, which is injected into the ground to melt the bitumen; gas is also used in parts of the oilsands upgrading process. According to reliable estimates some $50 billion of future oilsands investment is now on the drawing board; all of that could be jeopardized by high gas prices. AECL, which has sold only three nuclear reactors since 1996, hopes that the prospect of a continuing high price of natural gas will put it in a favorable position to displace natural gas with nuclear energy as the energy source for creating steam. Environmentalists consider AECL's suggestion of building a nuclear reactor for generating steam for oilsands production as unrealistic, and one that is based on 'nothing but a hope and a prayer'.

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)

The back end of the fuel cycle and CANDU

International Nuclear Information System (INIS)

Allan, C.J.; Dormuth, K.W.

2001-01-01

CANDU reactor operators have benefited from several advantages of the CANDU system and from AECL's experience, with regard to spent fuel handling, storage and disposal. AECL has over 20 years experience in development and application of medium-term storage and research and development on the disposal of used fuel. As a result of AECL's experience, short-term and medium-term storage and the associated handling of spent CANDU fuel are well proven and economic, with an extremely high degree of public and environmental protection. In fact, both short-term (water-pool) and medium-term (dry canister) storage of CANDU fuel are comparable or lower in cost per unit of energy than for PWRs. Both pool storage and dry spent fuel storage are fully proven, with many years of successful, safe operating experience. AECL's extensive R and D on the permanent disposal of spent-fuel has resulted in a defined concept for Canadian fuel disposal in crystalline rock. This concept was recently confirmed as ''technically acceptable'' by an independent environmental review panel. Thus, the Canadian program represents an international demonstration of the feasibility and safety of geological disposal of nuclear fuel waste. Much of the technology behind the Canadian concept can be adapted to permanent land-based disposal strategies chosen by other countries. In addition, the Canadian development has established a baseline for CANDU fuel permanent disposal costs. Canadian and international work has shown that the cost of permanent CANDU fuel disposal is similar to the cost of LWR fuel disposal per unit of electricity produced. (author)

Progress report. Physics and Health Sciences, Health Sciences Section (1988 July 01 - December 31)

International Nuclear Information System (INIS)

Milton, J.D.C.

1989-04-01

The screening assay for inherited variations in radiosensitivity has been tested. The object is to determine whether those individuals whose cells are abnormally radiosensitive are in fact prone to cancer. Follow-up of the health of radiation workers at AECL continues. As noted in the Hare report (Ontario Nuclear Safety Review), 'epidemiological analysis of the exposed workers of AECL ... shows cancer mortality to be below that in the general public'. These studies are being extended in order to ensure that the initial conclusions remain valid with up-to-date information. A new, very sensitive thermoluminescent material has been adapted for use in AECL dosimetry. The new material results in a much improved performance for measuring small doses and in addition, for accurate dose estimates of low energy beta rays. Much of the work of the Environmental Research Branch concerns modelling. In the atmosphere, our work on atmospheric plume dispersion and metabolic modelling has led naturally to AECL staff contributing to the high profile international study, BIOMOVS. Similarly, the release of a small quantity of tritiated heavy water provided an excellent opportunity to test our model of surface water flow in the Ottawa River. This rather simple model provided a surprisingly accurate prediction, and gave the best estimate of the total release. Finally, continuing analysis of Twin Lakes tracer data is making significant contributions to our very sophisticated model of groundwater flow in porous, heterogeneous media. Conversion of this model to run under NOS/VE on the new Cyber 990 computer is essentially complete

Design and development to simplify transfer

International Nuclear Information System (INIS)

Bertin, L.

1981-01-01

The methods of technology transfer from the Atomic Energy of Canada Ltd. to industry and electric utilities are discussed. Approximately 40 years of Canadian technology is just one advantage countries outside Canada gain when purchasing Candu systems. To promote a large programme of industrial research, AECL has a very large expenditure on industrial contract work, about $6 million on one typical year. Approximately 30 to 40 attached staff join AECL each year, and some new products have resulted from the technology transfer, eg. development of nuclear fuels to proven reliability, seamless Inconel and high quality bellows. (author)

Postclosure assessment as a design tool for waste disposal systems

International Nuclear Information System (INIS)

Goodwin, B.W.; Hajas, W.C.; LeNeveu, D.M.; Melnyk, T.W.

1995-01-01

AECL Research and Ontario Hydro share the responsibility to evaluate the feasibility and safety of the concept for the disposal of Canada's nuclear fuel waste. The concept involves deep underground disposal in crystalline rock on the Canadian Shield. AECL Research is currently preparing an Environmental Impact Statement for review by a federal Environmental Assessment Review Panel. In this paper, we present an example of how simulations performed for the postclosure assessment could influence the design and layout of the engineered system with respect to the structural features of its host rock formation. (author). 8 refs., 2 figs

Field tracer transport experiments at the site of Canada's underground research laboratory

International Nuclear Information System (INIS)

Frost, L.H.; Davison, C.C.; Vandergraaf, T.T.; Scheier, N.W.; Kozak, E.T.

1997-01-01

To gain a better understanding of the processes affecting solute transport in fractured crystalline rock, groundwater tracer experiments are being performed within natural fracture domains and excavation damage zones at various scales at the site of AECL's Underground Research Laboratory (URL). The main objective of these experiments is to develop and demonstrate methods for characterizing the solute transport properties within fractured crystalline rock. Estimates of these properties are in turn being used in AECL's conceptual and numerical models of groundwater flow and solute transport through the geosphere surrounding a nuclear fuel waste disposal vault in plutonic rock of the Canadian Shield. (author)

Canadian Food Irradiation Facilities; Installations Canadiennes d'Irradiation des Aliments; Kanadskie ustanovki dlya oblucheniya pishchevykh produktov; Instalaciones de Irradiacion de Alimentos en el Canada

Energy Technology Data Exchange (ETDEWEB)

Warland, H. M.F.; MacQueen, K. F. [Atomic Energy of Canada Ltd., Commercial Products, Ottawa (Canada)

1966-11-15

Atomic Energy of Canada Limited (AECL) began work on the irradiation of potatoes in 1956, using spent fuel rods as the radiation source. In 1958 the first Gammacell 220, a self-contained irradiator, was designed and manufactured by AECL, and cobalt-60 was then used exclusively in the food irradiation programme. In 1960 the first food and drug clearance was obtained for potatoes. The next stage was to demonstrate to the potato industry that cobalt-60 was a safe, simple and reliable tool, and that irradiation would inhibit sprouting under field conditions. A mobile irradiator was designed and produced by AECL in 1961 to carry out this pilot-plant programme. The irradiator was mounted on a fully-equipped road trailer and spent the 1961/1962 season irradiating one million pounds of potatoes at various points in Eastern Canada. In 1965 the first commercial food irradiator was designed and built by AECL for Newfield Products, Ltd. Whilst the potato programme was under way, AECL initiated co-operative programmes with Canadian food research laboratories, using additional Gammacells. In 1960, AECL constructed an irradiation facility in a shielded room at its own plant in Ottawa for the irradiation of larger objects, such as sides of pork and stems of bananas. During 1963 the mobile irradiator, already a most useful tool, was made more versatile when its source strength was increased and it was equipped with a product cooling system and van air conditioning. Following these modifications, the unit was employed in California for the irradiation of a wide spectrum of fruits at the United States Department of Agriculture Station in Fresno. The Gammacell, mobile irradiator, shielded-room facility, the commercial food irradiator and some of the main food programmes are described in detail. There is an increasing amount of interest in irradiation by the food industry, and prospects are encouraging for future installations. (author) [French] L'Atomic Energy of Canada Limited'(AECL

Summary of the Environmental Impact Statement on the concept for disposal of Canada's nuclear fuel waste

International Nuclear Information System (INIS)

1994-01-01

This is the Summary of the Environmental Impact Statement (EIS) prepared by Atomic Energy of Canada Limited (AECL) on the concept for disposal of Canada's nuclear fuel waste. The proposed concept is a method for geological disposal, based on a system of natural and engineered barriers. The EIS provides information requested by the Environmental Assessment Panel reviewing the disposal concept and presents AECL's case for the acceptability of the concept. The introductory chapter of this Summary provides background information on several topics related to nuclear fuel waste, including current storage practices for used fuel, the need for eventual disposal of nuclear fuel waste, the options for disposal, and the reasons for Canada's focus on geological disposal. Chapter 2 describes the concept for disposal of nuclear fuel waste. Because the purpose of implementing the concept would he to protect human health and the natural environment far into the future, we discuss the long-term performance of a disposal system and present a case study of potential effects on human health and the natural environment after the closure of a disposal facility. The effects and social acceptability of disposal would depend greatly on how the concept was implemented. Chapter 3 describes AECL's proposed approach to concept implementation. We discuss how the public would be involved in implementation; activities that would be undertaken to protect human health, the natural environment, and the socio-economic environment; and a case study of the potential effects of disposal before the closure of a disposal facility. The last chapter presents AECL's Conclusion, based on more than 15 years of research and development, that implementation of the disposal concept represents a means by which Canada can safely dispose of its nuclear fuel waste. This chapter also presents AECL's recommendation that Canada progress toward disposal of its nuclear fuel waste by undertaking the first stage of concept

Impact of modules on the ACR construction schedule

International Nuclear Information System (INIS)

Choy, Ed; Elgohary, Medhat; Fairclough, Neville; Yu, Stephen; Murayama, Kouichi; Miura, Jun; Kawahata, Junichi

2003-01-01

The ACR (Advanced CANDU Reactor), developed by Atomic Energy of Canada Ltd. (AECL), is designed with constructability considerations as a major requirement during all project phases from the concept design stage to the detail design stage. For ACR-700, a project schedule of 48 months has been developed for the nth replicated unit with a 36 month construction period duration from First Concrete to Fuel Load. AECL, recognizing the immense benefit of collective experience, is partnering with Hitachi Ltd in the development of the ACR power plant design. AECL has gained valuable experience in implementing new construction methods at the Qinshan (Phase III) twin unit CANDU 6 plant in China, and Hitachi likewise has enjoyed success in modular construction of ABWRs in Japan. Utilizing these experiences, AECL is developing the ACR nuclear steam plant (NSP) and Hitachi is developing the Turbine Building. An overall construction strategy, which builds on the success of these construction methods from the nuclear power plant developments in China and Japan, has been developed for the ACR. The overall construction strategy comprises the 'Open Top' construction technique using a Very Heavy Lift crane, parallel construction activities, with extensive modularization and prefabrication. Modules and prefabrications are major features of the ACR design, resulting in an excess of 80% of Reactor Building internal work being completed as modules or as very streamlined traditional construction. This paper reviews the ACR construction strategy and provides examples of modules and how they impact on the ACR construction schedule. In conclusion, the ACR-700 is designed using the latest, proven construction methods to achieve a 36 month construction period for the nth replicated unit. (author)

Experiments in ZED-2 to study the physics of low-void reactivity fuel in CANDU

International Nuclear Information System (INIS)

Zeller, M.B.; Celli, A.; McPhee, G.P.

1994-01-01

Prospective CANDU clients have indicated a desire for a zero or negative coolant void reactivity. In response to this market requirement AECL Research and AECL CANDU are jointly developing and testing a Low-Void Reactivity Fuel (LVRF) bundle, which will be retrofitable to the current generation of CANDU reactors. An important component of the LVRF program is the undertaking of reactor-physics experiments in the zero-energy ZED-2 lattice test facility at Chalk River Laboratories. Preliminary void-reactivity measurements have already been performed in ZED-2 using a limited amount of the prototype fuel. These experiments were to provide a proof-of-principle for the LVRF concept. A more comprehensive set of experiments are planned for later this year. Experiments to be performed include: measuring the critical buckling of CANDU-type lattices containing LVRF, with and without coolant in the channels; measuring the reactivity effect of heating the LVRF fuel and coolant in ZED-2 hot channels; and measuring detailed reaction rates and neutron density distributions across a LVRF bundle, in voided and D 2 O-cooled channels, by the foil activation method. This paper describes the experimental approach to be used for the study and presents calculations employing transport and diffusion theory to predict the results. The codes used for the simulations are the lattice code WIMS-AECL and the core code CONIFERS. Included in the paper are results from the preliminary measurement of void coefficient for LVRF in a ZED-2 lattice and a comparison of those results to predictions based on WIMS-AECL calculations. (author). 3 refs., 1 tab., 10 figs

Validation of WIMS-CANDU using Pin-Cell Lattices

International Nuclear Information System (INIS)

Kim, Won Young; Min, Byung Joo; Park, Joo Hwan

2006-01-01

The WIMS-CANDU is a lattice code which has a depletion capability for the analysis of reactor physics problems related to a design and safety. The WIMS-CANDU code has been developed from the WIMSD5B, a version of the WIMS code released from the OECD/NEA data bank in 1998. The lattice code POWDERPUFS-V (PPV) has been used for the physics design and analysis of a natural uranium fuel for the CANDU reactor. However since the application of PPV is limited to a fresh fuel due to its empirical correlations, the WIMS-AECL code has been developed by AECL to substitute the PPV. Also, the WIMS-CANDU code is being developed to perform the physics analysis of the present operating CANDU reactors as a replacement of PPV. As one of the developing work of WIMS-CANDU, the U 238 absorption cross-section in the nuclear data library of WIMS-CANDU was updated and WIMS-CANDU was validated using the benchmark problems for pin-cell lattices such as TRX-1, TRX-2, Bapl-1, Bapl-2 and Bapl-3. The results by the WIMS-CANDU and the WIMS-AECL were compared with the experimental data

Digital control for the Penn State Breazeale reactor

International Nuclear Information System (INIS)

Raiskums, G.A.

1991-01-01

Digital control has been an integral part of Canada deuterium uranium (CANDU) nuclear power reactor technology since the 1960s. Much of the high CANDU production reliability can be attributed to the fault-tolerant and flexible control algorithms achievable with digital control. Atomic Energy of Canada Limited (AECL) has now transported this technology to research reactors, using industrial-grade microcomputers to solve equipment aging and spares obsolescence problems so prevalent at older installations. The open architecture of the Intel 8086-based computers provides for wide availability and reasonably priced, quality hardware from numerous sources. AECL recently supplied the Pennsylvania State University Breazeale Reactor (PSBR) with a new console containing a digital control and monitoring system. The reactor safety system (RSS) was also replaced with hardwired relay logic and truly analog state-of-the-art wide range nuclear instrumentation supplied by AECL's subcontractor, Gamma-Metrics. Retaining analog hardware for the mandated RSS functions was key to minimizing licensing efforts and the extensive verification and validation that would be required for safety system software. This paper elaborates on the digital control and monitoring portion of the PSBR console replacement, with emphasis on the key system objectives

Quality assurance in management of geotechnical experiments for nuclear waste disposal

International Nuclear Information System (INIS)

Dormuth, K.W.; Simmons, G.R.

1992-01-01

Research and development (R and D) of technology for the disposal of nuclear fuel waste in plutonic rock is being undertaken in the Canadian Nuclear Fuel Waste Management Program, jointly funded by Atomic Energy of Canada Limited (AECL) Research and Ontario Hydro under the auspices of the CANDU Owner's Group. A major component of the R and D is geotechnical research to improve the understanding of the response of the host rock to a waste repository; investigate the interactions between the waste package, sealing systems, and rock; elucidate geotechnical factors affecting potential transport of waste elements from the repository; and establish and refine techniques and procedures for repository engineering. Nine major experimental activities are currently in various stages of planning and implementation at AECL's Underground Research Laboratory (URL). A general description of a quality assurance (QA) program developed at AECL for R and D on nuclear waste disposal has been published previously. This QA program is project-oriented and is designed specifically for and R and D environment. The full application of the QA program is being phased into the management of the operating phase experiments because some activities were under way prior to establishment of the QA program

AECL's excavation stability study - summary of observations

International Nuclear Information System (INIS)

Read, R.S.; Chandler, N.A.

1996-05-01

The Excavation Stability Study (ESS) was conducted at the 420 Level of the Underground Research Laboratory (URL) to evaluate stability and the extent of excavation damage in tunnels as a function of tunnel geometry and orientation, geology, and excavation method. A series of ovaloid and circular openings were used to achieve different boundary stress levels and near-field stress distributions to assess the effect of tunnel geometry on damage development. Several of these openings had sections in both granite and granodiorite lithology, providing a comparison of damage in rock types with different strength characteristics. Damage around circular tunnels (one excavated by drill-and-blast, the other by mechanical means) was also investigated. The study.showed that mechanically stable openings can be excavated in the most adverse stress conditions at the 420 Level of the URL. In addition, it was shown that tunnel stability is sensitive to tunnel shape, variations in geology, and to some extent, the excavation method. Findings of the study are relevant in developing design criteria, and in assessing the feasibility of constructing large ovaloid openings in adverse stress conditions. This report summarizes the preliminary observations related to tunnel stability and excavation damage. (author). 8 refs., 7 tabs., 23 figs

Proceedings of DUPIC fuel workshop 97

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-07-01

The researchers discuss the technical aspects of DUPIC fuel fabrication in the workshop as follows; (1) The DUPIC fuel development program in KAERI (2) AECL`s progress in developing the DUPIC fuel fabrication process (3) Mechanical decladding (4) Nonproliferation and safeguards aspects of the DUPIC fuel cycle concept (5) Assessment of DUPIC fuel compatibility with CANDU-6 (6) The development of combination software for spent PWR fuel to fabricate the homogeneous DUPIC fuel (7) Thermodynamic properties of the DUPIC fuel and its performance (8) Captural properties of cesium and ruthenium (9) A secondary fuel removal process : Plasma processing (10) Technology development for DUPIC process safeguards.

Information management for decommissioning projects

International Nuclear Information System (INIS)

LeClair, A.N.; Lemire, D.S.

2011-01-01

This paper explores the importance of records and information management for decommissioning projects. Key decommissioning information and elements of a sound information management strategy are identified. Various knowledge management strategies and tools are discussed as opportunities for leveraging decommissioning information. The paper also examines the implementation of Atomic Energy of Canada Limited's (AECL) strategy for the long term preservation of decommissioning information, and its initiatives in leveraging of information with the application of several knowledge management strategies and tools. The implementation of AECL's strategy illustrates common as well as unique information and knowledge management challenges and opportunities for decommissioning projects. (author)

New build CANDU in Canada - development and application of information management systems for latest construction technology

International Nuclear Information System (INIS)

Asakura, S.; Akane, N.; Byrne, J.; Canas, B.; Kereliuk, S.; Akahori, S.

2007-01-01

In the wake of recent events representing growing nuclear energy interest in Canada, AECL and Hitachi are sharing each other's expertise as each company has its own unique and unrivalled capability in managing new build construction projects. This paper addresses some of the key strategies used to execute successfully a New CANDU build project, by focusing on recent developments and implementations in the construction and project management fields and by highlighting the use of cutting edge information technology. These strategies are designed to achieve and maximize their benefit to the New Build CANDU project team, to AECL/Hitachi as well as customers, partners and suppliers. (author)

CANDU in the next century

International Nuclear Information System (INIS)

Meneley, D.A.; Torgerson, D.F.

1997-01-01

AECL's main product line is available today in two designs, designated as CANDU 6 and CANDU 9. Each of these is based on successfully operating pressurized-heavy-water nuclear plants. Several new CANDU stations are under construction or planned around the world. The author presents plant concepts which may evolve from today's products during the 21st century, indicating the particular development directions which might be followed by AECL product development depending on the future competitive environment, economics, and market circumstances. This study shows that the CANDU energy supply system is sufficiently flexible to be adapted into widely varying circumstances over the next century and beyond

New opportunities from nuclear R and D

International Nuclear Information System (INIS)

Hart, R.G.

1984-01-01

The author presents a new initiative within Atomic Energy of Canada Ltd. (AECL), the intention to look for spin-off business opportunities from main-line research and development. In 1982 AECL began encouraging ideas for spin-off applications. Some problems were encountered: the reluctance of staff to divert attention from the CANDU program; resource allocation; difficulties in getting market input; and difficulties in deciding what to license and what to retain as an in-house business opportunity. Successes have come in the areas of using CANDU technology in LWRs, SLOWPOKE reactors, industrial accelerators, stable isotope production, intelligent sensing systems, and deuterated lucite for fibre optics. (L.L.)

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)

ACR: Licensing and design readiness

International Nuclear Information System (INIS)

Alizadeh, A.

2009-01-01

Full text The Canadian nuclear technology has a long history dating back to the 1940s. In this regard, Canada is in a unique situation, shared only by a very few countries, where original nuclear power technology has been invented and further developed. Canadian Nuclear Safety Commission (CNSC), then called AECB, was established in 1946. CNSC focuses on nuclear security, nuclear safety, establishing health and safety regulations, and has also played an instrumental role in the formation of the IAEA. CNSC has provided assistance to the establishment of regulatory authorities in AECL's client countries such as Korea, Argentina, China and Romania. AECL has developed the Gen III+ ACR 1000 as evolutionary advancement of the current CANDU 6 reactor. ACR-1000 has evolved from AECL's in depth experience with CANDU systems, components, and materials, as well as the feedback received from owners and operators of CANDU plants. The ACR-1000 design retains the proven strengths and features of CANDU reactors, while incorporating innovations and state-of-the-art technology. It also features major improvements in economics, inherent safety characteristics, and performance. ACR-1000 has completed its Basic Engineering, has advanced in the licensing process in Canada, and is ready for deployment in Canadian and world markets. EC6 is an evolution of CANDU 6 and is a Gen III natural uranium fuelled reactor. Its medium size and potential for fuel localization and advanced fuel cycles is an optimal strategic solution in many markets.AECL's reactor products are shown to be compliant with a variety of licensing and regulatory requirements. These include the new CNSC DRD-337, IAEA NS-R1, and EUR. This allows the countries interested in CANDU reactor products to be confident of its licensing in their own regulatory regimes.

The Qinshan phase III project-a successful model of sino-canadian cooperation

International Nuclear Information System (INIS)

Pang, S.H.H.; Alikhan, S.; Gu Jun

2005-01-01

The Qinshan Phase III (CANDU) Project, the largest-scale cooperative project between China and Canada, was completed in 2003 well in advance of the schedule and 10% under budget. The Third Qinshan (Phase III) Nuclear Power Plant (TQNPP) was built in record times: Unit 1 achieved commercial operation on December 31, 2002 and Unit 2 on July 20, 2003, 43 days and 115 days ahead of schedule respectively. Improvements in design and construction methods allowed Unit 1 to be constructed in 51.5 months from First Concrete to Criticality - a record in China for nuclear power plants. The key factors are project management and project management tools, quality assurance, construction methods, electronic documentation with configuration control that provides up-to-date on-line information, CADDS design linked with material management and control. New design and construction techniques were introduced by combining conventional AECL practices with working experiences in China. The most advanced tools and techniques for achieving optimum construction quality, schedule and cost were used. Successful application of advanced project management methods and tools has benefited TQNPC in its subsequent plant operation, and the Chinese contractors in advancing their capabilities in future nuclear projects in China as well as enhancing their opportunities internationally. Excellent co-operation and teamwork within the integrated TQNPC/AECL Commissioning Team with well documented QA program, process and procedures also contributed to the remarkable success of the Project. AECL's initial assessment, based on lessons learned, showed that the project schedule could readily be reduced to 66 months and the capital costs reduced by 25% for a replication project. AECL is building on this experience and successful results of TQNPP in its Advanced CANDU Reactor TM (ACR TM ) ** design. (authors)

Proposed Atomic Energy of Canada Ltd. 99Mo waste calcination process

International Nuclear Information System (INIS)

Ramey, D.W.; Haas, P.A.; Malkemus, D.W.; McGinnis, C.P.; Meyers, E.S.; Patton, B.D.; Birdwell, J.F.; Jubin, R.T.; Coltharp, K.A.

1994-10-01

Atomic Energy of Canada Limited (AECL), at its Chalk River Laboratory, generates from 3000 to 5000 L/year of high-level fissile waste solution from the production of 99 Mo. In this Mo process, highly enriched uranium (93 wt % 235 U, total uranium basis) contained in uranium-aluminum alloy target rods is irradiated to produce the 99 Mo product. The targets are removed from the reactor and dissolved in a mercury nitrate-catalyzed reaction with nitric acid. The 99 Mo product is then recovered by passing the solution through an alumina (Al 2 O 3 ) column. During discussions with personnel from the Oak Ridge National Laboratory (ORNL) on September 10, 1992, the ORNL-developed technology formerly applied to the solidification of aqueous uranium waste (Consolidated Edison Uranium Solidification Program or CEUSP) was judged potentially applicable to the AECL 99 Mo waste. Under a Work-for-Others contract (no. ERD-92-1132), which began May 24, 1993, ORNL was tasked to determine the feasibility of applying the CEUSP (or a similar) calcination process to solidify AECL's 99 Mo waste for > 30 years of safe dry storage. This study was to provide sufficient detailed information on the applicability of a CEUSP-type waste solidification process to allow AECL to select the process which best suited its needs. As with the CEUSP process, evaporation of the waste and a simultaneously partial destruction of acid by reaction with formaldehyde followed by in situ waste can thermal denitration waste was chosen as the best means of solidification. Unlike the CEUSP material, the 99 Mo waste has a considerable number of problem volatile and semivolatile constituents which must be recovered in the off-gas treatment system. Mercury removal before calcination was seen as the best option

Transport modeling of sorbing tracers in artificial fractures

International Nuclear Information System (INIS)

Keum, Dong Kwon; Baik, Min Hoon; Park, Chung Kyun; Cho, Young Hwan; Hahn, Phil Soo.

1998-02-01

This study was performed as part of a fifty-man year attachment program between AECL (Atomic Energy Canada Limited) and KAERI. Three kinds of computer code, HDD, POMKAP and VAMKAP, were developed to predict transport of contaminants in fractured rock. MDDM was to calculate the mass transport of contaminants in a single fracture using a simple hydrodynamic dispersion diffusion model. POMKAP was to predict the mass transport of contaminants by a two-dimensional variable aperture model. In parallel with modeling, the validation of models was also performed through the analysis of the migration experimental data obtained in acrylic plastic and granite artificial fracture system at the Whiteshell laboratories, AECL, Canada. (author). 34 refs., 11 tabs., 76 figs

Summary of feasibility studies on in situ disposal as a decommissioning option for nuclear facilities

International Nuclear Information System (INIS)

Helbrecht, R.A.

2002-01-01

A scoping study was conducted over the period 1998-2000 to consider the feasibility of in situ disposal as a decommissioning option for AECL's Nuclear Power Demonstration Reactor located at Rolphton, Ontario. The results of a detailed assessment are summarized and the study concludes that in situ disposal appears feasible. Additional work required to confirm the results is also identified. A second in situ component, contaminated Winnipeg River sediments at AECL's Whiteshell Laboratory located in Manitoba, was also evaluated. That study concluded that in situ abandonment would have no adverse impact on aquatic life, humans and the environment. A summary of the study is presented as an appendix to the report. (author)

Chernobyl - a Canadian technical perspective

International Nuclear Information System (INIS)

Howieson, J.Q.; Snell, V.G.

1987-01-01

In this report we present the design review done to date in Canada by AECL. From the Canadian point of view it covers: 1) relevant information on the Chernobyl design and the accident, both as presented by the Soviets at the Post-Accident Review Meeting (PARM) held in Vienna from August 25-29, 1986, and as deduced from publicly available Soviet documentation; and 2) details of AECL's technical review of the CANDU PHWR (Pressurized Heavy Water Reactor) against the background of the Chernobyl accident, and implications of the Chernobyl accident. Reviews of operational aspects are underway by the Canadian electrical utilities and a review by the Canadian regulatory agency (the Atomic Energy Control Board) is near completion

Transport modeling of sorbing tracers in artificial fractures

Energy Technology Data Exchange (ETDEWEB)

Keum, Dong Kwon; Baik, Min Hoon; Park, Chung Kyun; Cho, Young Hwan; Hahn, Phil Soo

1998-02-01

This study was performed as part of a fifty-man year attachment program between AECL (Atomic Energy Canada Limited) and KAERI. Three kinds of computer code, HDD, POMKAP and VAMKAP, were developed to predict transport of contaminants in fractured rock. MDDM was to calculate the mass transport of contaminants in a single fracture using a simple hydrodynamic dispersion diffusion model. POMKAP was to predict the mass transport of contaminants by a two-dimensional variable aperture model. In parallel with modeling, the validation of models was also performed through the analysis of the migration experimental data obtained in acrylic plastic and granite artificial fracture system at the Whiteshell laboratories, AECL, Canada. (author). 34 refs., 11 tabs., 76 figs.

Development and implementation of a construction environmental protection program at a solid radioactive waste management facility

Energy Technology Data Exchange (ETDEWEB)

Wong, T.S. [Atomic Energy of Canada Limited, Mississauga, Ontario (Canada); Bishop, T. [Atomic Energy of Canada Limited, Saint John, New Brunswick (Canada); Hickman, C.N. [Point Lepreau Generating Station, Saint John, New Brunswick (Canada)

2007-07-01

Refurbishment of ageing nuclear stations has great economic and environmental benefits, including reduced greenhouse gas emissions. The Government of New Brunswick (NB) decided in 2005 to refurbish the Point Lepreau Generating Station with Atomic Energy of Canada Limited (AECL) as the general contractor. The project includes construction of additional radioactive waste management facilities. AECL developed, for the construction project, an environmental protection program to comply with commitments made during the environmental assessment process, and regulatory requirements. The program covers detailed environmental plans, training courses, and engagement of consultants to provide training and conduct monitoring of the construction activities. Construction related environmental effects have been successfully mitigated and the monitoring results indicate compliance with all environmental requirements. (author)

Power and the future generation

International Nuclear Information System (INIS)

Rummery, T.E.

1994-01-01

In this keynote address, the author, who was acting president of AECL at the time of the conference, emphasizes the importance of nuclear energy to Canada, and its future importance to the developing countries. In 1992, nuclear energy supplied 15% of Canada's electricity, employed 30,000 people in Canada, created at least 10,000 jobs in other sectors, generated federal tax revenues of C$700 million, and by supplanting coal and gas imports saved about C$1 billion. Export sales prospects in China, Korea, Turkey, the Philippines, Indonesia and Thailand are indicated. AECL is presently undergoing reorganization for greater efficiency. A public opinion poll indicated about 70% Canadian public support for nuclear energy

Particle-tracking code (track3d) for convective solute transport modelling in the geosphere: Description and user`s manual; Programme de reperage de particules (track3d) pour la modelisation du transport par convection des solutes dans la geosphere: description et manuel de l`utilisateur

Energy Technology Data Exchange (ETDEWEB)

Nakka, B W; Chan, T

1994-12-01

A deterministic particle-tracking code (TRACK3D) has been developed to compute convective flow paths of conservative (nonreactive) contaminants through porous geological media. TRACK3D requires the groundwater velocity distribution, which, in our applications, results from flow simulations using AECL`s MOTIF code. The MOTIF finite-element code solves the transient and steady-state coupled equations of groundwater flow, solute transport and heat transport in fractured/porous media. With few modifications, TRACK3D can be used to analyse the velocity distributions calculated by other finite-element or finite-difference flow codes. This report describes the assumptions, limitations, organization, operation and applications of the TRACK3D code, and provides a comprehensive user`s manual.

Environmental assessment as a planning tool for the decommissioning of a nuclear research facility in Canada

International Nuclear Information System (INIS)

Klukas, M.H.; Grondin, D.J.; Helbrecht, R.A.

2002-01-01

Whiteshell Laboratories, a nuclear research facility operated by Atomic Energy of Canada Ltd. (AECL), have provided research facilities for the Canadian Nuclear Industry since the early 1960's. In 1997, AECL made a business decision to discontinue research programs and operations at the laboratories. Shortly thereafter the decision was made in agreement with the Federal Government of Canada to decommission the laboratories. In compliance with its own policy and to meet the requirements of the Canadian Legislation, AECL assessed the potential environmental effects of the project. The Environmental Assessment included studies to evaluate he feasibility of leaving two major project components in place; low-level radioactive waste in trenches located at the Whiteshell Laboratories site and river sediments contaminated from operational effluent releases. For both project components, it was determined that managing the wastes in the existing location was environmentally sound. An extensive follow-up program, comprising of additional monitoring and analysis to verify these findings will be implemented. As a result of these assessments and the assessments for other project components it was concluded that the project was not likely to cause significant adverse effects. The assessment decision was accepted by the Minister of the Environment in 2002 April. (author)

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

Operating Experience of MACSTOR Modules at CANDU 6 Stations

International Nuclear Information System (INIS)

Beaudoin, Robert R.

2005-01-01

Over the last three decades, Atomic Energy of Canada Limited (AECL) has contributed to the technology development and implementation of dry spent fuel management facilities in Canada, Korea and Romania During that period, AECL has developed a number of concrete canister models and the MACSTOR200 module, a medium size air-cooled vault with a 228 MgU (Mega grams of Uranium) capacity. AECL's dry storage technologies were used for the construction of eight large-scale above ground dry storage facilities for CANDU spent fuel. As of 2005, those facilities have an installed capacity in excess of 5,000 MgU. Since 1995, the two newest dry storage installations built for CANDU 6 reactors at Gentilly 2 (Canada) and Cernavoda (Romania) used the MACSTOR 200 module. Seven such modules have been built at Gentilly 2 during the 1995 to 2004 period and one at Cernavoda in 2003. The construction and operating experience of those modules is reviewed in this paper. The MACSTOR 200 modules were initially designed for a 50-year service life, with recent units at Gentilly 2 licensed for a 100-year service life in a rural (non-maritime) climate. During the 1995-2005 period, six of the eight modules were loaded with fuel. Their operation has brought a significant amount of experience on loading operations, performance of fuel handling equipment, radiation shielding, heat transfer, monitoring of the two confinement boundaries and radiation dose to personnel. Heat dissipation performance of the MACSTOR 200 was initially licensed using values derived from full scale tests made at AECL's Whiteshell Research Laboratories, that were backed-up by temperature measurements made on the first two modules. Results and computer models developed for the MACSTOR 200 module are described. Korea Hydro and Nuclear Power (KHNP) and its subsidiary Nuclear Environment Technology Institute (NETEC), in collaboration with Hyundai Engineering Company Ltd. (HEC) and AECL, are developing a new dry storage module to

Considering plant life management influences on new plant design

International Nuclear Information System (INIS)

Dam, R.F.; Choy, E.; Soulard, M.; Nickerson, J.H.; Hopwood, J.

2003-01-01

After operating successfully for more than half their design life, owners of CANDU reactors are now engaging in Plant Life Management (PLiM) activities to ensure not only life attainment, but also life extension. For several years, Atomic Energy of Canada Ltd. (AECL) has been working with domestic and offshore CANDU utilities on a comprehensive and integrated CANDU PLiM program that will see existing CANDU plants successfully and reliably operate through their design life and beyond. To support the PLiM program development, a significant level of infrastructure has been, and continues to be, developed at AECL. This includes the development of databases that document relevant knowledge and background to allow for a more accessible and complete understanding of degradation issues and the strategies needed to deal with these issues. As the level of integration with various project, services and R and D activities in AECL increases, this infrastructure is growing to encompass a wider range of design, operations and maintenance details to support comprehensive and quantitative assessment of CANDU stations. With the maturation of the PLiM program, these processes were adapted for application to newer plants. In particular, a fully integrated program was developed that interrelates the design basis, operations, safety, and reliability and maintenance strategies, as applied to meet plant design goals. This has led to the development of the maintenance-based design concept. The various PLiM technologies, developed and applied in the above programs with operating stations, are being modified and tailored to assist with the new plant design processes to assure that ACR- Advanced CANDU Reactor meets its targets for operation, maintenance, and lifetime performance. Currently, the ACR, developed by Atomic Energy of Canada Ltd. (AECL), is being designed with features to increase capacity factors, to reduce the risk of major equipment failures, to improve access to key components

Operator companion

International Nuclear Information System (INIS)

Natalizio, A.; Anderson, J.W.D.; Sills, H.E.

1988-01-01

Abundant, cheap computing power has provided industry with a far greater opportunity than was available one or two decades ago to automate industrial processes and to improve the man-machine interface. Exciting innovations in knowledge representation methods arising from artificial intelligence research pave the way for advanced support systems for assisting plant operators. AECL has recognized the importance of knowledge based system technology, particularly expert systems, in the achievement of this objective and also, as a strategic technology to be fully exploited in the next generation of CANDU reactors. Operator Companion, an expert system intended to diagnose plant faults and advise the operator on appropriate restoring or corrective actions, is a major undertaking which is receiving support within the research and engineering groups of AECL

Characterization of natural colloids sampled from a fractured granite groundwater

Energy Technology Data Exchange (ETDEWEB)

Baik, Min Hoon; Keum, Dong Kwon; Hahn, Pil Soo [Korea Atomic Energy Research Institute, Taejeon (Korea); Vilks, Peter [AECL Whiteshell Laboratories (Canada)

2000-02-01

This study was carried out as a part of international joint study of KAERI with AECL. The main purpose of this study is to analyze the physicochemical characteristics and sorption properties of natural colloids sampled from the deep fractured granite groundwater located in the Underground Research Laboratory (URL) of AECL. Physicochemical characteristics such as composition, size distribution, and concentrations of natural colloids was analyzed. This study will be basic data for the analysis of the effect of colloids on the radionuclide migration in a geological medium. This study may provide information for the evaluation of the roles and effects of colloids in the safety and performance assessment of a possible future radioactive waste repository. 20 refs., 8 figs., 8 tabs. (Author)

Electron-processing technology: A promising application for the viscose industry

Science.gov (United States)

Stepanik, T. M.; Rajagopal, S.; Ewing, D.; Whitehouse, R.

1998-06-01

In marketing its IMPELA ® line of high power, high-throughput industrial accelerators, Atomic Energy of Canada Limited (AECL) is working with viscose (rayon) companies world-wide to integrate electron-processing technology as part of the viscose manufacturing process. The viscose industry converts cellulose wood pulp into products such as staple fiber, filament, cord, film, packaging, and non-edible sausage casings. This multibillion dollar industry is currently suffering from high production costs, and is facing increasingly stringent environmental regulations. The use of electron-treated pulp can significantly lower production costs and can provide equally significant environmental benefits. This paper describes our current understanding of the benefits of using electron-treated pulp in this process, and AECL's efforts in developing this technology.

Validation of the ORIGEN-S code for predicting radionuclide inventories in used CANDU fuel

International Nuclear Information System (INIS)

Tait, J.C.; Gauld, I.; Kerr, A.H.

1995-01-01

The safety assessment being conducted by AECL Research for the concept of deep geological disposal of used CANDU UO 2 fuel requires the calculation of radionuclide inventories in the fuel to provide source terms for radionuclide release. This report discusses the validation of selected actinide and fission-product inventories calculated using the ORIGEN-S code coupled with the WIMS-AECL lattice code, using data from analytical measurements of radioisotope inventories in Pickering CANDU reactor fuel. The recent processing of new ENDF/B-VI cross-section data has allowed the ORIGEN-S calculations to be performed using the most up-to-date nuclear data available. The results indicate that the code is reliably predicting actinide and the majority of fission-product inventories to within the analytical uncertainty. ((orig.))

AECL programs for new applications for nuclear energy

International Nuclear Information System (INIS)

Robertson, J.A.L.

1982-05-01

This document reports the activities of the New Applications Steering Committee (NASC) of Atomic Energy of Canada Ltd. The NASC is intended to develop future RβD programs, and more specifically to promote certain existing ideas that have not yet become part of established programs, stimulate new idaas, identify needs and opportunities for RβD, evaluate proposals for RβD programs, initiate action on new ideas, and provide feedback to a staff who may be expected to generate ideas. Major areas and technologies that have been studied by the NASC and are covered in this report include oil substitution by nuclear heat and by electricity, energy storage and the role of hydrogen, nuclear energy in liquid fuel production, assessment of Canadian energy resources, and computer modelling of energy systems

Reorganization of AECL and the future marketing program

International Nuclear Information System (INIS)

Donnelly, James

Atomic Energy of Canada Ltd. Engineering Co. has been reorganized to support the new emphasis on foreign sales of CANDU reactors. Much has been learned from reactor sales to Argentina, Korea, and Romania, but Canada needs to sell one 600 MWe reactor a year in order to avoid a decline in its nuclear industry. (LL)

1979-80 annual report

International Nuclear Information System (INIS)

1980-01-01

Atomic Energy of Canada Ltd. added a fifth semi-autonomous unit, Atomic Energy of Canda International Company, in June 1979, to assist in the company's pursuit of world wide acceptance of the CANDU system. Evaluations of reactor safety following the Three Mile Island accident, public hearings in Ontario, and the report of the Porter Commission all reaffirm the safety of Canadian nuclear power plants. Continuing efforts were made to bring information on nuclear power to the public. AECL continued to participate in the International Fuel Cycle Evaluation; INFCE findings confirm the competitiveness of the CANDU reactor. Emphasis in the AECL research program was on safety, safeguards, health effects of radiation, waste management and new applications for nuclear power. The Radiochemical Company had sales of $49 million, with 97% of its business being in the export market. The Engineering Company is working on eight major projects totalling 12000 MW(e) as well as providing consulting service for the CANDU stations already in operation. The Chemical Company produced over 5000000 kg of heavy water. AECL revenues were $497.1 million in 1979, an increase of 41.6 percent over the previous year. Research and development expenditures increased 2 percent to $127.2 million. Net income for the year increased to $11.2 million from $5.2 million for the previous year. (LL)

Burnup calculation of a CANDU6 reactor using the Serpent and MCNP6 codes

Energy Technology Data Exchange (ETDEWEB)

Hussein, M.S.; Bonin, H.W., E-mail: mohamed.hussein@rmc.ca, E-mail: bonin-h@rmc.ca [Royal Military College of Canada, Dept. of Chemistry and Chemical Engineering, Kingston, ON (Canada); Lewis, B.J., E-mail: Brent.Lewis@uoit.ca [Univ. of Ontario Inst. of Tech., Faculty of Energy Systems and Nuclear Science, Oshawa, ON (Canada)

2014-07-01

A study of fuel burnup for the CANDU6 reactor is carried out to validate the most recent versions of the probabilistic transport code (MCNP6) and the continuous energy burnup calculation code (Serpent). These two codes allow for 3-D geometry calculation accounting for a detailed analysis without unit-cell homogenization. On the other hand, the WIMS-AECL computer program is used to model neutron transport in nuclear-reactor lattices for design, safety analysis, and operation. It works with two-dimensional regions and can perform collision probability calculations for a periodic structure of the lattice cell. In the present work, the multiplication factor, the total flux and fuel burnup could be calculated for a CANDU6 nuclear reactor based on the GENTILLY-2 core design. The MCNP6 and Serpent codes provide a calculation of the track length estimated flux per neutron source. This estimated flux is then scaled with normalization to the reactor power in order to provide a flux in unit of n/cm{sup 2}s. Good agreement is observed between the actual total flux calculated by MCNP6, Serpent and WIMS-AECL. The effective multiplication factors of the whole core CANDU6 reactor are further calculated as a function of burnup and further compared to those calculated by WIMS-AECL where excellent agreement is also obtained. (author)

Burnup calculation of a CANDU6 reactor using the Serpent and MCNP6 codes

International Nuclear Information System (INIS)

Hussein, M.S.; Bonin, H.W.; Lewis, B.J.

2014-01-01

A study of fuel burnup for the CANDU6 reactor is carried out to validate the most recent versions of the probabilistic transport code (MCNP6) and the continuous energy burnup calculation code (Serpent). These two codes allow for 3-D geometry calculation accounting for a detailed analysis without unit-cell homogenization. On the other hand, the WIMS-AECL computer program is used to model neutron transport in nuclear-reactor lattices for design, safety analysis, and operation. It works with two-dimensional regions and can perform collision probability calculations for a periodic structure of the lattice cell. In the present work, the multiplication factor, the total flux and fuel burnup could be calculated for a CANDU6 nuclear reactor based on the GENTILLY-2 core design. The MCNP6 and Serpent codes provide a calculation of the track length estimated flux per neutron source. This estimated flux is then scaled with normalization to the reactor power in order to provide a flux in unit of n/cm 2 s. Good agreement is observed between the actual total flux calculated by MCNP6, Serpent and WIMS-AECL. The effective multiplication factors of the whole core CANDU6 reactor are further calculated as a function of burnup and further compared to those calculated by WIMS-AECL where excellent agreement is also obtained. (author)

Control of blast overpressure and vibrations at the Underground Research Laboratory

International Nuclear Information System (INIS)

Kuzyk, G.W.; Onagi, D.P.; Mohanty, B.

1991-01-01

AECL Research (AECL) has constructed an Underground Research Laboratory (URL) as a facility for research and development in the Canadian Nuclear Fuel Waste Management Program. The objectives of the program are to develop and evaluate the technology to ensure safe, permanent disposal of Canada's nuclear fuel waste. Several multidisciplinary experiments and engineering demonstrations are planned for the URL over the next ten years. In 1989, AECL excavated a test room for the Buffer/Container Experiment at the 240 Level. The blasts were designed to limit vibration and overpressure damage because the excavation was located close to existing furnishings and services that were very susceptible to blast-induced vibration and overpressure. An experimental room, which contained sensitive instrumentation, was located within 30 m of the initial blasts. A concrete floor slab, timber curtains and a bulkhead were installed to protect furnishings and services from fly-rock and overpressure. Five of the initial blasts were monitored. This paper describes the results of the monitoring program and the effectiveness of the blast design, floor slab and timber curtains and bulkhead in reducing blast overpressure and vibrations at the blast site. It is shown that greater than a 20-fold reduction in both blast vibrations and air overpressures can be achieved with specific combinations of blast design, installation of timber curtains and construction of a concrete floor slab

CRYOCOL a computer program to calculate the cryogenic distillation of hydrogen isotopes

International Nuclear Information System (INIS)

Douglas, S.R.

1993-02-01

This report describes the computer model and mathematical method coded into the AECL Research computer program CRYOCOL. The purpose of CRYOCOL is to calculate the separation of hydrogen isotopes by cryogenic distillation. (Author)

Cost and schedule reduction for next-generation Candu

International Nuclear Information System (INIS)

Hopwood, J.M.; Yu, S.; Pakan, M.; Soulard, M.

2002-01-01

AECL has developed a suite of technologies for Candu R reactors that enable the next step in the evolution of the Candu family of heavy-water-moderated fuel-channel reactors. These technologies have been combined in the design for the Advanced Candu Reactor TM1 (ACRTM), AECL's next generation Candu power plant. The ACR design builds extensively on the existing Candu experience base, but includes innovations, in design and in delivery technology, that provide very substantial reductions in capital cost and in project schedules. In this paper, main features of next generation design and delivery are summarized, to provide the background basis for the cost and schedule reductions that have been achieved. In particular the paper outlines the impact of the innovative design steps for ACR: - Selection of slightly enriched fuel bundle design; - Use of light water coolant in place of traditional Candu heavy water coolant; - Compact core design with unique reactor physics benefits; - Optimized coolant and turbine system conditions. In addition to the direct cost benefits arising from efficiency improvement, and from the reduction in heavy water, the next generation Candu configuration results in numerous additional indirect cost benefits, including: - Reduction in number and complexity of reactivity mechanisms; - Reduction in number of heavy water auxiliary systems; - Simplification in heat transport and its support systems; - Simplified human-machine interface. The paper also describes the ACR approach to design for constructability. The application of module assembly and open-top construction techniques, based on Candu and other worldwide experience, has been proven to generate savings in both schedule durations and overall project cost, by reducing premium on-site activities, and by improving efficiency of system and subsystem assembly. AECL's up-to-date experience in the use of 3-D CADDS and related engineering tools has also been proven to reduce both engineering and

Using geographical information systems in planning NLLP decommissioning and environmental restoration activities

International Nuclear Information System (INIS)

McGregor, R.; Turner, W.

2011-01-01

The Nuclear Legacy Liabilities Program (NLLP) manages Canada's nuclear legacy liabilities at Atomic Energy of Canada Limited (AECL) sites and is funded by the Government of Canada through Natural Resources Canada (NRCan). Through the first five years of the Program these two organizations have worked collaboratively to bring numerous projects to completion. In addition to the diversity of facilities and waste dealt with under the NLLP, the Program involves seven sites in three different provinces. The breadth of the Program encompasses over 20 different projects at AECL's Chalk River Laboratories (CRL) site alone, with new projects evolving as work continues. Nuclear legacy liabilities are the result of over 60 years of nuclear research and development conducted by the National Research Council of Canada (1944 to 1952) and AECL (1952 to 2006) on behalf of the Government of Canada. The liabilities consist of outdated and unused research facilities and buildings, a wide variety of buried and stored radioactive waste, and affected lands. Since 1952, AECL has safely and cost effectively managed Canada's nuclear research facilities and the waste generated by their operation. During this time AECL improved waste management technologies and developed expertise in best practices. All projects undertaken by the NLLP contain a spatial, or geographically referenced, component that can be captured in a geographic information system (GIS). From the decommissioning of a single building within the plant itself (e.g. the building location itself or spaces within the building) to the process of locating a new facility within the CRL site (e.g. location within the CRL property in three dimensions and adjacency to other communities) all these projects contain spatially referenced information. This spatial information can be captured, organized and used by the GIS software to analyze and model any number of questions. The paper will discuss projects that address a

Annual report 1998-1999

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-07-01

This is the Annual Report of the Atomic Energy of Canada Limited for the year ending March 31, 1999 and summarizes the activities of AECL during the period 1998-1999. The Activities covered in this Report include the CANDU Reactor Business, with excellent progress reported on the construction of two 700 MWe-class CANDU reactors in Qinshan, China. In the Republic of Korea, Wolsong Unit entered into commercial operation and Wolsong Unit 4 achieved sustained nuclear reaction. The Report also covers AECL's R and D and Waste Management programs. In the R and D section, the report outlines the development of the CANFLEX fuel bundle, Fuel Channels, Reactor Safety, Code Validation, Fuels and Fuel Cycles as well as Heavy Water production. Progress in the Waste Management program is also discussed.

Validation of the ORIGEN-S code for predicting radionuclide inventories in used CANDU Fuel

International Nuclear Information System (INIS)

Tait, J.C.; Gauld, I.; Kerr, A.H.

1994-10-01

The safety assessment being conducted by AECL Research for the concept of deep geological disposal of used CANDU UO 2 fuel requires the calculation of radionuclide inventories in the fuel to provide source terms for radionuclide release. This report discusses the validation of selected actinide and fission-product inventories calculated using the ORIGEN-S code coupled with the WIMS-AECL lattice code, using data from analytical measurements of radioisotope inventories in Pickering CANDU reactor fuel. The recent processing of new ENDF/B-VI cross-section data has allowed the ORIGEN-S calculations to be performed using the most up-to-date nuclear data available. The results indicate that the code is reliably predicting actinide and the majority of fission-product inventories to within the analytical uncertainty. 38 refs., 4 figs., 5 tabs

Annual report 1998-1999

International Nuclear Information System (INIS)

1999-01-01

This is the Annual Report of the Atomic Energy of Canada Limited for the year ending March 31, 1999 and summarizes the activities of AECL during the period 1998-1999. The Activities covered in this Report include the CANDU Reactor Business, with excellent progress reported on the construction of two 700 MWe-class CANDU reactors in Qinshan, China. In the Republic of Korea, Wolsong Unit entered into commercial operation and Wolsong Unit 4 achieved sustained nuclear reaction. The Report also covers AECL's R and D and Waste Management programs. In the R and D section, the report outlines the development of the CANFLEX fuel bundle, Fuel Channels, Reactor Safety, Code Validation, Fuels and Fuel Cycles as well as Heavy Water production. Progress in the Waste Management program is also discussed

Whiteshell labs closure: crisis or opportunity?

International Nuclear Information System (INIS)

Simpson, L.

2003-01-01

L. Simpson, Mayor, Local Government District of Pinawa, Manitoba, described the impacts and public concerns produced by a hastily planned and executed withdrawal of the primary employer from a dependent company town. The Whiteshell Laboratories of the Crown corporation Atomic Energy of Canada Limited (AECL) were established in Eastern Manitoba in 1963, and Pinawa was created 15 kilometres away. Located in a provincial park region, Pinawa has also become a popular holiday cottage area with 20 000 residents inside a 30-minute radius. In 1995, the AECL Reactor Safety Research Program was moved to Chalk River, and the Nuclear Waste Management Program (NWMP) was left in limbo. Commercial negotiations to go on operating business on the site broke down. The town of Pinawa, the major stakeholder, was kept at arm's length from all discussions. (author)

Environmental scan

International Nuclear Information System (INIS)

1988-01-01

Trends in current affairs and public policy that emerged in 1988 are analyzed to provide a tool for Atomic Energy of Canada's decision makers. This issue provides a general overview of the economic and energy environments; and international review of nuclear policies, equipment orders, and trends that will position Canada and AECL within the global nuclear community; a precis of Canadian public opinion polls on economic, environmental and energy issues; a summary of major trends identifies by Canadian opinion leaders from the public and private sectors; a review of opinions and recommendations of influential Canadian policy institutes; a report on government policies and actions that affect AECL directly or indirectly; an analysis of new coverage by print and electronic media; a review of anti-nuclear organizations; and conclusions and recommendations

Qinshan plant display system: experience to date

International Nuclear Information System (INIS)

Bin, L.; Jiangdong, Y.; Weili, C.; Haidong, W.; Wangtian, L.; Lockwood, R.; Doucet, R.; Trask, D.; Judd, R.

2004-01-01

The two CANDU 6 units operated by the Third Qinshan Nuclear Power Corporation (TQNPC) include, as part of a control centre upgrade, a new plant display system (PDS). The PDS provides plant operators with new display and monitoring functionality designed to compliment the DCC capability. It includes new overview and trend displays (e.g., critical safety parameter monitor and user-defined trends), and enhanced annunciation based on AECL's Computerized Alarm Message List System (CAMLS) including an alarm interrogation capability. This paper presents a review of operating experience gained since the PDS was commissioned more than three years ago. It includes feedback provided by control room operators and trainers, PDS maintainers, and AECL development and support staff. It also includes an overview of improvements implemented since the PDS and suggestions for the future enhancements. (author)

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

Computer based plant display and digital control system of Wolsong NPP Tritium Removal Facility

International Nuclear Information System (INIS)

Jung, C.; Smith, B.; Tosello, G.; Grosbois, J. de; Ahn, J.

2007-01-01

The Wolsong Tritium Removal Facility (WTRF) is an AECL-designed, first-of-a-kind facility that removes tritium from the heavy water that is used in systems of the CANDUM reactors in operation at the Wolsong Nuclear Power Plant in South Korea. The Plant Display and Control System (PDCS) provides digital plant monitoring and control for the WTRF and offers the advantages of state-of-the-art digital control system technologies for operations and maintenance. The overall features of the PDCS will be described and some of the specific approaches taken on the project to save construction time and costs, to reduce in-service life-cycle costs and to improve quality will be presented. The PDCS consists of two separate computer sub-systems: the Digital Control System (DCS) and the Plant Display System (PDS). The PDS provides the computer-based Human Machine Interface (HMI) for operators, and permits efficient supervisory or device level monitoring and control. A System Maintenance Console (SMC) is included in the PDS for the purpose of software and hardware configuration and on-line maintenance. A Historical Data System (HDS) is also included in the PDS as a data-server that continuously captures and logs process data and events for long-term storage and on-demand selective retrieval. The PDCS of WTRF has been designed and implemented based on an off-the-self PDS/DCS product combination, the Delta-V System from Emerson. The design includes fully redundant Ethernet network communications, controllers, power supplies and redundancy on selected I/O modules. The DCS provides field bus communications to interface with 3rd party controllers supplied on specialized skids, and supports HART communication with field transmitters. The DCS control logic was configured using a modular and graphical approach. The control strategies are primarily device control modules implemented as autonomous control loops, and implemented using IEC 61131-3 Function Block Diagram (FBD) and Structured

Fusion Canada issue 11

Energy Technology Data Exchange (ETDEWEB)

NONE

1990-06-01

A short bulletin from the National Fusion Program. Included in this issue is a report on operation at Tokamak de Varennes, CRITIC irradiations at AECL, Tritium systems at TFTR, physics contribution at ITER. 4 figs.

Fuel cycles

International Nuclear Information System (INIS)

Hawley, N.J.

1983-05-01

AECL publications, from the open literature, on fuels and fuel cycles used in CANDU reactors are listed in this bibliography. The accompanying index is by subject. The bibliography will be brought up to date periodically

CANDU in Romania

International Nuclear Information System (INIS)

Keillor, M.

1990-01-01

The author, a former journalist, and now manager of media relations at AECL CANDU, visited Romania to get a first-hand account of conditions at the Cernavoda site. He refutes allegations of slave labour, or inhuman conditions

Update on Canada's nuclear fuel waste management program

International Nuclear Information System (INIS)

Allan, C.J.

1992-09-01

The Canadian Nuclear Fuel Waste Management Program (CNFWMP) was launched in 1978 as a joint initiative by the governments of Canada and Ontario. Under the program, AECL has been developing and assessing a generic concept to dispose of nuclear fuel waste in plutonic rock of the Canadian Shield. The disposal concept has been referred for review under the Environmental Assessment and Review Process. AECL will submit an Environmental Impact Statement (EIS) to an Environmental Assessment Panel, which was appointed in late 1989. Hearings will be held in areas that have a particular interest in the concept and its application. At the end of the review, the Panel will make recommendations as to the acceptability of the concept and the course of future action. The federal government will decide on the next steps to be taken. In the spring of 1990 public open houses were held to tell prospective participants how to enter the process. Sessions designed to assist the Panel in determining the scope of the EIS took place in the autumn of 1990. In June 1991 the Panel issued for comment a set of draft guidelines for the EIS. More than 30 groups and individuals submitted comments. The final guidelines were issued in March 1992, and AECL expects to submit its EIS to the Panel in 1993. If the concept review is completed by 1995 and if the concept is approved, disposal could begin some time after 2025. (L.L.) (12 refs.)

A compendium of the data used with the SYVAC3-CC3 system model

International Nuclear Information System (INIS)

Szekely, J.G.; Stephens, M.E.; Witzke, K.H.; Melnyk, T.W.; LeNeveu, D.M.; McConnell, D.B.; Goodwin, B.W.

1994-12-01

AECL is evaluating a concept for disposing of nuclear fuel waste from Canada's CANDU reactors deep in plutonic rock of the Canadian Shield. As part of this evaluation, AECL has developed models of the physicals, chemical, geological and biological processes that could occur in a sealed accessible environment over thousands of years. The mathematical models of the transport of radionuclides and toxic chemicals from nuclear fuel waste to the environment are incorporated into a computer model named the SYstems Variability Analysis Code, generation 3, and Canadian Concept model, generation 3 (SYVAC3-CC3). This report reproduces the data in the master database used by SYVAC3-CC3 for the postclosure assessment of deep laboratory and field studies conducted by AECL Research over the past fifteen years, including the investigations at an Underground Research Laboratory excavated to a depth of 450 meters in a large granitic batholith within the Whiteshell Research area near Lac du Bonnet, Manitoba; conceptual engineering studies; detailed analyses of specific features, events and processes; and published literature. The data represent characteristics of a hypothetical vault, certain geological characteristics of the Whiteshell Research area, and a general surface environment with a human population living a rural lifestyle on a portion of the Canadian Shield in central Canada. The data are stored in a master database, which is used with a suite of computer programs to create the input data files used by SYVAC3-CC3. (author). 19 refs., 11 tabs., 2 figs

A human reliability assessment screening method for the NRU upgrade project

International Nuclear Information System (INIS)

Bremner, F.M.; Alsop, C.J.

1997-01-01

The National Research Universal (NRU) reactor is a 130MW, low pressure, heavy water cooled and moderated research reactor. The reactor is used for research, both in support of Canada's CANDU development program, and for a wide variety of other research applications. In addition, NRU plays an important part in the production of medical isotopes, e.g., generating 80% of worldwide supplies of Molybdenum-99. NRU is owned and operated by Atomic Energy of Canada Ltd. (AECL), and is currently undergoing upgrading as part of AECL's continuing commitment to operate their facilities in a safe manner. As part of these upgrades both deterministic and probabilistic safety assessments are being carried out. It was recognized that the assignment of Human Error Probabilities (HEPs) is an important part of the Probabilistic Safety Assessment (PSA) studies, particularly for a facility whose design predates modern ergonomic practices, and which will undergo a series of backfitted modifications whilst continuing to operate. A simple Human Reliability Assessment (HRA) screening method, looking at both pre- and post-accident errors, was used in the initial safety studies. However, following review of this method within AECL and externally by the regulator, it was judged that benefits could be gained for future error reduction by including additional features, as later described in this document. The HRA development project consisted of several stages; needs analysis, literature review, development of method (including testing and evaluation), and implementation. This paper discusses each of these stages in further detail. (author)

International standard problem (ISP) no. 41 follow up exercise: Containment iodine computer code exercise: parametric studies

Energy Technology Data Exchange (ETDEWEB)

Ball, J.; Glowa, G.; Wren, J. [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada); Ewig, F. [GRS Koln (Germany); Dickenson, S. [AEAT, (United Kingdom); Billarand, Y.; Cantrel, L. [IPSN (France); Rydl, A. [NRIR (Czech Republic); Royen, J. [OECD/NEA (France)

2001-11-01

This report describes the results of the second phase of International Standard Problem (ISP) 41, an iodine behaviour code comparison exercise. The first phase of the study, which was based on a simple Radioiodine Test Facility (RTF) experiment, demonstrated that all of the iodine behaviour codes had the capability to reproduce iodine behaviour for a narrow range of conditions (single temperature, no organic impurities, controlled pH steps). The current phase, a parametric study, was designed to evaluate the sensitivity of iodine behaviour codes to boundary conditions such as pH, dose rate, temperature and initial I{sup -} concentration. The codes used in this exercise were IODE(IPSN), IODE(NRIR), IMPAIR(GRS), INSPECT(AEAT), IMOD(AECL) and LIRIC(AECL). The parametric study described in this report identified several areas of discrepancy between the various codes. In general, the codes agree regarding qualitative trends, but their predictions regarding the actual amount of volatile iodine varied considerably. The largest source of the discrepancies between code predictions appears to be their different approaches to modelling the formation and destruction of organic iodides. A recommendation arising from this exercise is that an additional code comparison exercise be performed on organic iodide formation, against data obtained front intermediate-scale studies (two RTF (AECL, Canada) and two CAIMAN facility, (IPSN, France) experiments have been chosen). This comparison will allow each of the code users to realistically evaluate and improve the organic iodide behaviour sub-models within their codes. (author)

International standard problem (ISP) no. 41 follow up exercise: Containment iodine computer code exercise: parametric studies

International Nuclear Information System (INIS)

Ball, J.; Glowa, G.; Wren, J.; Ewig, F.; Dickenson, S.; Billarand, Y.; Cantrel, L.; Rydl, A.; Royen, J.

2001-11-01

This report describes the results of the second phase of International Standard Problem (ISP) 41, an iodine behaviour code comparison exercise. The first phase of the study, which was based on a simple Radioiodine Test Facility (RTF) experiment, demonstrated that all of the iodine behaviour codes had the capability to reproduce iodine behaviour for a narrow range of conditions (single temperature, no organic impurities, controlled pH steps). The current phase, a parametric study, was designed to evaluate the sensitivity of iodine behaviour codes to boundary conditions such as pH, dose rate, temperature and initial I - concentration. The codes used in this exercise were IODE(IPSN), IODE(NRIR), IMPAIR(GRS), INSPECT(AEAT), IMOD(AECL) and LIRIC(AECL). The parametric study described in this report identified several areas of discrepancy between the various codes. In general, the codes agree regarding qualitative trends, but their predictions regarding the actual amount of volatile iodine varied considerably. The largest source of the discrepancies between code predictions appears to be their different approaches to modelling the formation and destruction of organic iodides. A recommendation arising from this exercise is that an additional code comparison exercise be performed on organic iodide formation, against data obtained front intermediate-scale studies (two RTF (AECL, Canada) and two CAIMAN facility, (IPSN, France) experiments have been chosen). This comparison will allow each of the code users to realistically evaluate and improve the organic iodide behaviour sub-models within their codes. (author)

Safety culture improvements in a nuclear laboratory setting

International Nuclear Information System (INIS)

Smith, K.L.; McKenna, J.

2014-01-01

In 2008, AECL performed a comprehensive safety culture assessment using recognized, industry-proven methodologies. Main observations were grouped into several key areas including standards, procedures, error-free work, and leadership fundamentals. Shortly thereafter, in 2009 May, the National Research Universal (NRU) reactor was shut down following discovery of a small leak of heavy water. Extensive repairs were required to return the reactor to service and a root cause investigation was conducted to determine the organizational and programmatic causes that led to the event. Taken together, these presented management with insights into common areas of weaknesses in performance and behaviours. A Corrective Action Plan (CAP) to address both the findings of the root cause analysis and safety culture assessment was captured in a comprehensive improvement plan issued in 2010 March, entitled the Voyageur Program Phase II (Voyageur II). The CAP addresses six key areas: Improve equipment reliability; Drive desired behaviours; Improve problem identification and resolution; Improve use of industry Operating Experience (OPEX) and reduce isolationism; Improve standards of operation; and, Improve management oversight. AECL's safety culture has been monitored regularly using quarterly surveys. A detailed safety culture assessment was executed in 2012 September. Compared with previous results, improvements for AECL were noted in the following areas: Use of Operating Experience, specifically in work planning, pre job briefs and training; Procedure quality; Availability of safety equipment; Control of temporary changes; and, Improved operational standards. (author)

Progress towards a new Canadian irradiation-research facility

International Nuclear Information System (INIS)

Lee, A.G.; Lidstone, R.F.

1993-01-01

As reported at the second meeting of the International Group on Research Reactors, Atomic Energy of Canada Limited (AECL) is evaluating its options for future irradiation facilities. During the past year significant progress has been made towards achieving consensus on the irradiation requirements for AECL's major research programs and interpreting those requirements in terms of desirable characteristics for experimental facilities in a research reactor. The next stage of the study involves identifying near-term and long-term options for irradiation-research facilities to meet the requirements. The near-term options include assessing the availability of the NRU reactor and the capabilities of existing research reactors. The long-term options include developing a new irradiation-research facility by adapting the technology base for the MAPLE-X10 reactor design. Because materials testing in support of CANDU power reactors dominates AECL's irradiation requirements, the new reactor concept is called the MAPLE Materials Testing Reactor (MAPLE-MTR). Parametric physics and engineering studies are in progress on alternative MAPLE-MTR configurations to assess the capabilities for the following types of test facilities: - fast-neutron sites, that accommodate materials-irradiation assemblies, - small-diameter vertical fuel test loops that accommodate multielement assemblies, - large-diameter vertical fuel test loops, each able to hold one or more CANDU fuel bundles, - horizontal test loops, each able to hold full-size CANDU fuel bundles or small-diameter multi-element assemblies, and - horizontal beam tubes

Annual report, 1990-1991

International Nuclear Information System (INIS)

1991-01-01

At the beginning of the 1990/91 fiscal year the government of Canada announced that it would maintain the CANDU nuclear option, increase R and D funding for AECL Research, and authorize the start of negotiations to build a prototype CANDU 3 reactor. Later in the year AECL signed contracts with the Korea Electric Power Corporation to supply a second CANDU reactor for the Wolsung site. Consolidated net income was $7.8 million, after a $10.2 million loss in 1990. Revenue from nuclear power operations increased 11 percent to $187 million, with a 23 percent increase in the contribution from nuclear supply and services. Research and development expenditures rose to $293 million in 1991 from $259 million in 1990. The increase was mainly in cost-shared work on waste management, safety, health and environmental programs. Cost recovery revenue, principally from Ontario Hydro, increased to $87 million, reducing the federal government's share to 53 percent compared to 87 percent in 1985. Federal funding of R and D has been maintained at the 1990 level. The net expense of R and D operations was reduced to $11.0 million compared to $22.6 million in the previous year. Cash flow from all sources amounted to $47.9 million, leaving AECL with adequate working capital for the next year. In the future higher capital investment than previously anticipated will be required for waste management facilities associated with commercial isotope production. All figures are given in Canadian dollars

Progress report - physical sciences - physics division 1990 July 01 - December 31

International Nuclear Information System (INIS)

1991-05-01

A completely new administrative structure of AECL Research was implemented on 1990 July 1. All of the basic physics programs, together with accelerator physics, radiation applications and most of the chemistry programs of AECL, have been placed in a new organizational unit called Physical Sciences. This unit also includes the management of the National Fusion Program. The research programs of Physical Sciences are grouped into three divisions: Chemistry, Physics and TASCC. Progress in each division will henceforth be reported on a twice-yearly basis. This report is the first of the new series to be issued by the Physics Division. Of special note within the period covered by this report was the successful acceleration of over 75 mA of protons to 600 keV in RFQ1 making it the highest current RFQ in the world. Our electron accelerator expertise has been recognized by the award of one of the R and D 100 awards for the IMPELA (10 MeV 50 kW) machine. Considerable activity was associated with bringing the new dual beam neutron spectrometer DUALSPEC to completion. This instrument has been jointly funded by AECL and NSERC through McMaster University and will be a central component of the national neutron scattering facility at NRU in the 1990's. A major effort was made with the writing of a Project Definition Document for installation of a cold neutron source at the most opportune time

Safety culture improvements in a nuclear laboratory setting

Energy Technology Data Exchange (ETDEWEB)

Smith, K.L.; McKenna, J. [Atomic Energy of Canada Limited, Chalk River, ON (Canada)

2014-07-01

In 2008, AECL performed a comprehensive safety culture assessment using recognized, industry-proven methodologies. Main observations were grouped into several key areas including standards, procedures, error-free work, and leadership fundamentals. Shortly thereafter, in 2009 May, the National Research Universal (NRU) reactor was shut down following discovery of a small leak of heavy water. Extensive repairs were required to return the reactor to service and a root cause investigation was conducted to determine the organizational and programmatic causes that led to the event. Taken together, these presented management with insights into common areas of weaknesses in performance and behaviours. A Corrective Action Plan (CAP) to address both the findings of the root cause analysis and safety culture assessment was captured in a comprehensive improvement plan issued in 2010 March, entitled the Voyageur Program Phase II (Voyageur II). The CAP addresses six key areas: Improve equipment reliability; Drive desired behaviours; Improve problem identification and resolution; Improve use of industry Operating Experience (OPEX) and reduce isolationism; Improve standards of operation; and, Improve management oversight. AECL's safety culture has been monitored regularly using quarterly surveys. A detailed safety culture assessment was executed in 2012 September. Compared with previous results, improvements for AECL were noted in the following areas: Use of Operating Experience, specifically in work planning, pre job briefs and training; Procedure quality; Availability of safety equipment; Control of temporary changes; and, Improved operational standards. (author)

ACR-1000TM Project - Licensing Opportunities and Challenges

International Nuclear Information System (INIS)

Popov, N.; Doerffer, S.; Ion, R.; Hopwood, J.

2011-01-01

Atomic Energy of Canada Limited (AECL) has developed the Advanced CANDU Reactor TM 1 1000 (ACR-1000 TM ) as an evolutionary advancement of the current CANDU 6 reactor. The ACR-1000 design has evolved from AECL's in-depth knowledge of CANDU TM systems, components, and materials, as well as the experience and feedback received from owners and operators of CANDU plants. The ACR design retains the proven strengths and features of CANDU reactors, while incorporating innovations and state-of-the-art technology. It also features major improvements in economics, inherent safety characteristics, and performance, while retaining the proven benefits of the CANDU family of nuclear power plants. To ensure that the ACR design is compliant with Canadian and international requirements, regulatory pre-project reviews of the ACR-1000 (and ACR-700 TM 1 with lower output) were conducted early in the design work. The regulatory feedback from these pre-project regulatory reviews helped AECL to better understand regulatory expectations in Canada, US and the UK, and to make further advancements and improvements in the ACR design to meet the Canadian and international regulatory requirements. This paper provides an overview of the key design features of the ACR-1000 reactor design, and summary of the pre-project reviews by those above-mentioned regulatory bodies, demonstrating opportunities and challenges in licensing process of and pointing to the importance of efficient vendor-regulator interaction. (author)

Using systematic aging assessments to improve effectiveness of plant maintenance programs

International Nuclear Information System (INIS)

Watson, P.; Yang, J.X.; Dam, R.F.; Nickerson, J.H.

2003-01-01

Nuclear plant equipment aging assessment studies provided by AECL include life assessments, condition assessments or systematic assessments of maintenance. AECL has developed several tools to apply the results of aging assessment studies to improve the effectiveness of actual plant maintenance programs. The Systematic Assessment of Maintenance and the SYSTMS tool generate maintenance tasks for a system. The System Maintenance Datastore tool assesses the maintenance resources on a system basis, and can thus quantify the savings realized by optimizing the maintenance program. Long term trends in condition-based maintenance due to component aging can be predicted, and resource savings due to optimum timing of component replacement or general plant refurbishment can be quantified. The System based Adaptive Maintenance Process ensures the maintenance program is continually updated to reflect the latest plant equipment condition and maintenance strategy information. (author)

Nuclear platform research and development - 2008-09 highlights

International Nuclear Information System (INIS)

Sadhankar, R.R.

2009-08-01

The Nuclear Platform R and D Program has lead responsibility for the maintenance and further development of the CANDU intellectual property covering the safety, licensing and design basis for nuclear facilities. The Nuclear Platform R and D Program is part of the Research and Technology Operation (RTO) unit of AECL and is managed through the Research and Development division, which has responsibility for maintaining and enhancing the knowledge and technology base. The RTO is also responsible for managing AECL's nuclear facilities and infrastructure (including laboratories and R and D facilities), the nuclear waste management program and other legacy liabilities (e.g., decommissioning) to demonstrate and grow shareholder value. The Nuclear Platform also provides the technology base from which new products and services can be developed to meet customer needs (including ACR and commercial products and services). (author)

Application of heat pipes in nuclear reactors for passive heat removal

Energy Technology Data Exchange (ETDEWEB)

Haque, Z.; Yetisir, M., E-mail: haquez@aecl.ca [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada)

2013-07-01

This paper introduces a number of potential heat pipe applications in passive (i.e., not requiring external power) nuclear reactor heat removal. Heat pipes are particularly suitable for small reactors as the demand for heat removal is significantly less than commercial nuclear power plants, and passive and reliable heat removal is required. The use of heat pipes has been proposed in many small reactor designs for passive heat removal from the reactor core. This paper presents the application of heat pipes in AECL's Nuclear Battery design, a small reactor concept developed by AECL. Other potential applications of heat pipes include transferring excess heat from containment to the atmosphere by integrating low-temperature heat pipes into the containment building (to ensure long-term cooling following a station blackout), and passively cooling spent fuel bays. (author)

Learning from experience: feedback to CANDU design

International Nuclear Information System (INIS)

Allen, P.J.; Hopwood, J.M.; Rousseau, G.P.

1998-01-01

AECL's main product line is based on two single unit CANDU nuclear power plant designs; CANDU 6 and CANDU 9, each of which is based on successfully operating CANDU plants. AECL's CANDU development program is based upon evolutionary improvement. The evolutionary design approach ensures the maximum degree of operational provenness. It also allows successful features of today's plants to be retained while incorporating improvements as they develop to the appropriate level of design maturity. A key component of this evolutionary development is a formal process of gathering and responding to feedback from: NPP operation, construction and commissioning; regulatory input; equipment supplier input; R and D results; market input. The progresses for gathering and implementing the experience feedback and a number of recent examples of design improvements from this feedback process are described in the paper. (author)

Development of nuclear fuel. Development of CANDU advanced fuel bundle

International Nuclear Information System (INIS)

Suk, Ho Chun; Hwang, Woan; Jeong, Young Hwan; Jung, Sung Hoon

1991-07-01

In order to develop CANDU advanced fuel, the agreement of the joint research between KAERI and AECL was made on February 19, 1991. AECL conceptual design of CANFLEX bundle for Bruce reactors was analyzed and then the reference design and design drawing of the advanced fuel bundle with natural uranium fuel for CANDU-6 reactor were completed. The CANFLEX fuel cladding was preliminarily investigated. The fabricability of the advanced fuel bundle was investigated. The design and purchase of the machinery tools for the bundle fabrication for hydraulic scoping tests were performed. As a result of CANFLEX tube examination, the tubes were found to be meet the criteria proposed in the technical specification. The dummy bundles for hydraulic scoping tests have been fabricated by using the process and tools, where the process parameters and tools have been newly established. (Author)

Management of experimental and exotic fuels by Atomic Energy of Canada Ltd

International Nuclear Information System (INIS)

Doyle, J.R.

1999-01-01

Atomic Energy of Canada (AECL) has been engaged in nuclear research and development at its Chalk River Laboratories since the 1940's. During this time, a wide variety of irradiated research reactor and experimental fuels have been stored in a variety of storage facilities. Some of these fuels are of unique composition and configuration, and some fuels have been degraded as a result of research activities. In preparing decommissioning plans for these storage facilities, AECL has developed a strategy that identifies how each type of fuel will be dispositioned in the future. The goal of this strategy is to ensure that the fuels are maintained in a safe stable state until a repository for these fuels becomes available. This paper describes the current storage facilities, options considered for long-term fuel management, and the strategy selected to manage these fuels. (author)

Continuous improvement of pump seals

International Nuclear Information System (INIS)

Wong, W.; Eyvindson, A.; Rhodes, D.B.

2003-01-01

Pump seal reliability continues to be an area needing improvement and ongoing vigilance. Methods have been developed for identifying and assessing factors relating to seal performance, selecting the most relevant ones for a specific station, and then focusing on the most significant aspects and how to improve. Discussion invariably addresses maintenance practices, seal design, monitoring capabilities, operating conditions, transients, and pump and motor design. Success in reliability improvement requires ongoing dialogue among the station operators, pump manufacturers and seal designers. AECL CAN-seals lead the nuclear industry in reliability and seal life. They effectively save operators millions of dollars in outage time and person-rem. This paper describes some of the significant developments in AECL's ongoing program in seal R and D, as well as recent new installations following the most demanding seal qualification programs to date. (author)

Atomic Energy of Canada Limited annual report 1987-88

International Nuclear Information System (INIS)

1988-01-01

The annual report of Atomic Energy of Canada Limited for the fiscal year ended March 31, 1988 covers: Research Company; CANDU Operations; Radiochemical Company; Medical Products Division; The Future; Financial Sections; Board of Directors and Officers; and AECL locations

Nuclear fuel activities in Canada

Energy Technology Data Exchange (ETDEWEB)

Cox, D S [Fuel Development Branch, Chalk River Labs., AECL (Canada)

1997-12-01

Nuclear fuel activities in Canada are considered in the presentation on the following directions: Canadian utility fuel performance; CANDU owner`s group fuel programs; AECL advanced fuel program (high burnup fuel behaviour and development); Pu dispositioning (MOX) activities. 1 tab.

Team CANDU : ready for the marketplace

International Nuclear Information System (INIS)

Howieson, J.Q.

2007-01-01

This paper outlines the partnership between AECL and a number of leading global nuclear suppliers to market the Candu power reactor. The mission of the CANDU team is to develop market opportunities for CANDU technology and deliver successful CANDU projects

Modifications to the FISS program

International Nuclear Information System (INIS)

Donnelly, J.V.

1985-11-01

FISS is a computer code for use in investigating alternative fuel cycle strategies, performing system simulations accounting for the dynamic effects in growing systems. The changes that have been made to the original FISS program reported in AECL-5814 are described

ACR-1000: Operator - based development

International Nuclear Information System (INIS)

Shalaby, B.; Alizadeh, A.

2007-01-01

Atomic Energy of Canada Limited (AECL) has adapted the successful features of CANDU * reactors to establish Generation III + Advanced CANDU Reactor T M (ACR T M) technology. The ACR-1000 T M nuclear power plant is an evolutionary product, starting with the strong base of CANDU reactor technology, coupled with thoroughly-demonstrated innovative features to enhance economics, safety, operability and maintainability. The ACR-1000 benefits from AECL's continuous-improvement approach to design, that enabled the traditional CANDU 6 product to compile an exceptional track record of on-time, on budget product delivery, and also reliable, high capacity-factor operation. The ACR-1000 engineering program has completed the basic plant design and has entered detailed pre-project engineering and formal safety analysis to prepare the preliminary (non-project-specific) safety case. The engineering program is strongly operator-based, and encompasses much more than traditional pre-project design elements. A team of utility-experienced operations and maintenance experts is embedded in the engineering team, to ensure that all design decisions, at the system and the component level, are taken with the owner-operator interest in mind. The design program emphasizes formal review of operating feedback, along with extensive operator participation in program management and execution. Design attention is paid to layout and access of equipment, to component and material selection, and to ensuring maximum ability for on-line maintenance. This enables the ACR-1000 to offer a three-year interval between scheduled maintenance outages, with a standard 21-day outage duration. SMART CANDU T M technology allows on-line monitoring and diagnostics to further enhance plant operation. Modules of the Advanced CANDU SMART technologies are already being back-fitted to current CANDU plants. As well as reviewing the ACR-1000 design features and their supporting background, the paper describes the status of

Challenges for remote monitoring and control of small reactors

Energy Technology Data Exchange (ETDEWEB)

Trask, D., E-mail: traskd@aecl.ca [Atomic Energy of Canada Limited, Fredericton, New Brunswick (Canada)

2013-07-01

This paper considers a model for small, unmanned, remotely located reactors and discusses the ensuing cyber security and operational challenges for monitoring and control and how these challenges might be overcome through some of AECL's research initiatives and experience. (author)

Radiation applications research and facilities in AECL research company

Science.gov (United States)

Iverson, S. L.

In the 60's and 70's Atomic Energy of Canada had a very active R&D program to discover and develop applications of ionizing radiation. Out of this grew the technology underlying the company's current product line of industrial irradiators. With the commercial success of that product line the company turned its R&D attention to other activities. Presently, widespread interest in the use of radiation for food processing and the possibility of developing reliable and competitive machine sources of radiation hold out the promise of a major increase in industrial use of radiation. While many of the applications being considered are straightforward applications of existing knowledge, others depend on more subtle effects including combined effects of two or more agents. Further research is required in these areas. In March 1985 a new branch, Radiation Applications Research, began operations with the objective of working closely with industry to develop and assist the introduction of new uses of ionizing radiation. The Branch is equipped with appropriate analytical equipment including HPLC (high performance liquid chromatograph) and GC/MS (gas chromatograph/mass spectrometer) as well as a Gammacell 220 and an I-10/1, one kilowatt 10 MeV electron accelerator. The accelerator is located in a specially designed facility equipped for experimental irradiation of test quantities of packaged products as well as solids, liquids and gases in various configurations. A conveyor system moves the packaged products from the receiving area, through a maze, past the electron beam at a controlled rate and finally to the shipping area. Other necessary capabilities, such as gamma and electron dosimetry and a microbiology laboratory, have also been developed. Initial projects in areas ranging from food through environmental and industrial applications have been assessed and the most promising have been selected for further work. As an example, the use of charcoal adsorbent beds to concentrate the components of gas or liquid waste streams requiring treatment is showing promise as a method of significantly reducing the cost of radiation treatment for some effluents. A number of other projects are described.

Processing of LLRW arising from AECL nuclear research centres

International Nuclear Information System (INIS)

Buckley, L.P.; Le, V.T.; Beamer, N.V.; Brown, W.P.; Helbrecht, R.A.

1988-11-01

Operation of nuclear research reactors and laboratories results in the generation of a wide variety of solid and liquid radioactive wastes. This paper describes practical experience with processing of low-level radioactive wastes at two major nuclear research centres in Canada

AECL's progress in developing the DUPIC fuel fabrication process

International Nuclear Information System (INIS)

Sullivan, J.D.; Cox, D.S.

1995-01-01

Spent Pressurized Water Reactor (PWR) fuel can be used directly in CANDU reactors without the need for wet chemical reprocessing or reenrichment. Considerable experimental progress has been made in verifying the practicality of this fuel cycle, including hot-cell experiments using spent PWR fuels and out-cell trials using surrogate fuels. This paper describes the current status of these experiments. (author)

Radiation applications research and facilities in AECL Research Company

International Nuclear Information System (INIS)

Iverson, S.L.

1988-01-01

In the 60's and 70's Atomic Energy of Canada had a very active R and D program to discover and develop applications of ionizing radiation. Widespread interest in the use of radiation for food processing and the possibility of developing reliable and competitive machine sources of radiation hold out the promise of a major increase in industrial use of radiation. In March 1985 a new branch, Radiation Applications Research, began operations with the objective of working closely with industry to develop and assist the introduction of new uses of ionizing radiation. The Branch is equipped with appropriate analytical equipment including HPLC (high performance liquid chromatograph) and GC/MS (gas chromatograph/mass spectrometer) as well as a Gammacell 220 and an I-10/1, one kilowatt 10 MeV electron accelerator. The accelerator is located in a specially designed facility equipped for experimental irradiation of the test quantities of packaged products as well as solids, liquids and gases in various configurations. A conveyor system moves the packaged products from the receiving area, through a maze, past the electron beam at a controlled rate and finally to the shipping area. Other necessary capabilities, such as gamma and electron dosimetry and a microbiology laboratory, have also been developed. Initial projects in areas ranging from food through environmental and industrial applications have been assessed and the most promising have been selected for further work. As an example, the use of charcoal absorbent beds to concentrate the components of gas or liquid waste streams requiring treatment is showing promise as a method of significantly reducing the cost of radiation treatment for some effluents. A number of other projects are described. (author)

Safety re-assessment of AECL test and research reactors

International Nuclear Information System (INIS)

Winfield, D.J.

1990-01-01

Atomic Energy of Canada Limited currently has four operating engineering test/research reactors of various sizes and ages; a new isotope-production reactor Maple-X10, under construction at Chalk River Nuclear Laboratories (CRNL), and a heating demonstration reactor, SDR, undergoing high-power commissioning at Whiteshell Nuclear Research Establishment (WNRE). The company is also performing design studies of small reactors for hot water and electricity production. The older reactors are ZED-2, PTR, NRX, and NRU; these range in age from 42 years (NRX) to 29 years (ZED-2). Since 1984, limited-scope safety re-assessments have been underway on three of these reactors (ZED-2, NRX AND NRU). ZED-2 and PTR are operated by the Reactor Physics Branch; all other reactors are operated by the respective site Reactor Operations Branches. For the older reactors the original safety reports produced were entirely deterministic in nature and based on the design-basis accident concept. The limited scope safety re-assessments for these older reactors, carried out over the past 5 years, have comprised both quantitative probabilistic safety-assessment techniques, such as event tree and fault analysis, and/or qualitative techniques, such as failure mode and effect analysis. The technique used for an individual assessment was dependent upon the specific scope required. This paper discusses the types of analyses carried out, specific insights/recommendations resulting from the analysis, and the plan for future analysis. In addition, during the last four years safety assessments have been carried out on the new isotope-, heat-, and electricity-producing reactors, as part of the safety design review, commissioning and licensing activities

A forward looking company

International Nuclear Information System (INIS)

Christian, David A.

2004-01-01

The article is an excerpt of an interview with David A. Christian, Senior Vice President-Nuclear and Chief Nuclear Officer, Dominion Generation conducted at NEI's Nuclear Energy Assembly in New Orleans, Louisiana on 13 May 2004. It highlights the company's energy diversity, and in particular, activities related to early-site permits and possible future plans for nuclear power plant development in the U.S. The interview touches on questions related to the Consortium (composed of Dominion, AECL Technologies, the U.S. subsidiary of AECL, Hatachi America and Bechtel Power Corp.) and the DOE financial support involved (approximately 50%) along with comments related to job impacts, energy security and climate change impacts, human resource issues (particularly about getting high school students interested in jobs related to the nuclear industry) and public policy. The interview ends with a discussion of investment interest and the state of standardization in the industry

Technology transfer: The CANDU approach

International Nuclear Information System (INIS)

Hart, R.S.

1998-01-01

The many and diverse technologies necessary for the design, construction licensing and operation of a nuclear power plant can be efficiently assimilated by a recipient country through an effective technology transfer program supported by the firm long term commitment of both the recipient country organizations and the supplier. AECL's experience with nuclear related technology transfer spans four decades and includes the construction and operation of CANDU plants in five countries and four continents. A sixth country will be added to this list with the start of construction of two CANDU 6 plants in China in early 1997. This background provides the basis for addressing the key factors in the successful transfer of nuclear technology, providing insights into the lessons learned and introducing a framework for success. This paper provides an overview of AECL experience relative to the important factors influencing technology transfer, and reviews specific country experiences. (author)

Combined electrolysis and catalytic exchange (CECE) technology - an economical alternative for heavy water upgraders using water distillation

International Nuclear Information System (INIS)

Ryland, D.K.; Sadhankar, R.R.

2003-01-01

Heavy water upgrading is a unique and crucial part of a CANDU power station. Water distillation (DW) systems are used for heavy water upgrading in all CANDU stations. The DW upgrader is designed to take advantage of the difference in relative volatility (a measure of separation of isotopes) between H 2 O and D 2 O. However, the low relative volatility of the H 2 O/D 2 O system requires large number of stages (long columns) and large reflux ratios (large reboiler loads) - thus resulting in significant capital and operating costs. Atomic Energy of Canada Limited (AECL) developed the Combined Electrolysis and Catalytic Exchange (CECE) technology as an economical alternative to the DW system. CECE-based upgraders have been demonstrated in pilot scale facilities at AECL Chalk River Laboratories and in Hamilton, Ontario. This design is based on catalytic hydrogen isotope exchange between water and hydrogen gas. (author)

Medical isotope shortage 2009-2010 and future options NRU, SLOWPOKE and MAPLE

Energy Technology Data Exchange (ETDEWEB)

Hilborn, J. [Deep River, Ontario (Canada)

2013-07-01

The 15 month shutdown of NRU and the unexpected termination of the AECL/Nordion MAPLE project caused a world-wide shortage of medical isotopes. After the recent repair of NRU, AECL is confident that it could continue operating safely and reliably as a multi-purpose reactor until 2021 or longer. There is convincing evidence that the restoration of the MAPLE reactors is technically feasible, but it is highly improbable that a 10 MW MAPLE production reactor can ever be cost-effective. However, conversion of the present 10 MW reactors to 3 MW, without major changes to the structural hardware, warrants serious consideration. Finally, even the 20 kW SLOWPOKE reactor could produce useful quantities of Mo-99. If the present fuel rods were replaced with a small tank containing a solution of low-enriched uranyl sulphate in water, three of these liquid core reactors could supply all of Canada. (author)

Medical isotope shortage 2009-2010 and future options NRU, SLOWPOKE and MAPLE

International Nuclear Information System (INIS)

Hilborn, J.

2013-01-01

The 15 month shutdown of NRU and the unexpected termination of the AECL/Nordion MAPLE project caused a world-wide shortage of medical isotopes. After the recent repair of NRU, AECL is confident that it could continue operating safely and reliably as a multi-purpose reactor until 2021 or longer. There is convincing evidence that the restoration of the MAPLE reactors is technically feasible, but it is highly improbable that a 10 MW MAPLE production reactor can ever be cost-effective. However, conversion of the present 10 MW reactors to 3 MW, without major changes to the structural hardware, warrants serious consideration. Finally, even the 20 kW SLOWPOKE reactor could produce useful quantities of Mo-99. If the present fuel rods were replaced with a small tank containing a solution of low-enriched uranyl sulphate in water, three of these liquid core reactors could supply all of Canada. (author)

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

Effluent and environmental monitoring of Chalk River Laboratories

Energy Technology Data Exchange (ETDEWEB)

Pilgrim, T.; De Waele, C.; Gallagher, C. [Atomic Energy of Canada Limited, Chalk River, ON (Canada)

2014-07-01

Atomic Energy of Canada Limited's (AECL's) Environmental Protection Program has been gathering environmental monitoring data at its Chalk River Laboratories (CRL) for over 60 years. The comprehensive effluent and environmental monitoring program at CRL consists of more than 600 sampling locations, including the Ottawa River, with approximately 60,000 analyses performed on air and liquid effluent parameters each year. Monitoring for a variety of radiological and non-radiological parameters is regularly conducted on various media, including ambient air, foodstuff (e.g. milk, fish, garden produce, large game, and farm animals), groundwater, Ottawa River water and other surface water on and off-site. The purpose of the monitoring program is to verify that past and current radiological and non-radiological emissions derived from AECL operations and activities, such as process water effluent into the Ottawa River, are below regulatory limits and demonstrate that CRL operations do not negatively affect the quality of water on or leaving the site. In fact, ongoing program reports demonstrate that radiological emissions are well below regulatory limits and have been declining for the past five years, and that non-radiological contaminants do not negatively affect the quality of water on and off the site. Two updated Canadian Standards Association (CSA) standards for Effluent and Environmental monitoring have come into effect and have resulted in some changes to the AECL Program. This presentation will discuss effluent and surface water monitoring results, the observed trends, the changes triggered by the CSA standards, and a path forward for the future. (author)

CFD analysis of flow and heat transfer in Canadian supercritical water reactor bundle

International Nuclear Information System (INIS)

Podila, K.; Rao, Y.F.

2015-01-01

Highlights: • Flow and heat transfer in SCWR fuel bundle design by AECL is studied using CFD. • Bare-rod bundle geometry is tested at 23.5, 25 and 28 MPa using STAR-CCM+ code. • SST k–ω low-Re model was used to study occurrence of heat transfer deterioration. - Abstract: Within the Gen-IV International Forum, AECL is leading the effort in developing a conceptual design for the Canadian SCWR. AECL proposed a new fuel bundle design with two rings of fuel elements placed between central flow tube and the pressure tube. In line with the scope of the conceptual design, the objective of the present CFD work is to aid in developing a bundle heat transfer correlation for the Canadian SCWR fuel bundle design. This paper presents results from an ongoing effort in determining the conditions favorable for occurrence of HTD in the supercritical bundle flows. In the current investigation, bare-rod bundle geometry was tested for the proposed fuel bundle design at 23.5, 25 and 28 MPa using STAR-CCM+ CFD code. Taking advantage of the design symmetry of the fuel bundle, only 1/32 of the computational domain was simulated. The low-Reynolds number modification of SST k–ω turbulence model along with y + < 1 was used in the simulations. For lower mass flow simulations, the increase of inlet temperature and operational pressure was found effective in reducing the occurrence of HTD. For higher mass flow simulations, normal heat transfer behaviour was observed except for the lower pressure range (23.5 MPa)

Qinshan CANDU commissioning - a successful partnership

International Nuclear Information System (INIS)

Alikhan, S.; Thomson, J.; Jun, G.; Guoyuan, J.

2004-01-01

The Qinshan CANDU Nuclear Power Plant consists of 2 x 728 MWe CANDU 6 units, built in Zhejiang Province, China, by the Third Qinshan Nuclear Power Company (TQNPC) as the owner and Atomic Energy of Canada Limited (AECL) as the main contractor. The Contract between China National Nuclear Corporation (CNNC) and AECL was signed in November 1996 and became effective on February 12, 1997 with scheduled completion dates of February 12, 2003 for Unit 1 and November 12, 2003 for Unit 2. Unit 1 was declared in-service on December 31, 2002, 43 days ahead of schedule and Unit 2 was declared in service on July 20, 2003, 115 days ahead of schedule. The successful partnership between AECL, Bechtel, Hitachi and TQNPC working as a team is the key to this success. Total commissioning period from first energization of the system service transformer to in-service for both units was 20.7 months, which is significantly better than the experience at other comparable CANDU 6 units. It has clearly demonstrated the benefits of building two units together, about 6 months apart, to achieve optimum utilization of resources already mobilized for the first unit; the second unit is commissioned with less than 40% of the effort required for the first unit. Since in-service to the end of March 2004, Unit 1 has operated at a gross capacity factor of 93% and Unit 2 at 82.5%, including loss of production for one month in August 2003 to repair the failure of turbine LP blades tie-wire. (author)

TASCC newsletter volume 6 no. 9

International Nuclear Information System (INIS)

Thomson, L.

1992-09-01

A newsletter produced by Chalk River's Tandem Accelerator Superconducting Cyclotron Facility. Included in this September issue is a report of TASCC productivity, awards from AECL, and a symposium hosted by TASCC, a facility report and operating record and a listing of September's experiments. 1 fig

A world-class act

International Nuclear Information System (INIS)

Richards, Sherrilynne; Thomas, Ron.

1992-01-01

In the autumn of 1991, a school on food irradiation held at AECL's Whiteshell Laboratories was attended by 14 food scientists from 12 countries. More than 30 countries have now approved food irradiation. In Canada, Nordion is a world leader with its cobalt-60 irradiators

A short history of the CANDU nuclear power system

Energy Technology Data Exchange (ETDEWEB)

Brooks, G L

1993-04-01

This paper provides a short historical summary of the evolution of the CANDU nuclear power system with emphasis on the roles played by Ontario Hydro and private sector companies in Ontario in collaboration with Atomic Energy of Canada Limited (AECL). (author). 1 fig., 61 refs.

CANDU 9 - reducing capital costs through advanced construction

International Nuclear Information System (INIS)

Hedges, K.; Yu, S.; Hopwood, J.

1996-01-01

Reducing costs is a clear priority in nuclear markets where capital reaches billions and financing is hard-won. To address that priority, AECL introduced the use of advanced construction techniques. This has been one of the key thrusts behind its development of CANDU 9. (author)

A short history of the CANDU nuclear power system

International Nuclear Information System (INIS)

Brooks, G.L.

1993-04-01

This paper provides a short historical summary of the evolution of the CANDU nuclear power system with emphasis on the roles played by Ontario Hydro and private sector companies in Ontario in collaboration with Atomic Energy of Canada Limited (AECL). (author). 1 fig., 61 refs

Long Term Storage with Surveillance of Canadian Prototype Nuclear Power Reactors

International Nuclear Information System (INIS)

Janzen, Rick

2008-01-01

Atomic Energy of Canada (AECL) was originally formed by the government of Canada in 1952 to perform research in radiation and nuclear areas. In the mid 1950's Canada decided to limit itself to peaceful uses of nuclear energy and AECL embarked on several research and development programs, one of them being the development of nuclear power plants. This led to the development of the CANDU TM design of heavy water power reactors, of which there are now 29 operating around the world. This presentation discusses the present state of the first two CANDU TM prototype reactors and a prototype boiling light water reactor and lessons learnt after being in a long-term storage with surveillance state for more than 20 years. AECL facilities undergo decommissioning by either a prompt or a deferred removal approach. Both approaches are initiated after an operating facility has been declared redundant and gone through final operational shutdown. For the deferred approach, initial decommissioning activities are performed to put the facility into a sustainable, safe, shutdown state to minimize the hazards and costs of the ensuing extended storage with surveillance (SWS) or Safestor phase. At the appropriate time, the facility is dismantled and removed, or put into a suitable condition for re-use. AECL has a number of facilities that were built during its history, and some of these are now redundant or will become redundant in the near future. The deferred removal approach is part of AECL's decommissioning strategy for several reasons: 1. Reduction in radiation doses to workers during the final dismantling, 2. No facilities are available yet in Canada for the management of quantity of wastes arising from decommissioning, 3. Financial constraints presented by the number of facilities that will undergo decommissioning, compared to the availability of funds to carry out the work. This has led to the development of a comprehensive decommissioning plan that includes all of AECL's redundant

AELIB user's manual

International Nuclear Information System (INIS)

Evans, L.E.; Klawitter, G.L.

1981-05-01

This report is an updatable manual for users of AELIB, the AECL Library of FORTRAN-callable routines for the CRNL CDC 6600/CYBER 170 system. It provides general advice on the use of this library and detailed information on the selection and usage of particular library routines

Heating- and growing-degree days at Chalk River Nuclear Laboratories, 1976-1980

International Nuclear Information System (INIS)

Jay, P.C.; Wildsmith, D.P.

1981-05-01

An update of the report, Heating- and Growing-Degree-Days at Chalk River Nuclear Laboratories (AECL-5547) is presented along with various other meteorological variables which were not included in the previous publication. Also included, and shown in graph form, are the monthly degree-day frequencies. (author)

Shaft extension design at the Underground Research Laboratory, Pinawa, Manitoba

International Nuclear Information System (INIS)

Kuzyk, G.W.; Ball, A.E.

1991-01-01

AECL Research has constructed an underground laboratory for the research and development required for the Canadian Nuclear Fuel Waste Management Program. The experimental program in the laboratory will contribute to the assessment of the feasibility and safety of nuclear fuel waste disposal deep in stable plutonic rock. In 1988, AECL extended the shaft of the Underground Research Laboratory (URL) from the existing 255 m depth to a depth of 443 m in cooperation with the United States Department of Energy. The project, which involved carrying out research activities while excavation and construction work was in progress, required careful planning. To accommodate the research programs, full-face blasting with a burn cut was used to advance the shaft. Existing facilities at the URL had to be modified to accommodate an expanded underground facility at a new depth. This paper discusses the design criteria, shaft-sinking methods and approaches used to accommodate the research work during this shaft extension project. (11 refs., 11 figs.)

Licensing the ACR-700 in the USA

International Nuclear Information System (INIS)

Langman, V.; Ion, R.; Reid, C.; Snell, V.

2003-01-01

Atomic Energy of Canada Ltd. (AECL), via its 100% owned US subsidiary AECL Technologies Inc., is performing a pre-application review of the Advanced CANDU Reactor (ACR) with the US Nuclear Regulatory Commission (USNRC). Completion of this pre-application review by mid-2004, is in support of an application to the USNRC for Standard Design Certification that is targeted for the fall of 2004. The intent of the pre-application review is to deal up-front with potential issues associated with the CANDU reactor genealogy of the ACR that are different from the Light Water Reactor (LWR) and Boiling Water Reactor (BWR) regulatory framework in the USA. The focus of the paper will be to describe the pre-application review process currently underway with the NRC staff. In the context of the pre-application review this paper will provide an overview of the licensing approach being used to introduce the ACR-700 to the USA. (author)

Licensing the ACR-700 in the USA

Energy Technology Data Exchange (ETDEWEB)

Langman, V.; Ion, R. [Atomic Energy of Canada Limited, Mississauga, Ontario (Canada); Reid, C. [Bechtel Power Corporation, San Fransisco, California (United States); Snell, V. [Atomic Energy of Canada Limited, Mississauga, Ontario (Canada)

2003-07-01

Atomic Energy of Canada Ltd. (AECL), via its 100% owned US subsidiary AECL Technologies Inc., is performing a pre-application review of the Advanced CANDU Reactor (ACR) with the US Nuclear Regulatory Commission (USNRC). Completion of this pre-application review by mid-2004, is in support of an application to the USNRC for Standard Design Certification that is targeted for the fall of 2004. The intent of the pre-application review is to deal up-front with potential issues associated with the CANDU reactor genealogy of the ACR that are different from the Light Water Reactor (LWR) and Boiling Water Reactor (BWR) regulatory framework in the USA. The focus of the paper will be to describe the pre-application review process currently underway with the NRC staff. In the context of the pre-application review this paper will provide an overview of the licensing approach being used to introduce the ACR-700 to the USA. (author)

Large-scale hydrogen production using nuclear reactors

Energy Technology Data Exchange (ETDEWEB)

Ryland, D.; Stolberg, L.; Kettner, A.; Gnanapragasam, N.; Suppiah, S. [Atomic Energy of Canada Limited, Chalk River, ON (Canada)

2014-07-01

For many years, Atomic Energy of Canada Limited (AECL) has been studying the feasibility of using nuclear reactors, such as the Supercritical Water-cooled Reactor, as an energy source for large scale hydrogen production processes such as High Temperature Steam Electrolysis and the Copper-Chlorine thermochemical cycle. Recent progress includes the augmentation of AECL's experimental capabilities by the construction of experimental systems to test high temperature steam electrolysis button cells at ambient pressure and temperatures up to 850{sup o}C and CuCl/HCl electrolysis cells at pressures up to 7 bar and temperatures up to 100{sup o}C. In parallel, detailed models of solid oxide electrolysis cells and the CuCl/HCl electrolysis cell are being refined and validated using experimental data. Process models are also under development to assess options for economic integration of these hydrogen production processes with nuclear reactors. Options for large-scale energy storage, including hydrogen storage, are also under study. (author)

Program of experiments for the operating phase of the Underground Research Laboratory

International Nuclear Information System (INIS)

Simmons, G.R.; Bilinsky, D.M.; Davison, C.C.; Gray, M.N.; Kjartanson, B.H.; Martin, C.D.; Peters, D.A.; Lang, P.A.

1992-09-01

The Underground Research Laboratory (URL) is one of the major research and development facilities that AECL Research has constructed in support of the Canadian Nuclear Fuel Waste Management Program. The URL is a unique geotechnical research facility constructed in previously undisturbed plutonic rock, which was well characterized before construction. The site evaluation and construction phases of the URL project have been completed and the operating phase is beginning. A program of operating phase experiments that address AECL's objectives for in situ testing has been selected. These experiments were subjected to an external peer review and a subsequent review by the URL Experiment Committee in 1989. The comments from the external peer review were incorporated into the experiment plans, and the revised experiments were accepted by the URL Experiment Committee. Summaries of both reviews are presented. The schedule for implementing the experiments and the quality assurance to be applied during implementation are also summarized. (Author) (9 refs., 11 figs.)

A cooperative agreement for research on radioactive waste management between the United States Department of Energy and Atomic Energy of Canada Limited

International Nuclear Information System (INIS)

Dormuth, K.W.; Levich, R.A.

1994-01-01

The United States Department of Energy (USDOE) and Atomic Energy of Canada Limited (AECL) have a history of more than ten years of bilateral cooperation in the management of high level radioactive waste. In 1982, the USDOE and AECL executed a five year information-exchange agreement, for open-quotes Cooperation in Radioactive Waste Managementclose quotes. Since that time, this bilateral umbrella agreement has been renewed twice and the third renewal is currently being processed. International cooperation in high level radioactive waste management is highly beneficial to all concerned. Each nation involved in high level waste disposal has a single coordinated program for developing, testing, and evaluating approaches, hardware, and techniques for high level waste disposal. Thus there is limited opportunity for researchers in each country to exchange views regarding disposal technology with experienced researchers external to their own program, and to share research and development activities. The international arena, however, provides a host of organizations who have similar responsibilities and therefore similar interests and needs

Quality evaluation of the nuclear fuel manufactured in Romania before 1990

International Nuclear Information System (INIS)

Budan, O.; Galeriu, C.A.; Pascu, A.; Bailescu, A.; Andrei, G.

1997-01-01

Nuclear fuel fabricated in Romania before June 1990 was stored and was not licensed for the use in reactor. A preliminary appraisal performed by AECL and Zircatec experts in 1990, considered this fuel as being of suspect quality. Taking into consideration that Nuclear Fuel Plant was qualified to produce CANDU-6 fuel, only after 1990, RENEL-GEN authorized FCN to evaluate the actual quality of the stock fuel, in 1996. A documented evaluation program was developed and implemented. Stock production of each year was considered as one fuel bundle lot. Quality verification was done on statistical basis. Random sampling was applied, with the condition that each production week was represented in the sample. The results show that the fuel quality is not acceptable for in-reactor use. Recovery solutions for the stock fuel were established and already applied. An independent review of the program, results and recovery solutions, made by AECL confirmed the consistency of the work performed by FCN for stock fuel quality evaluation. (author)

R and D directions for the development of CANDU reactors

International Nuclear Information System (INIS)

Torgerson, D.F.

1998-01-01

Full text: AECL is carrying out a comprehensive R and D programme to advance all aspects of CANDU reactor technology. These programs are focusing on three main strategic directions: improved economics, enhanced safety, and fuel cycle flexibility. R and D areas include fuel cycle development, heavy water technology, fuel channel development, safety technology, control and instrumentation, reactor chemistry, systems and components, and health and environment. In each case, the R and D programs have short, medium, and long-term goals to achieve the overall strategic directions. Most of the programs seek to further develop and exploit some of the unique characteristics of pressurized heavy water reactors. Examples of this include high neutron economy and on-power fueling which allow several different fuel cycles, the presence of large water heat sinks for enhanced safety, and modular components that can be easily replaced for plant life extension. This presentation reviews AECL's product development directions and the R and D programs that have been begun for their development

Electron processing of fibre-reinforced advanced composites

International Nuclear Information System (INIS)

Singh, A.; Saunders, C.B.; Barnard, J.W.; Lopata, V.J.; Kremers, W.; McDougall, T.E.; Chung, M.; Tateishi, Miyoko

1996-01-01

Advanced composites, such as carbon-fibre-reinforced epoxies, are used in the aircraft, aerospace, sporting goods, and transportation industries. Though thermal curing is the dominant industrial process for advanced composites, electron curing of similar composites containing acrylated epoxy matrices has been demonstrated by our work. The main attraction of electron processing technology over thermal technology is the advantages it offers which include ambient temperature curing, reduced curing times, reduced volatile emissions, better material handling, and reduced costs. Electron curing technology allows for the curing of many types of products, such as complex shaped, those containing different types of fibres and up to 15 cm thick. Our work has been done principally with the AECL's 10 MeV, 1 kW electron accelerator; we have also done some comparative work with an AECL Gammacell 220. In this paper we briefly review our work on the various aspects of electron curing of advanced composites and their properties. (Author)

The disposal of Canada's nuclear fuel waste: public involvement and social aspects

International Nuclear Information System (INIS)

Greber, M.A.; Frech, E.R.; Hillier, J.A.R.

1994-01-01

This report describes the activities undertaken to provide information to the public about the Canadian Nuclear Fuel Waste Management Program as well as the opportunities for public involvement in the direction and development of the disposal concept through government inquiries and commissions and specific initiatives undertaken by AECL. Public viewpoints and the major issues identified by the public to be of particular concern and importance in evaluating the acceptability of the concept are described. In addition, how the issues have been addressed during the development of the disposal concept or how they could be addressed during implementation of the disposal concept are presented. There is also discussion of public perspectives of risk, the ethical aspects of nuclear fuel waste disposal, and public involvement in siting a nuclear fuel waste disposal facility. The Canadian Nuclear Fuel Waste Management Program is funded jointly by AECL and Ontario Hydro under the auspices of the CANDU Owners Group. (author)

Annunciation - building product team capabilities to support utility operational improvement

International Nuclear Information System (INIS)

Doucet, R.; Brown, R.; Trask, D.; Leger, R.; Mitchel, G.; Judd, R.; Davey, E.

2003-01-01

The purpose of this paper is to describe an AECL initiative to enhance the capabilities to assist utilities with undertaking annunciation improvement. This initiative was undertaken to complement a recent annunciation product upgrade, and in anticipation of developing commercial opportunities to assist Canadian and foreign utilities with control room annunciation improvement. Utilities are relying more and more on external engineering product and service providers to meet their plant support needs as they reduce in-house staffing to lower ongoing support costs. This evolving commercial environment places new demands on product and service providers, and provides new opportunities for increasing the proportion of product and service provider participation in plant improvement projects. This paper outlines recent AECL experience in the annunciation product area. The paper discusses the rationale for product support capability improvement, discusses the approaches undertaken, describes lessons learned, and outlines a proposed utility support model for assisting with future annunciation improvements. (author)

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

A study of the health of the employees of Atomic Energy of Canada Limited. 1

International Nuclear Information System (INIS)

Weeks, J.L.

1981-09-01

This report summarizes the status of Atomic Energy of Canada Ltd.'s health study of its present and past employees, and is a description of the steps which have been taken up to the time of writing. During the design phase there was a shift in the emphasis of the study. What was originally proposed as a study of mortality in a population of radiation workers, related spacifically to radiation exposure, has become a study of mortality data for all AECL employees. The interest in mortality as a function of occupational radiation expksure remains, but it is recognized that the data available to the study will probably be inadequate for the definition of a dose-effect relationship, although it will be useful in conjuction with other similar studies. The importance of cancer incidence is recognized, and the possibility of linking the AECL data to that contained in the National Cancer Incidence Reporting System is being pursued

Highlights of Bill C-14, the proposed new Nuclear Control Act

International Nuclear Information System (INIS)

Anon.

1978-01-01

If the bill is passed, the name of the regulatory body will be changed from the Atomic Energy Control Board to the Nuclear Control Board. It is intended to make the board more independent and removed from any involvement in the promotional and commercial aspects of the nuclear industry. The board will no longer answer to the same minister as AECL. Licensing applications will generally be published, except proprietary information. Public hearings will be a compulsory part of licensing major facilities. Various provisions of the bill are explained section by section. ''Prescribed substances'' under the act will definitely include all radionuclides and deuterium. A fund for decontamination will be endowed by licensees. The board will be able to make regulations for obsolete or abandoned sites, or for waste disposal sites. The part of the bill which deals with the responsibility of the Minister of Energy, Mines and Resources for A.E.C.L. generally remains unchanged from the previous act

Plutonium dispositioning in CANDU

International Nuclear Information System (INIS)

Boczar, P.G.; Feinroth, H.; Luxat, J.C.

1995-07-01

Recently, the U.S. Department of Energy (DOE) sponsored Atomic Energy of Canada Limited (AECL) to evaluate salient technical, strategic, schedule, and cost-related parameters of using CANDU reactors for dispositioning of weapons-grade plutonium in the form of Mixed OXide (MOX) fuel. A study team, consisting of key staff from the CANDU reactor designers and researchers (AECL), operators (Ontario Hydro) and fuel suppliers, analyzed all significant factors involved in such application, with the objective of identifying an arrangement that would permit the burning of MOX in CANDU at the earliest date. One of Ontario Hydro's multi-unit stations, Bruce A nuclear generating station (4x769 MW(e)), was chosen as the reference for the study. The assessment showed that no significant modifications of reactor or process systems are necessary to operate with a full MOX core. Plant modifications would be limited to fuel handling and modifications necessary to accommodate enhanced security and safeguards requirements. No safety limitations were identified

Improvement of antifungal and antibacterial antibiotic producing strain of Bacillus subtilis AFCI-69 by radiation and chemical mutagens. Part of a coordinated programme on radiation biology

International Nuclear Information System (INIS)

Ahmad, M.S.

1978-08-01

Gamma radiation was used to select higher antibiotic yield mutants of Bacillus subtilis AECL 69. The test organisms were Aspergillus niger RAGENI 70 and Staphylococcus aureus 6571 (16) N.C.T.C. Searches for fermentation, purification and characterization of antibiotics of parent strain and its mutants were carried out

MARS - a multidetector array for reaction studies

International Nuclear Information System (INIS)

Ball, G.C.; Davies, W.G.; Forster, J.S.

1988-03-01

The proposal for MARS, a Multidetector Array for Reaction Studies is presented. MARS consists of a large, high-vacuum vessel enclosing an array of 128 scintillation detectors for use in studies of heavy-ion collisions at TASCC. The instrument will be funded and owned jointly by AECL and NSERC

Evaluation of spiral wound reverse osmosis for four radioactive waste processing applications

International Nuclear Information System (INIS)

Sen Gupta, S.K.

1997-01-01

A pilot-scale spiral wound reverse osmosis rig was used to treat four significantly different radioactive waste streams, three of which were generated at the Chalk River Laboratories at AECL. These streams included: 1. A chemical decontamination (CD/DC) waste stream which is routinely treated by the plant-scale membrane system at CRL; 2. Reactor waste which is a dilute radioactive waste stream (containing primarily tritium and organic acids), and it an effluent from the operating reactors at AECL; 3. An ion exchange regenerant waste stream which contains a mixture of stream (1) (CD/DC), blended with secondary waste from ion exchange regeneration; 4. Boric acid simulated waste which is a by-product waste of the PWR reactors. This was the only stream treated that was not generated as a waste liquid at AECL. For the first three streams specified above, reverse osmosis was used to remove chemical and radiochemical impurities from the water with efficiencies usually exceeding 99%. In these three cases the 'permeate' or clean water was the product of the process. In the case of stream 4, reverse osmosis was used in a recovery application for the purpose of recycling boric acid back to the reactor, with the concentrate being the 'product'. Reverse osmosis technology was successfully demonstrated for the treatment of all four streams. Prefiltration and oxidation (with photocatalytic continuous oxidation technology) were evaluated as pretreatment alternatives for streams 1, 2, and 3. The results indicated that the effective crossflow velocity through and membrane vessel was more important in determining the extent of membrane fouling than the specific pretreatment strategy employed. (author)

Some thoughts for 'Energia Nucleara'

International Nuclear Information System (INIS)

Harris, David S.

2002-01-01

This is a report of an interview between the 'Energia Nucleara' reporter and Mr David S. Harris, the AECL project director for Cernavoda NPP Unit 2. The following items were addressed during the interview: the status of the Cernavoda NPP Unit 2 project; the differences in the project between Unit 1 and Unit 2; the Romanian infrastructure and industrial contributions to the Unit 2 project; the cooperation with Romanian design team; the Canadian authorities support to Unit 2 completion; Unit 3 project and AECL possible involvement. Following the Romanian Government's decision to complete Cernavoda Unit 2 in late 2002 work was recommenced in the key areas of engineering, procurement of equipment and materials signing of major supply contracts and construction, such that the total project is now 52% complete. actual construction activities are now 41% complete, and the number of key milestones have recently been achieved, such as: Closure of the Reactor Building 'B' Opening; commencement of rolling in of 45,000 main turbine condenser tubes; commencement of post-tensioning works on the Reactor Building structure and the completion of various infrastructure civil works. Structures and equipment already delivered, and installed or stored are in good conditions and ready for construction continuation. The following changes were implemented in Unit 2 as compared to Unit 1: design changes to meet new regulations and provide increases in the margin of safety; changes due to development of nuclear technology, particularly those improving performance and reliability of operation; design changes to replace equipment affected by obsolescence to allow purchasing of spare parts in the future. Concerning the future, AECL is willing to cooperate with the Romanian SNN on the Unit 3 completion process

The application of an integrated approach to design, procurement and construction in reducing overall nuclear power plant costs. Annex 19

International Nuclear Information System (INIS)

Didsbury, R.; Shalaby, B.A.; Torgerson, D.F.

2002-01-01

As part of its on-going efforts to reduce the cost of CANDU nuclear power plants, AECL has embarked on an integrated approach to design, procurement and construction activities associated with new CANDU 6 and CANDU 9 projects. The approach is predicated on the fact there is a vast quantity of information that needs to be managed and controlled over the life of a nuclear power plant project. Therefore, ensuring the completeness and correctness of all the information needed by all project participants, facilitating sharing of this information amongst the project's participants, and automating the various deliverable production processes offers significant potential not only for overall project cost (and schedule) savings but also for reducing operations and maintenance costs once the plant enters service. Facilitating and indeed of key importance to this approach is the use of a suite of integrated information technology-based engineering, procurement and project control tools used throughout the design, engineering, procurement and construction phases of the project. A unique and important feature of these tools is their high degree of integration both from a work process and a data perspective. Use of these tools is well underway on AECL's Qinshan Project which is realizing significant benefits in cost and schedule. This paper will describe the approach AECL is taking, along with the tools it has both put in place, and those additional items planned for the future along with the cost, schedule and quality benefits that arise from their use. Progress to date on the Qinshan project also will be discussed as well as the expected application to the plant once it has gone into service will also be discussed. (author)

Romanian nuclear fuel program: past, present and future

International Nuclear Information System (INIS)

Budan, O.; Rotaru, I.; Galeriu, C.A.

1997-01-01

The paper presents and comments the policy adopted in Romania for the production of CANDU-6 nuclear fuel before and after 1990. In this paper the word 'past' refers to the period before 1990 and 'present' to the 1990-1997 period. 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

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

Assessment of neutron transport codes for application to CANDU fuel lattices analysis

International Nuclear Information System (INIS)

Roh, Gyu Hong; Choi, Hang Bok

1999-08-01

In order to assess the applicability of WIMS-AECL and HELIOS code to the CANDU fuel lattice analysis, the physics calculations has been carried out for the standard CANDU fuel and DUPIC fuel lattices, and the results were compared with those of Monte Carlo code MCNP-4B. In this study, in order to consider the full isotopic composition and the temperature effect, new MCNP libraries have been generated from ENDF/B-VI release 3 and validated for typical benchmark problems. The TRX-1,2,BAPL-1,2,3 pin -cell lattices and KENO criticality safety benchmark calculations have been performed for the new MCNP libraries, and the results have shown that the new MCNP library has sufficient accuracy to be used for physics calculation. Then, the lattice codes have been benchmarked by the MCNP code for the major physics parameters such as the burnup reactivity, void reactivity, relative pin power and Doppler coefficient, etc. for the standard CANDU fuel and DUPIC fuel lattices. For the standard CANDU fuel lattice, it was found that the results of WIMS-AECL calculations are consistent with those of MCNP. For the DUPIC fuel lattice, however, the results of WIMS-AECL calculations with ENDF/B-V library have shown that the discrepancy from the results of MCNP calculations increases when the fuel burnup is relatively high. The burnup reactivities of WIMS-ACEL calculations with ENDF/B-VI library have shown excellent agreements with those of MCNP calculation for both the standard CANDU and DUPIC fuel lattices. However, the Doppler coefficient have relatively large discrepancies compared with MCNP calculations, and the difference increases as the fuel burns. On the other hand, the results of HELIOS calculation are consistent with those of MCNP even though the discrepancy is slightly larger compared with the case of the standard CANDU fuel lattice. this study has shown that the WIMS-AECL products reliable results for the natural uranium fuel. However, it is recommended that the WIMS

Hardware replacements and software tools for digital control computers

International Nuclear Information System (INIS)

Walker, R.A.P.; Wang, B-C.; Fung, J.

1996-01-01

Technological obsolescence is an on-going challenge for all computer use. By design, and to some extent good fortune, AECL has had a good track record with respect to the march of obsolescence in CANDU digital control computer technology. Recognizing obsolescence as a fact of life, AECL has undertaken a program of supporting the digital control technology of existing CANDU plants. Other AECL groups are developing complete replacement systems for the digital control computers, and more advanced systems for the digital control computers of the future CANDU reactors. This paper presents the results of the efforts of AECL's DCC service support group to replace obsolete digital control computer and related components and to provide friendlier software technology related to the maintenance and use of digital control computers in CANDU. These efforts are expected to extend the current lifespan of existing digital control computers through their mandated life. This group applied two simple rules; the product, whether new or replacement should have a generic basis, and the products should be applicable to both existing CANDU plants and to 'repeat' plant designs built using current design guidelines. While some exceptions do apply, the rules have been met. The generic requirement dictates that the product should not be dependent on any brand technology, and should back-fit to and interface with any such technology which remains in the control design. The application requirement dictates that the product should have universal use and be user friendly to the greatest extent possible. Furthermore, both requirements were designed to anticipate user involvement, modifications and alternate user defined applications. The replacements for hardware components such as paper tape reader/punch, moving arm disk, contact scanner and Ramtek are discussed. The development of these hardware replacements coincide with the development of a gateway system for selected CANDU digital control

Development of modern CANDU PHWR cross-section libraries for SCALE

International Nuclear Information System (INIS)

Shoman, Nathan T.; Skutnik, Steven E.

2016-01-01

Highlights: • New ORIGEN libraries for CANDU 28 and 37-element fuel assemblies have been created. • These new reactor data libraries are based on modern ENDF/B-VII.0 cross-section data. • The updated CANDU data libraries show good agreement with radiochemical assay data. • Eu-154 overestimated when using ENDF-VII.0 due to a lower thermal capture cross-section. - Abstract: A new set of SCALE fuel lattice models have been developed for the 28-element and 37-element CANDU fuel assembly designs using modern cross-section data from ENDF-B/VII.0 in order to produce new reactor data libraries for SCALE/ORIGEN depletion analyses. These new libraries are intended to provide users with a convenient means of evaluating depletion of CANDU fuel assemblies using ORIGEN through pre-generated cross sections based on SCALE lattice physics calculations. The performance of the new CANDU ORIGEN libraries in depletion analysis benchmarks to radiochemical assay data were compared to the previous version of the CANDU libraries provided with SCALE (based on WIMS-AECL models). Benchmark comparisons with available radiochemical assay data indicate that the new cross-section libraries perform well at matching major actinide species (U/Pu), which are generally within 1–4% of experimental values. The library also showed similar or better results over the WIMS-AECL library regarding fission product species and minor actinoids (Np, Am, and Cm). However, a notable exception was in calculated inventories of "1"5"4Eu and "1"5"5Eu, where the new library employing modern nuclear data (ENDF/B-VII.0) performed substantially poorer than the previous WIMS-AECL library (which used ENDF-B/VI.8 cross-sections for these species). The cause for this discrepancy appears to be due to differences in the "1"5"4Eu thermal capture cross-section between ENDF/B-VI.8 and ENDF/B-VII.0, an effect which is exacerbated by the highly thermalized flux of a CANDU heavy water reactor compared to that of a typical

R and D in support of CANDU plant life management

International Nuclear Information System (INIS)

Tapping, R.L.; Holt, R.A.

1999-01-01

One of the keys to the long-term success of CANDUs is a high capacity factor over the station design life. Considerable R and D in underway at AECL to develop technologies for assessing, monitoring and mitigating the effect of plant ageing and for improving plant performance and extending plant life. To achieve longer service life and to realize high capacity factor from CANDU stations, AECL is developing new technologies to enhance fuel channel and steam generator inspection capabilities, to monitor system health, and to allow preventive maintenance and cleaning (e.g., on-line chemical cleaning processes that produce small volumes of wastes). The life management strategy for fuel channels and steam generators requires a program to inspect components on a routine basis to identify mechanisms that could potentially affect fitness-for-service. In the case of fuel channels, the strategy includes inspections for dimensional changes, flaw detection, and deuterium concentration. New techniques are been developed to enhance these inspection capabilities; examples include accurate measurement of the gap between a pressure tube and its calandria tube and rapid full-length inspections of steam generator tubes for all known flaw types. Central to life management of components are Fitness-for-Service Guidelines (FFSG) that have been developed with the CANDU Owners Group (COG) that provide a standardized method to assess the potential for propagation of flaws detected during in-service inspections, and assessment of any change in fracture characteristics of the material. FFSG continue to be improved with the development of new technologies such as the capability to credit relaxation of stresses due to creep and non-rejectable flaws in pressure tubes. Effective management of plant systems throughout their lifetime requires much more than data acquisition and display - it requires that system health is continually monitored and managed. AECL has developed a system Health Monitor

Radioactive waste management in Canada: a bibliography of published literature

International Nuclear Information System (INIS)

Hawley, N.J.

1978-09-01

In view of the increased interest in the management of radioactive wastes, a need has been felt for a listing of Canadian publications in this field. Over one hundred AECL reports and other Canadian papers are included as well as a list of selected international conferences on the topic. (author)

TASCC newsletter volume 9 no. 7

International Nuclear Information System (INIS)

Thomson, L.

1995-07-01

A newsletter produced by Chalk River's Tandem Accelerator Superconducting Cyclotron Facility. Included in this July issue of TASCC is an update of the facility, submission of report by the Program Advisory Committee, government program review begins at AECL, awards to TASCC personnel and a listing of July's experiments. 2 figs

INC '93 overview

International Nuclear Information System (INIS)

Howe, Bruce

1993-01-01

At the close of the International Nuclear Congress, INC '93, held in Toronto in October 1993, Bruce Howe, then president of AECL, presented a 'Review and Conclusions' under the following headings: Introduction, Future Energy Requirements, Economics of electricity generation, Radioactive waste management, Reactor safety, Public acceptance, Technology developments, Future energy strategies, Conclusion

Potential uses of remote handling and robotic techniques in the back end of the fuel cycle

International Nuclear Information System (INIS)

Reynolds, N.P.; Tabe, T.; Fenton, N.; Baumgartner, P.

1984-01-01

Atomic Energy of Canada Limited (AECL) is actively conducting research on used fuel immobilization, used fuel reprocessing, and nuclear fuel waste immobilization and disposal. This paper attempts to identify potential uses of robotics and remote handling techniques in these areas, where their adoption could lead to significant processing, economic and safety advantages

Eddy current manual, volume 2

International Nuclear Information System (INIS)

Cecco, V.S.; Van Drunen, G.; Sharp, F.L.

1984-09-01

This report on eddy current testing is divided into three sections: (a) Demonstration of Basic Principles, (b) Practical (Laboratory) Tests and, (c) Typical Certification Questions. It is intended to be used as a supplement to ΣEddy Current Manual, Volume 1Σ (AECL-7523) during CSNDT Foundation Level II and III courses

The Atomic Energy of Canada Limited (AECL) employee health study

International Nuclear Information System (INIS)

Weeks, J.L.

1985-01-01

The Atomic Energy Health Study formally began in April 1980. The purpose of the study is to determine the causes of death among a population of radiation workers and to compare this information with data available for the causes of death in the general population. The study population and the implementation are briefly discussed. The aim of the study is to determine the real occupational risk of being a radiation worker. 3 refs

Laboratory and modeling studies in search of the critical hydrogen concentration

International Nuclear Information System (INIS)

Bartels, David; Wu, Weiqiang; Kanjana, Kotchaphan; Sims, Howard; Henshaw, Jim

2012-09-01

The great success of hydrogen water chemistry (HWC) for primary coolant in nuclear power plants is due to the prevention of net radiolysis and to maintenance of the corrosion potential below -230 mV (SHE) where the rate of stress corrosion cracking is minimized. The critical hydrogen concentration or CHC has been defined as that concentration of excess H 2 in primary coolant water, which prevents net water radiolysis via the chain reaction OH + H 2 ↔H 2 O + H (1, -1) H + H 2 O 2 → H 2 O + OH (2) The principle oxidizing free radical (OH) is thus converted into a reducing radical (H), oxidation products are reduced back to water, and the net result is no chemical change. A set of benchmark experiments at the U2 reactor in Chalk River have been reported in an extensive AECL report, which indicate that the CHC in this reactor is ca. 25 micro-molar. Using the review of yields and reaction rates set forth in another recent AECL report, the Chalk River experiments have been modelled in work at NNL, Harwell. The model was not able to successfully reproduce the experimental CHC, or the steady-state H 2 concentrations (SSH2) in the absence of excess hydrogen. A sensitivity analysis of the entire model was carried out. Essentially three important variables have been found to dominate the result. Reaction rate (1) is overwhelmingly important in determining how much H 2 is needed to accomplish the chain back-reaction. Almost with equal importance, the back reaction (-1) needs to be considered at 300 deg. C, but there is some uncertainty of its magnitude. Finally, the relative yields of radicals and molecular products (i.e. H 2 , H 2 O 2 ) in particular H 2 :OH from the radiolysis are critical. Laboratory studies of hydrogenated water radiation chemistry have been carried out with a van de Graaff electron accelerator at Notre Dame Radiation Laboratory. Modelling of the hydrogen produced as a function of the hydrogen input, suggests that the reaction rate (-1) is ca. two

Emergency core cooling system sump chemical effects on strainer head loss

International Nuclear Information System (INIS)

Edwards, M.K.; Qiu, L.; Guzonas, D.A.

2010-01-01

Chemical precipitates formed in the recovery water following a Loss of Coolant Accident (LOCA) have the potential to increase head loss across the Emergency Core Cooling System (ECCS) strainer, and could lead to cavitation of the ECCS pumps, pump failure and loss of core cooling. AECL, as a strainer vendor and research organization, has been involved in the investigation of chemical effects on head loss for its CANDU® and Pressurized Water Reactor (PWR) customers. The chemical constituents of the recovery sump water depend on the combination of chemistry control additives and the corrosion and dissolution products from metals, concrete, and insulation materials. Some of these dissolution and corrosion products (e.g., aluminum and calcium) may form significant quantities of precipitates. The presence of chemistry control additives such as sodium hydroxide, trisodium phosphate and boric acid can significantly influence the precipitates formed. While a number of compounds may be shown to be thermodynamically possible under the conditions assumed for precipitation, kinetic factors play a large role in the morphology of precipitates. Precipitation is also influenced by insulation debris, which can trap precipitates and act as nucleation sites for heterogeneous precipitation. This paper outlines the AECL approach to resolving the issue of chemical effects on ECCS strainer head loss, which included modeling, bench top testing and reduced-scale testing; the latter conducted using a temperature-controlled variable-flow closed-loop test rig that included an AECL Finned Strainer® test section equipped with a differential pressure transmitter. Models of corrosion product release and the effects of precipitates on head loss will also be presented. Finally, this paper discusses the precipitates found in test debris beds and presents a possible method for chemical effects head loss modeling. (author)

Lattice cell and full core physics of internally cooled annular fuel in heavy water moderated reactors

Energy Technology Data Exchange (ETDEWEB)

Armstrong, J.; Hamilton, H.; Hyland, B. [Atomic Energy of Canada Limited, Chalk River Laboratories, Chalk River, Ontario, K0J 1J0 (Canada)

2013-07-01

A program is underway at Atomic Energy of Canada Limited (AECL) to develop a new fuel bundle concept to enable greater burnups for PT-HWR (pressure tube heavy water reactor) cores. One option that AECL is investigating is an internally cooled annular fuel (ICAF) element concept. ICAF contains annular cylindrical pellets with cladding on the inner and outer diameters. Coolant flows along the outside of the element and through the centre. With such a concept, the maximum fuel temperature as a function of linear element rating is significantly reduced compared to conventional, solid-rod type fuel. The preliminary ICAF bundle concept considered in this study contains 24 half-metre long internally cooled annular fuel elements and one non-fuelled centre pin. The introduction of the non-fuelled centre pin reduces the coolant void reactivity (CVR), which is the increase in reactivity that occurs on voiding the coolant in accident scenarios. Lattice cell and full core physics calculations of the preliminary ICAF fuel bundle concept have been performed for medium burnups of approximately 18 GWd/tU using WIMS-AECL and reactor fuel simulation program (RFSP). The results will be used to assist in concept configuration optimization. The effects of radial and axial core power distributions, linear element power ratings, refuelling rates and operational power ramps have been analyzed. The results suggest that burnups of greater than 18 GWd/tU can be achieved in current reactor designs. At approximately 18 GWd/tU, expected maximum linear element ratings in a PT-HWR with online-refuelling are approximately 90 kW/m. These conditions would be prohibitive for solid-rod fuel, but may be possible in ICAF fuel given the reduced maximum fuel temperature as a function of linear element rating. (authors)

Lattice cell and full core physics of internally cooled annular fuel in heavy water moderated reactors

International Nuclear Information System (INIS)

Armstrong, J.; Hamilton, H.; Hyland, B.

2013-01-01

A program is underway at Atomic Energy of Canada Limited (AECL) to develop a new fuel bundle concept to enable greater burnups for PT-HWR (pressure tube heavy water reactor) cores. One option that AECL is investigating is an internally cooled annular fuel (ICAF) element concept. ICAF contains annular cylindrical pellets with cladding on the inner and outer diameters. Coolant flows along the outside of the element and through the centre. With such a concept, the maximum fuel temperature as a function of linear element rating is significantly reduced compared to conventional, solid-rod type fuel. The preliminary ICAF bundle concept considered in this study contains 24 half-metre long internally cooled annular fuel elements and one non-fuelled centre pin. The introduction of the non-fuelled centre pin reduces the coolant void reactivity (CVR), which is the increase in reactivity that occurs on voiding the coolant in accident scenarios. Lattice cell and full core physics calculations of the preliminary ICAF fuel bundle concept have been performed for medium burnups of approximately 18 GWd/tU using WIMS-AECL and reactor fuel simulation program (RFSP). The results will be used to assist in concept configuration optimization. The effects of radial and axial core power distributions, linear element power ratings, refuelling rates and operational power ramps have been analyzed. The results suggest that burnups of greater than 18 GWd/tU can be achieved in current reactor designs. At approximately 18 GWd/tU, expected maximum linear element ratings in a PT-HWR with online-refuelling are approximately 90 kW/m. These conditions would be prohibitive for solid-rod fuel, but may be possible in ICAF fuel given the reduced maximum fuel temperature as a function of linear element rating. (authors)

Predicting steam generator crevice chemistry

International Nuclear Information System (INIS)

Burton, G.; Strati, G.

2006-01-01

'Full text:' Corrosion of steam cycle components produces insoluble material, mostly iron oxides, that are transported to the steam generator (SG) via the feedwater and deposited on internal surfaces such as the tubes, tube support plates and the tubesheet. The build up of these corrosion products over time can lead to regions of restricted flow with water chemistry that may be significantly different, and potentially more corrosive to SG tube material, than the bulk steam generator water chemistry. The aim of the present work is to predict SG crevice chemistry using experimentation and modelling as part of AECL's overall strategy for steam generator life management. Hideout-return experiments are performed under CANDU steam generator conditions to assess the accumulation of impurities in hideout, and return from, model crevices. The results are used to validate the ChemSolv model that predicts steam generator crevice impurity concentrations, and high temperature pH, based on process parameters (e.g., heat flux, primary side temperature) and blowdown water chemistry. The model has been incorporated into ChemAND, AECL's system health monitoring software for chemistry monitoring, analysis and diagnostics that has been installed at two domestic and one international CANDU station. ChemAND provides the station chemists with the only method to predict SG crevice chemistry. In one recent application, the software has been used to evaluate the crevice chemistry based on the elevated, but balanced, SG bulk water impurity concentrations present during reactor startup, in order to reduce hold times. The present paper will describe recent hideout-return experiments that are used for the validation of the ChemSolv model, station experience using the software, and improvements to predict the crevice electrochemical potential that will permit station staff to ensure that the SG tubes are in the 'safe operating zone' predicted by Lu (AECL). (author)

Assessment of CANDU physics codes using experimental data - II: CANDU core physics measurements

International Nuclear Information System (INIS)

Roh, Gyu Hong; Jeong, Chang Joon; Choi, Hang Bok

2001-11-01

Benchmark calculations of the advanced CANDU reactor analysis tools (WIMS-AECL, SHETAN and RFSP) and the Monte Carlo code MCNP-4B have been performed using Wolsong Units 2 and 3 Phase-B measurement data. In this study, the benchmark calculations have been done for the criticality, boron worth, reactivity device worth, reactivity coefficient, and flux scan. For the validation of the WIMS-AECL/SHETANRFSP code system, the lattice parameters of the fuel channel were generated by the WIMS-AECL code, and incremental cross sections of reactivity devices and structural material were generated by the SHETAN code. The results have shown that the criticality is under-predicted by -4 mk. The reactivity device worths are generally consistent with the measured data except for the strong absorbers such as shutoff rod and mechanical control absorber. The heat transport system temperature coefficient and flux distributions are in good agreement with the measured data. However, the moderator temperature coefficient has shown a relatively large error, which could be caused by the incremental cross-section generation methodology for the reactivity device. For the MCNP-4B benchmark calculation, cross section libraries were newly generated from ENDF/B-VI release 3 through the NJOY97.114 data processing system and a three-dimensional full core model was developed. The simulation results have shown that the criticality is estimated within 4 mk and the estimated reactivity worth of the control devices are generally consistent with the measurement data, which implies that the MCNP code is valid for CANDU core analysis. In the future, therefore, the MCNP code could be used as a reference tool to benchmark design and analysis codes for the advanced fuels for which experimental data are not available

A plan for the modification and assessment of TRAC-PF1/MOD2 for use in analyzing CANDU 3 transient thermal-hydraulic phenomena

International Nuclear Information System (INIS)

Siebe, D.A.; Boyack, B.E.; Giguere, P.T.

1994-11-01

This report presents the results of the review and planning done for the United States Nuclear Regulatory Commission to identify the thermal-hydraulic phenomena that could occur in the CANDU 3 reactor design during transient conditions, plan modifications to the TRAC-PF1/MOD2 (TRAC) computer code needed to adequately predict CANDU 3 transient thermal-hydraulic phenomena, and identify an assessment program to verify the ability of TRAC, when modified, to predict these phenomena. This work builds on analyses and recommendations produced by the Idaho National Engineering Laboratory (INEL). To identify the thermal-hydraulic phenomena, a large-break loss-of-coolant accident simulation, performed as part of earlier work by INEL with an Atomic Energy of Canada, Limited (AECL) thermal-hydraulic computer code (CATHENA), was analyzed in detail. Other accident scenarios were examined for additional phenomena. A group of Los Alamos National Laboratory reactor thermal-hydraulics experts ranked the phenomena to produce a preliminary phenomena identification and ranking table (PIRT). The preliminary nature of the PIRT was a result of a lack of direct expertise with the unique processes and phenomena of the CANDU 3. Nonetheless, this PIRT provided an adequate foundation for planning a program of code modifications. We believe that this PIRT captured the most important phenomena and that refinements to the PIRT will mainly produce clarification of the relative importance (ranking) of phenomena. A plan for code modifications was developed based on this PIRT and on information about the modeling methodologies for CANDU-specific phenomena used in AECL codes. AECL thermal-hydraulic test facilities and programs were reviewed and the information used in developing an assessment plan to ensure that TRAC-PF1/MOD2, when modified, will adequately predict CANDU 3 phenomena

Quebec Gentilly 2 nuclear power station

International Nuclear Information System (INIS)

Labbe, J.A.

Modifications and commissioning of the Gentilly reactor are described. The Gentilly reactor is owned by AECL, not Quebec Hydro, and has served as a prototype reactor. The Gentilly-2 reactor is a 'packaged' 600 MWe PHW reactor similar to Pickering-1, etc. Interesting aspects of construction and purchasing of equipment are described. (E.C.B.)

Catalytic hydrogen recombination for nuclear containments

International Nuclear Information System (INIS)

Koroll, G.W.; Lau, D.W.P.; Dewit, W.A.; Graham, W.R.C.

1994-01-01

Catalytic recombiners appear to be a credible option for hydrogen mitigation in nuclear containments. The passive operation, versatility and ease of back fitting are appealing for existing stations and new designs. Recently, a generation of wet-proofed catalyst materials have been developed at AECL which are highly specific to H 2 -O 2 , are active at ambient temperatures and are being evaluated for containment applications. Two types of catalytic recombiners were evaluated for hydrogen removal in containments based on the AECL catalyst. The first is a catalytic combustor for application in existing air streams such as provided by fans or ventilation systems. The second is an autocatalytic recombiner which uses the enthalpy of reaction to produce natural convective flow over the catalyst elements. Intermediate-scale results obtained in 6 m 3 and 10 m 3 spherical and cylindrical vessels are given to demonstrate self-starting limits, operating limits, removal capacity, scaling parameters, flow resistance, mixing behaviour in the vicinity of an operating recombiner and sensitivity to poisoning, fouling and radiation. (author). 13 refs., 10 figs

PEAR code review

International Nuclear Information System (INIS)

De Wit, R.; Jamieson, T.; Lord, M.; Lafortune, J.F.

1997-07-01

As a necessary component in the continuous improvement and refinement of methodologies employed in the nuclear industry, regulatory agencies need to periodically evaluate these processes to improve confidence in results and ensure appropriate levels of safety are being achieved. The independent and objective review of industry-standard computer codes forms an essential part of this program. To this end, this work undertakes an in-depth review of the computer code PEAR (Public Exposures from Accidental Releases), developed by Atomic Energy of Canada Limited (AECL) to assess accidental releases from CANDU reactors. PEAR is based largely on the models contained in the Canadian Standards Association (CSA) N288.2-M91. This report presents the results of a detailed technical review of the PEAR code to identify any variations from the CSA standard and other supporting documentation, verify the source code, assess the quality of numerical models and results, and identify general strengths and weaknesses of the code. The version of the code employed in this review is the one which AECL intends to use for CANDU 9 safety analyses. (author)

A practical process for light-water detritiation at large scales

Energy Technology Data Exchange (ETDEWEB)

Boniface, H.A. [Atomic Energy of Canada Limited, Chalk River, ON (Canada); Robinson, J., E-mail: jr@tyne-engineering.com [Tyne Engineering, Burlington, ON (Canada); Gnanapragasam, N.V.; Castillo, I.; Suppiah, S. [Atomic Energy of Canada Limited, Chalk River, ON (Canada)

2014-07-01

AECL and Tyne Engineering have recently completed a preliminary engineering design for a modest-scale tritium removal plant for light water, intended for installation at AECL's Chalk River Laboratories (CRL). This plant design was based on the Combined Electrolysis and Catalytic Exchange (CECE) technology developed at CRL over many years and demonstrated there and elsewhere. The general features and capabilities of this design have been reported as well as the versatility of the design for separating any pair of the three hydrogen isotopes. The same CECE technology could be applied directly to very large-scale wastewater detritiation, such as the case at Fukushima Daiichi Nuclear Power Station. However, since the CECE process scales linearly with throughput, the required capital and operating costs are substantial for such large-scale applications. This paper discusses some options for reducing the costs of very large-scale detritiation. Options include: Reducing tritium removal effectiveness; Energy recovery; Improving the tolerance of impurities; Use of less expensive or more efficient equipment. A brief comparison with alternative processes is also presented. (author)

The geochemical environment of nuclear fuel waste disposal

International Nuclear Information System (INIS)

Gascoyne, M.

1995-01-01

The concept for disposal of Canada's nuclear fuel waste in a geologic environment on the Canadian Shield has recently been presented by Atomic Energy of Canada Limited (AECL) to governments, scientists, and the public, for review. An important part of this concept concerns the geochemical environment of a disposal vault and includes consideration of rock and groundwater compositions, geochemical interactions between rocks, groundwaters, and emplaced vault materials, and the influences and significance of anthropogenic and microbiological effects following closure of the vault. This paper summarizes the disposal concept and examines aspects of the geochemical environment. The presence of saline groundwaters and reducing conditions at proposed vault depths (500-1000 m) in the Canadian Shield has an important bearing on the stability of the used nuclear fuel, its container, and buffer and backfill materials. The potential for introduction of anthropogenic contaminants and microbes during site investigations and vault excavation, operation, and sealing is described with examples from AECL's research areas on the Shield and in their underground research laboratory in southeastern Manitoba. (author)

Management of legacy spent nuclear fuel wastes at the Chalk River Laboratories: operating experience and progress towards waste remediation

International Nuclear Information System (INIS)

Cox, D.S.; Bainbridge, I.B.; Greenfield, K.R.

2006-01-01

AECL has been managing and storing a diversity of spent nuclear fuel, arising from operations at its Chalk River Laboratories (CRL) site over more than 50 years. A subset of about 22 tonnes of research reactor fuels, primarily metallic uranium, have been identified as a high priority for remediation, based on monitoring and inspection that has determined that these fuels and their storage containers are corroding. This paper describes the Fuel Packaging and Storage (FPS) project, which AECL has launched to retrieve these fuels from current storage, and to emplace them in a new above-ground dry storage system, as a prerequisite step to decommissioning some of the early-design waste storage structures at CRL. The retrieved fuels will be packaged in a new storage container, and subjected to a cold vacuum drying process that will remove moisture, and thereby reduce the extent of future corrosion and degradation. The FPS project will enable improved interim storage to be implemented for legacy fuels at CRL, until a decision is made on the ultimate disposition of legacy fuels in Canada. (author)

Prototype CIRCE plant-industrial demonstration of heavy-water production from a reformed hydrogen source

Energy Technology Data Exchange (ETDEWEB)

Spagnolo, D.A.; Boniface, H.A.; Sadhankar, R.R.; Everatt, A.E.; Miller, A.I. [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada); Blouin, J. [Air Liquide Canada, Hamilton, Ontario (Canada)

2002-09-01

Heavy-water (D{sub 2}0) production has been dominated by the Girdler-Sulphide (G-S) process, which suffers several intrinsic disadvantages that lead to high production costs. Processes based on hydrogen/water exchange have become more attractive with the development of proprietary wetproofed catalysts by AECL. One process that is synergistic with industrial hydrogen production by steam methane reforming (SMR), the combined industrial reforming and catalytic exchange (CIRCE) process, offers the best prospect for commercialization. SMRs are common globally in the oil upgrading and ammonia industries. To study the CIRCE process in detail, AECL, in collaboration with Air Liquide Canada, constructed a prototype CIRCE plant (PCP) in Hamilton, ON. The plant became fully operational in 2000 July and is expected to operate to at least the late fall of 2002. To date, plant operation has confirmed the adequacy of the design and the capability of enriching deuterium to produce heavy water without compromising hydrogen production. The proprietary wetproofed catalyst has performed as expected, both in activity and in robustness. (author)

Input modelling of ASSERT-PV V2R8M1 for RUFIC fuel bundle

Energy Technology Data Exchange (ETDEWEB)

Park, Joo Hwan; Suk, Ho Chun

2001-02-01

This report describes the input modelling for subchannel analysis of CANFLEX-RU (RUFIC) fuel bundle which has been developed for an advanced fuel bundle of CANDU-6 reactor, using ASSERT-PV V2R8M1 code. Execution file of ASSERT-PV V2R8M1 code was recently transferred from AECL under JRDC agreement between KAERI and AECL. SSERT-PV V2R8M1 which is quite different from COBRA-IV-i code has been developed for thermalhydraulic analysis of CANDU-6 fuel channel by subchannel analysis method and updated so that 43-element CANDU fuel geometry can be applied. Hence, ASSERT code can be applied to the subchannel analysis of RUFIC fuel bundle. The present report was prepared for ASSERT input modelling of RUFIC fuel bundle. Since the ASSERT results highly depend on user's input modelling, the calculation results may be quite different among the user's input models. The objective of the present report is the preparation of detail description of the background information for input data and gives credibility of the calculation results.

Input modelling of ASSERT-PV V2R8M1 for RUFIC fuel bundle

International Nuclear Information System (INIS)

Park, Joo Hwan; Suk, Ho Chun

2001-02-01

This report describes the input modelling for subchannel analysis of CANFLEX-RU (RUFIC) fuel bundle which has been developed for an advanced fuel bundle of CANDU-6 reactor, using ASSERT-PV V2R8M1 code. Execution file of ASSERT-PV V2R8M1 code was recently transferred from AECL under JRDC agreement between KAERI and AECL. SSERT-PV V2R8M1 which is quite different from COBRA-IV-i code has been developed for thermalhydraulic analysis of CANDU-6 fuel channel by subchannel analysis method and updated so that 43-element CANDU fuel geometry can be applied. Hence, ASSERT code can be applied to the subchannel analysis of RUFIC fuel bundle. The present report was prepared for ASSERT input modelling of RUFIC fuel bundle. Since the ASSERT results highly depend on user's input modelling, the calculation results may be quite different among the user's input models. The objective of the present report is the preparation of detail description of the background information for input data and gives credibility of the calculation results

Strategic provisioning of replacement parts for CANDU power plants

International Nuclear Information System (INIS)

Mizuno, G.; Tume, P.; Prentice, J.

2000-01-01

Provisioning of replacement parts and management of critical spares are key factors in optimizing maintenance programs for CANDU power plants. With a view to supply assurance, Atomic Energy Canada Limited (AECL) has created a Spare Parts Branch (SPB) to provide a clear pipeline from the client to the delivered replacement part(s). SPB provides the client with assured access to a qualified supplier database, computer aided design, engineering and manufacturing services and material upgrades and design registration through the authorized inspection agency. The AECL spare parts strategic provisioning service plan that has four thrusts: 1) the efficient delivery of cost-effective replacement parts; 2) obsolete parts resolution; 3) a website that will provide our clients with real-time access to replacement part data; and 4) inventory recovery opportunities. Thrusts one and two are actively ensuring plant maintenance for on-shore and off-shore CANDU clients. Thrusts three and four are longer-term commitments. This paper will explore these thrusts in the context of our CANDU business practices. (author)

Attenuation of contaminant plumes in homogeneous aquifers: Sensitivity to source function at moderate to large peclet numbers

International Nuclear Information System (INIS)

Selander, W.N.; Lane, F.E.; Rowat, J.H.

1995-05-01

A groundwater mass transfer calculation is an essential part of the performance assessment for radioactive waste disposal facilities. AECL's IRUS (Intrusion Resistant Underground Structure) facility, which is designed for the near-surface disposal of low-level radioactive waste (LLRW), is to be situated in the sandy overburden at AECL's Chalk River Laboratories. Flow in the sandy aquifers at the proposed IRUS site is relatively homogeneous and advection-dominated (large Peclet numbers). Mass transfer along the mean direction of flow from the IRUS site may be described using the one-dimensional advection-dispersion equation, for which a Green's function representation of downstream radionuclide flux is convenient. This report shows that in advection-dominated aquifers, dispersive attenuation of initial contaminant releases depends principally on two time scales: the source duration and the pulse breakthrough time. Numerical investigation shows further that the maximum downstream flux or concentration depends on these time scales in a simple characteristic way that is minimally sensitive to the shape of the initial source pulse. (author). 11 refs., 2 tabs., 3 figs

Introduction of microbial nutrients in a nuclear fuel waste disposal vault as a result of excavation and operation activities

Energy Technology Data Exchange (ETDEWEB)

Stroes-Gascoyne, S; Gascoyne, M; Onagi, D; Thomas, D A; Hamon, C J; Watson, R; Porth, R J

1996-08-01

A nuclear fuel waste disposal vault would not likely be a sterile environment. Bacterial activity would be expected in those areas of the vault conducive to bacterial life, i.e., where effects of heat, moisture content, radiation and compaction would not prevent or severely restrict bacterial life and where suitable and sufficient nutrients would be present. An inventory of bacterial nutrients that would be emplaced `intentionally` with vault materials (fuel waste, waste containers, buffer and backfill materials) has been made previously. This report assesses bacterial nutrients that would be added `inadvertently` to a vault in the form of residues of materials used to excavate and operate a vault. Measurements of blasting material residues in the various water supplies, excavated broken rock (muck) and in cores drilled in old and new tunnel walls were made at AECL`s Underground Research Laboratory. Results show that the largest potential nutrient addition (both carbon and nitrogen) to a vault would result from using untreated excavated broken rock as part of the backfill. (author). 16 refs., 4 tabs., 10 figs.

Enhanced CANDU 6 (EC6): a proven mid-sized reactor with fuel cycle capability

International Nuclear Information System (INIS)

Hopwood, J.; Soulard, M.; Hastings, I.J.

2011-01-01

Atomic Energy of Canada (AECL) is finalizing development of the Enhanced CANDU 6 (EC6), which incorporates the CANDU 6's well-proven features, and adds enhancements that make the reactor even more safe and easier to operate. The EC6 is the only mid-sized reactor (700 MWe class) with a proven pedigree that meets modern reactor expectations and regulatory standards. It is sized for smaller grids and also has outstanding fuel-cycle capability. Changes are incremental and consistent with the CANDU 6 project approach. The EC6 utilizes modern computers and a distributed control system housed in an advanced control room which, along with automated testing and on-line diagnostics, make the plant easier and safer to operate, with minimal operator intervention. Containment and seismic capability are upgraded to meet modern standards. The first deployment of the EC6 is anticipated in Canada; international markets are also being pursued. AECL is performing a comprehensive review of the EC6 design in the wake of the Fukushima accident, will review lessons learned, and incorporate any necessary improvements into new build design. (author)

Enhanced CANDU 6 (EC6): a proven mid-sized reactor with fuel cycle capability

International Nuclear Information System (INIS)

Hopwood, J.; Soulard, M.; Hastings, I.J.

2011-01-01

Atomic Energy of Canada (AECL) is finalizing development of the Enhanced CANDU 6 (EC6), which incorporates the CANDU 6's well-proven features, and enhancements that make the reactor even more safe and easier to operate. The EC6 is the only mid-sized reactor (700 MWe class) with a proven pedigree that meets modern reactor expectations and regulatory standards. It is sized for smaller grids and also has outstanding fuel-cycle capability. Changes are incremental and consistent with the CANDU 6 project approach. The EC6 utilizes modern computers and a distributed control system housed in an advanced control room which, along with automated testing and on-line diagnostics, make the plant easier and safer to operate, with minimal operator intervention. Containment and seismic capability are upgraded to meet modern standards. The first deployment of the EC6 is anticipated in Canada; international markets are also being pursued. AECL is performing a comprehensive review of the EC6 design in the wake of the Fukushima accident, will review lessons learned, and incorporate any necessary improvements into new build design. (author)

Fabrication of a CANFLEX-RU designed bundle for power ramp irradiation test in NRU

International Nuclear Information System (INIS)

Cho, Moon Sung

2000-11-01

The BDL-443 CANFLEX-RU bundle AKW was fabricated at Korea Atomic Energy Research Institute (KAERI) for power ramp irradiation testing in NRU reactor. The bundle was fabricated with IDR and ADU fuel pellets in adjacent elements and contains fuel pellets enriched to 1.65 wt% 235 U in the outer and intermediate rings and also contains pellets enriched to 2.00 wt% 235 U in the inner ring. This bundle does not have a center element to allow for insertion on a hanger bar. KAERI produced the IDR pellets with the IDR-source UO 2 powder supplied by BNFL. ADU pellets were fabricated and supplied by AECL. Bundle kits (Zircaloy-4 end plates, end plugs, and sheaths with brazed appendages) manufactured at KAERI earlier in 1996 were used for the fabrication of the bundle. The CANFLEX bundle was fabricated successfully at KAERI according to the QA provisions specified in references and as per relevant KAERI drawings and technical specification. This report covers the fabrication activities performed at KAERI. Fabrication processes performed at AECL will be documented in a separate report

Radionuclide migration in groundwater at a low-level waste disposal site: a comparison of predictive performance modeling versus field observations

International Nuclear Information System (INIS)

Robertson, D.E.; Myers, D.A.; Abel, K.H.; Bergeron, M.P.; Champ, D.R.; Killey, R.W.D.; Moltyaner, G.L.; Young, J.L.

1986-01-01

This paper describes a project which is structured to test the concept of modeling a shallow land low-level waste burial site. The project involves a comparison of the actual observed radionuclide migration in groundwaters at a 30-year old well-monitored field site with the results of predictive transport modeling. The comparison is being conducted as a cooperative program with the Atomic Energy of Canada Ltd. (AECL) at the low-level waste management area at the Chalk River Nuclear Laboratories, Ontario, Canada. A joint PNL-AECL field investigation was conducted in 1983 and 1984 to compliment the existing extensive data base on actual radionuclide migration. Predictive transport modeling is currently being conducted for this site; first, as if it were a new location being considered for a low-level waste shallow-land burial site and only minimal information about the site were available, and second, utilizing the extensive data base available for the site. The modeling results will then be compared with the level of effort needed to reasonably predict the spacial and temporal movement of radionuclides in the groundwater environment

Removal of a seized fuel channel from the KANUPP reactor

International Nuclear Information System (INIS)

Butt, W.M.; Gunn, R.J.

1995-01-01

In support of the Safe operation of KANUPP program, AECL was commissioned in early 1992 to assist the Karachi Nuclear Power Plant in the design and supply of equipment and procedures for removal of a seized fuel channel from the KANUPP CANDU reactor. In addition AECL was also asked to supply technical site support to assist the KANUPP station staff during the removal of the G-12 channel. The design of a fuel channel removal system presented an interesting challenge. The fuel channel design was unique to KANUPP with no history of previous channel removal, consequently nearly all tools and equipment had to be specially designed. In addition, the seized end fitting posed a special problem requiring the development several contingency tools and techniques. This paper is an account of the design and development of the removal system and the site experiences during the actual fuel channel removal. After the channel had been removed, it was confirmed that a corrosion seizure between the end fitting sleeve bearings was inhibiting normal channel elongation. (author)

Prototype CIRCE plant-industrial demonstration of heavy-water production from a reformed hydrogen source

International Nuclear Information System (INIS)

Spagnolo, D.A.; Boniface, H.A.; Sadhankar, R.R.; Everatt, A.E.; Miller, A.I.; Blouin, J.

2002-09-01

Heavy-water (D 2 0) production has been dominated by the Girdler-Sulphide (G-S) process, which suffers several intrinsic disadvantages that lead to high production costs. Processes based on hydrogen/water exchange have become more attractive with the development of proprietary wetproofed catalysts by AECL. One process that is synergistic with industrial hydrogen production by steam methane reforming (SMR), the combined industrial reforming and catalytic exchange (CIRCE) process, offers the best prospect for commercialization. SMRs are common globally in the oil upgrading and ammonia industries. To study the CIRCE process in detail, AECL, in collaboration with Air Liquide Canada, constructed a prototype CIRCE plant (PCP) in Hamilton, ON. The plant became fully operational in 2000 July and is expected to operate to at least the late fall of 2002. To date, plant operation has confirmed the adequacy of the design and the capability of enriching deuterium to produce heavy water without compromising hydrogen production. The proprietary wetproofed catalyst has performed as expected, both in activity and in robustness. (author)

Prototype CIRCE plant - industrial demonstration of heavy water production from reformed hydrogen source

International Nuclear Information System (INIS)

Spagnolo, D.A.; Boniface, H.A.; Sadhankar, R.R.; Everatt, A.E.; Miller, A.I.; Blouin, J.

2002-01-01

Heavy water (D 2 0) production has been dominated by the Girdler-Sulphide (G-S) process, which suffers several intrinsic disadvantages that lead to high production costs. Processes based on hydrogen/water exchange have become more attractive with the development of proprietary wetproofed catalysts by AECL. One process that is synergistic with industrial hydrogen production by steam methane reforming (SMR), the Combined Industrial Reforming and Catalytic Exchange (CIRCE) process, offers the best prospect for commercialization. SMRs are common globally in the oil-upgrading and ammonia industries. To study the CIRCE process in detail, AECL, in collaboration with Air Liquide Canada, constructed a prototype CIRCE plant (PCP) in Hamilton, Ontario. The plant became fully operational in 2000 July and is expected to operate to at least late fall of 2002. To-date, plant operation has confirmed the adequacy of the design and the capability of enriching deuterium to produce heavy water without compromising hydrogen production. The proprietary wetproofed catalyst has performed as expected, both in activity and in robustness. (author)

List of publications 1994 January - 1995 December

International Nuclear Information System (INIS)

Lim, M.J.; Dament, M.; Barrie, B.

1996-07-01

AECL's mandate is to undertake research into nuclear energy and from that develop commercial applications. Its objective is to secure the maximum economic benefit for Canada from CANDU technology and the associated research and development. Among our most important products are scientific reports, publications and conference presentations. This document fists our publications for 1994-95. (author)

Safe and secure: transportation of radioactive materials

International Nuclear Information System (INIS)

Howe, D.

2015-01-01

Western Waste Management Facility is Central Transportation Facility for Low and Intermediate waste materials. Transportation support for Stations: Reactor inspection tools and heavy water between stations and reactor components and single bundles of irradiated fuel to AECL-Chalk River for examination. Safety Track Record: 3.2 million kilometres safely travelled and no transportation accident - resulting in a radioactive release.

Proceedings of the international conference on nuclear structure at high angular momentum and the workshop on large gamma-ray detector arrays. Conference summaries

Energy Technology Data Exchange (ETDEWEB)

NONE

1992-05-01

The proceedings of the conference/workshop is being published in two volumes. Abstracts of all contributed papers are contained in volume 1. The final proceedings will be published as volume 2 under the same report number (AECL--10613), and will contain expanded versions of abstracts submitted by registered participants together with the invited and contributed talks.

Detection of defects in logs using computer assisted tomography (CAT) scanning

International Nuclear Information System (INIS)

Tonner, P.D.; Lupton, L.R.

1985-01-01

The Chalk River Nuclear Laboratories of AECL have performed a preliminary feasibility study on the applicability of computer assisted tomographic techniques to detect the internal structure of logs. Cross sections of three logs have been obtained using a medical CAT scanner. The results show that knots, rot and growth rings are easily recognized in both dry and wet logs

Computer-aided engineering for Qinshan CANDU projects

International Nuclear Information System (INIS)

Huang Zhizhang; Goland, D.

1999-01-01

The author briefly describes AECL's work in applying computer-aided engineering tools to the Qinshan CANDU Project. The main emphases will be to introduce the major CADD software tools and their use in civil design, process design and EI and C design. Other special software tools and non-CADD tools and their applications are also briefly introduced

Third international conference on CANDU fuel

International Nuclear Information System (INIS)

Boczar, Peter

1992-01-01

These proceedings contain full texts of all 49 papers from the ten sessions and the banquet address. The sessions were on the following subjects: International experience and programs; Fuel behaviour and operating experience; Fuel modelling; Fuel design; Advanced fuel and fuel cycle technology; AECL's concept for the disposal of nuclear fuel waste. The individual papers have been abstracted separately

Proceedings of the international conference on nuclear structure at high angular momentum and the workshop on large gamma-ray detector arrays. Conference summaries

International Nuclear Information System (INIS)

1992-05-01

The proceedings of the conference/workshop is being published in two volumes. Abstracts of all contributed papers are contained in volume 1. The final proceedings will be published as volume 2 under the same report number (AECL--10613), and will contain expanded versions of abstracts submitted by registered participants together with the invited and contributed talks

Annual report, 1978-79

International Nuclear Information System (INIS)

1979-01-01

Activities of AECL for the year ending March 31, 1979 are described. Progress in research, production and marketing of radioisotopes, heavy water manufacture, and construction of CANDU reactors is discussed. The company was restructured in 1978. Hearings on nuclear issues meant that more attention was paid to public affairs. A financial statement is included. (L.L.)

Successful completion of the Qinshan phase III nuclear power plant-a successful model for Chinese-Canadian cooperation

International Nuclear Information System (INIS)

Peng Xiaoxing

2004-01-01

This report documents Qinshan CANDU project construction and commissioning experience as well as management strategies and approaches that contributed to the successful completion of the project. The Qinshan phase III (CANDU) nuclear power plant was built in record times: Unit 1 achieved commercial operation on December 31, 2002 and Unit 2 on July 24, 2003, 43 days and 112 days ahead of schedule respectively. The reference plant design is the Wolsong 3 and 4 CANDU-6 units in the Republic of Korea. Improvements in design and construction methods allowed Unit 1 to be constructed in 51.5 Months from First Concrete to Criticality-a record in China for nuclear power plants. The key factors are project management and project management tools, quality assurance, construction methods (including open top construction, heavy lifts and modularization), electronic documentation with configuration control that provides up-to-date on-line information, CADDS design linked with material management, specialized material control including bar coding, and planning. The introduction of new design and construction techniques was achieved by combining conventional AECL practices with working experiences in China. The most advanced tools and techniques for achieving optimum construction quality, schedule and cost were used. Successful application of advanced project management methods and tools will benefit TQNPC in operation of the station, and the Chinese contractors in advancing their capabilities in future nuclear projects in China and enhancing their opportunities internationally. TQNPC's participation in Quality surveillance (QS) activities of nuclear steam plant (NSP) and Balance of Plant (BOP) offshore equipment benefited TQNPC in acquiring knowledge of specific equipment manufacturing processes, which can be applied to similar activities in China. China has established the capability of manufacturing CANDU fuel and becoming self-reliant in fuel supply. Excellent co-operation and

Application of up-front licensing

Energy Technology Data Exchange (ETDEWEB)

Grant, S D [Atomic Energy of Canada Ltd., Saskatoon, SK (Canada); Snell, V G [Atomic Energy of Canada Ltd., Mississauga, ON (Canada)

1996-12-31

AECL has been pioneering `up-front` licensing of new reactor designs. The CANDU 3 design has been formally reviewed by AECB staff for a number of years. The CANDU 9 design has just started the up-front licensing process. The process gives designers, regulators and potential customers early confidence in the licensability of future plants. (author). 4 refs., 2 tabs.

Atomic Energy of Canada Limited, annual report, 1995-1996

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-12-31

The 1996 Annual Report of Atomic Energy of Canada Ltd. (AECL) is published and submitted to the Honourable member of Parliament, Minister of Natural Resources. Included in this report are messages from Marketing and Commercial Operation, Product Development, i e.CANDU and Research Reactors, CANDU research, Waste Management, Environmental Management, Financial Review and also included are copies of the financial statements.

Atomic Energy of Canada Limited, annual report, 1995-1996

International Nuclear Information System (INIS)

1996-01-01

The 1996 Annual Report of Atomic Energy of Canada Ltd. (AECL) is published and submitted to the Honourable member of Parliament, Minister of Natural Resources. Included in this report are messages from Marketing and Commercial Operation, Product Development, i e.CANDU and Research Reactors, CANDU research, Waste Management, Environmental Management, Financial Review and also included are copies of the financial statements

List of publications 1990

International Nuclear Information System (INIS)

1991-06-01

AECL Research is engaged in research and development related to the peaceful applications of nuclear energy. Specifically, the company's mission is to perform the research, development, demonstration and marketing required to apply nuclear sciences and their related technologies for the maximum benefit of Canada. Among our most important products are scientific reports, publications and conference presentations. This document lists our publications for 1990

Application of up-front licensing

International Nuclear Information System (INIS)

Grant, S.D.; Snell, V.G.

1995-01-01

AECL has been pioneering 'up-front' licensing of new reactor designs. The CANDU 3 design has been formally reviewed by AECB staff for a number of years. The CANDU 9 design has just started the up-front licensing process. The process gives designers, regulators and potential customers early confidence in the licensability of future plants. (author). 4 refs., 2 tabs

List of publications 1991 January-December

International Nuclear Information System (INIS)

1992-02-01

AECL Research is engaged in research and development related to the peaceful applications of nuclear energy. Specifically, the company's mission is to perform the research, development, demonstration and marketing required to apply nuclear sciences and their related technologies for the maximum benefit of Canada. Among our most important products are scientific reports, publications and conference presentations. This document lists our publications for 1991

Removing fuelling transient using neutron absorbers

Energy Technology Data Exchange (ETDEWEB)

Paquette, S.; Chan, P.K.; Bonin, H.W., E-mail: Stephane.Paquette@rmc.ca [Royal Military College of Canada, Chemistry and Chemical Engineering Dept., Kingston, Ontario (Canada); Pant, A. [Cameco Fuel Manufacturing, Port Hope, Ontario (Canada)

2012-07-01

Preliminary criticality and burnup calculation results indicate that by employing a small amount of neutron absorber the fuelling transient, currently occurring in a CANDU 37-element fuel bundle, can be significantly reduced. A parametric study using the Los Alamos National Laboratories' MCNP 5 code and Atomic Energy of Canada Limited's WIMS-AECL 3.1 is presented in this paper. (author)

List of publications, 1989 January - December

International Nuclear Information System (INIS)

1990-02-01

This list includes all the scientific and technical publications of Atomic Energy of Canada Limited. This includes both technical reports and reprints of journal articles and conference proceedings issued from 1989 January to 1989 December. The titles and other bibliographic information are arranged in several categories, each devoted to a broad subject area. In addition, each document is identified with an AECL number

Radioactive waste repository study

International Nuclear Information System (INIS)

1978-11-01

This is the second part of a report of a preliminary study for AECL. It considers the requirements for an underground waste repository for the disposal of wastes produced by the Canadian Nuclear Fuel Program. The following topics are discussed with reference to the repository: 1) geotechnical assessment, 2) hydrogeology and waste containment, 3) thermal loading and 4) rock mechanics. (author)

Steam generators: critical components in nuclear steam supply systems

Energy Technology Data Exchange (ETDEWEB)

Stevens-Guille, P D

1974-02-28

Steam generators are critical components in power reactors. Even small internal leaks result in costly shutdowns for repair. Surveys show that leaks have affected one half of all water-cooled reactors in the world with steam generators. CANDU reactors have demonstrated the highest reliability. However, AECL is actively evolving new technology in design, manufacture, inspection and operation to maintain reliability. (auth)

3D CAD ON Qinshan CANDU project

International Nuclear Information System (INIS)

Goland, D.

2000-01-01

This paper briefly describe AECL's work in applying computer-aided engineering tools to the Qinshan CANDU project. The main thrust of this paper is to introduce the major CAD software tools and their use in civil design, process design and EI and C design. Other special software tools and non-CAD tools and their applications are also briefly introduced. (author)

An approach to neutronics analysis of candu reactors

International Nuclear Information System (INIS)

Gul, S.; Arshad, M.

1982-12-01

An attempt is made to tackle the problem of neutronics analysis of CANDU reactors. Until now CANDU reactors have been analysed by the methods developed at AECL and CGE using mainly receipe methods. Relying on multigroup transport codes GAM-GATHER in combination with diffusion code CITATION a package of codes is established to use it for survey as well as production purposes. (authors)

CADDS [Computer-aided Drafting and Design System] brings quality and precision to the Canadian Maple [research reactor

International Nuclear Information System (INIS)

Goland, D.

1989-01-01

Atomic Energy of Canada Ltd (AECL) has found that using the ''intelligent'' Computer-Aided Drafting and Design System (CADDS) helped address design problems at an early stage and led to productivity gains of around 50 per cent. Other bonuses were the quality and precision of the designs and documents produced. Its application to the MAPLE research reactor project is described. (author)

Progress report - Physical and Environmental Sciences - Physics Division. 1994 January 1 to December 31

International Nuclear Information System (INIS)

Harvey, M.

1995-09-01

This report marks the change from biannual to annual reports recording technical developments in Physics Division. During this period, AECL has continued with its restructuring program, with Physics Division now included in an expanded Physical and Environmental Sciences Unit. The Division itself remains unchanged, with major activities on neutron scattering, the Sudbury Neutrino Observatory and developments and applications of accelerator technology. (author)

Progress report - Physical and Environmental Sciences - Physics Division. 1994 January 1 to December 31

Energy Technology Data Exchange (ETDEWEB)

Harvey, M [ed.

1995-09-01

This report marks the change from biannual to annual reports recording technical developments in Physics Division. During this period, AECL has continued with its restructuring program, with Physics Division now included in an expanded Physical and Environmental Sciences Unit. The Division itself remains unchanged, with major activities on neutron scattering, the Sudbury Neutrino Observatory and developments and applications of accelerator technology. (author).

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

CFFTP journal volume 8 no. 2

International Nuclear Information System (INIS)

Macphee, R.

1991-12-01

A short journal article from Canadian Fusion Fuels Technology Project (CFFTP) highlighting the AECL Tritium Laboratory expansion, the advanced tritium course and the fluid seminar for industry. The research and development news on breeder blanket design and compact toroid fuelling gun and educational program news on CFFTP fusion fellowship awards, fusion seminars at McMaster University and the CFFTP student awards program

Performance characterization of hydrogen isotope exchange and recombination catalysts for tritium processing

International Nuclear Information System (INIS)

Suppiah, S.; Ryland, D.; Marcinkowska, K.; Boniface, H.; Everatt, A.

2010-01-01

AECL's hydrogen isotope exchange catalyst and recombination catalysts have been successfully applied to a wide range of industrial tritium-removal applications. The catalysts are used for Liquid Phase Catalytic Exchange (LPCE) and for gas-phase and trickle-bed recombination of hydrogen isotopes and have led to process simplification, improved safety and operational advantages. Catalyst performance design equations derived from laboratory testing of these catalysts have been validated against performance under industrial conditions. In a Combined Electrolysis and Catalytic Exchange (CECE) demonstration plant analyses of LPCE and recombiner efficiency were carried out as a function of catalyst activity over a wide range of operation. A steady-state process simulation used to model and design the hydrogen-water isotopic exchange processes, such as the CECE detritiation plant, was validated using the results of this demonstration. Catalyst development for isotope-exchange and recombination applications has continued over the last decade. As a result, significant improvements in catalyst performance have been achieved for these applications. This paper outlines the uniqueness of AECL's specialized catalysts and process designs for these applications with examples from laboratory and industrial case studies.

Fabrication of a CANFLEX-RU designed bundle for power ramp irradiation test in NRU

Energy Technology Data Exchange (ETDEWEB)

Cho, Moon Sung

2000-11-01

The BDL-443 CANFLEX-RU bundle AKW was fabricated at Korea Atomic Energy Research Institute (KAERI) for power ramp irradiation testing in NRU reactor. The bundle was fabricated with IDR and ADU fuel pellets in adjacent elements and contains fuel pellets enriched to 1.65 wt% {sup 235}U in the outer and intermediate rings and also contains pellets enriched to 2.00 wt% {sup 235}U in the inner ring. This bundle does not have a center element to allow for insertion on a hanger bar. KAERI produced the IDR pellets with the IDR-source UO{sub 2} powder supplied by BNFL. ADU pellets were fabricated and supplied by AECL. Bundle kits (Zircaloy-4 end plates, end plugs, and sheaths with brazed appendages) manufactured at KAERI earlier in 1996 were used for the fabrication of the bundle. The CANFLEX bundle was fabricated successfully at KAERI according to the QA provisions specified in references and as per relevant KAERI drawings and technical specification. This report covers the fabrication activities performed at KAERI. Fabrication processes performed at AECL will be documented in a separate report.

Post-irradiation examination of prototype Al-64 wt% U{sub 3}Si{sub 2} fuel rods from NRU

Energy Technology Data Exchange (ETDEWEB)

Sears, D.F.; Primeau, M.F.; Buchanan, C.; Rose, D. [Chalk River Labs., Ontario (Canada)

1997-08-01

Three prototype fuel rods containing Al-64 wt% U{sub 3}Si{sub 2} (3.15 gU/cm{sup 3}) have been irradiated to their design burnup in the NRU reactor without incident. The fuel was fabricated using production-scale equipment and processes previously developed for Al-U{sub 3}Si fuel fabrication at Chalk River Laboratories, and special equipment developed for U{sub 3}Si{sub 2} powder production and handling. The rods were irradiated in NRU up to 87 at% U-235 burnup under typical driver fuel conditions; i.e., nominal coolant inlet temperature 37{degrees}C, inlet pressure 654 kPa, mass flow 12.4 L/s, and element linear power ratings up to 73 kW/m. Post-irradiation examinations showed that the fuel elements survived the irradiation without defects. Fuel core diametral increases and volumetric swelling were significantly lower than that of Al-61 wt% U{sub 3}Si fuel irradiated under similar conditions. This irradiation demonstrated that the fabrication techniques are adequate for full-scale fuel manufacture, and qualified the fuel for use in AECL`s research reactors.

Features, events, processes, and safety factor analysis applied to a near-surface low-level radioactive waste disposal facility

Energy Technology Data Exchange (ETDEWEB)

Stephens, M.E.; Dolinar, G.M.; Lange, B.A. [Atomic Energy of Canada Limited, Ontario (Canada)] [and others

1995-12-31

An analysis of features, events, processes (FEPs) and other safety factors was applied to AECL`s proposed IRUS (Intrusion Resistant Underground Structure) near-surface LLRW disposal facility. The FEP analysis process which had been developed for and applied to high-level and transuranic disposal concepts was adapted for application to a low-level facility for which significant efforts in developing a safety case had already been made. The starting point for this process was a series of meetings of the project team to identify and briefly describe FEPs or safety factors which they thought should be considered. At this early stage participants were specifically asked not to screen ideas. This initial list was supplemented by selecting FEPs documented in other programs and comments received from an initial regulatory review. The entire list was then sorted by topic and common issues were grouped, and issues were classified in three priority categories and assigned to individuals for resolution. In this paper, the issue identification and resolution process will be described, from the initial description of an issue to its resolution and inclusion in the various levels of the safety case documentation.

MAAP4 CANDU analysis of a generic CANDU-6 plant: preliminary results

Energy Technology Data Exchange (ETDEWEB)

Petoukhov, S.M.; Mathew, P.M

2001-10-01

To support the generic probabilistic safety analysis (PSA) program at AECL, in particular to conduct Level 2 PSA analysis of a CANDU 6 plant undergoing a postulated severe accident, the capability to conduct severe accident consequence analysis for a CANDU plant is required. For this purpose, AECL selected MAAP4 CANDU from a number of other severe accident codes. The necessary models for a generic CANDU 6 station have been implemented in the code, and the code version 0.2 beta was tested using station data, which were assembled for a generic CANDU 6 station. This paper describes the preliminary results of the consequence analysis using MAAP4 CANDU for a generic CANDU 6 station, when it undergoes a station blackout and a large loss-of-coolant accident scenario. The analysis results show that the plant response is consistent with the physical phenomena modeled and the failure criteria used. The results also confirm that the CANDU design is robust with respect to severe accidents, which is reflected in the calculated long times that are available for administering accident management measures to arrest the accident progression before the calandria vessel or containment become at risk. (author)

Canadian fuel development program and recent operational experience

International Nuclear Information System (INIS)

Cox, D.S.; Kohn, E.; Lau, J.H.K.; Dicke, G.J.; Macici, N.N.; Sancton, R.W.

1995-01-01

This paper provides an overview of the current Canadian CANDU fuel R and D programs and operational experience. The details of operational experience for fuel in Canadian reactors are summarized for the period 1991-1994; excellent fuel performance has been sustained, with steady-state bundle defect rates currently as low as 0.02%. The status of introducing long 37-element bundles, and bundles with rounded bearing pads is reviewed. These minor changes in fuel design have been selectively introduced in response to operational constraints (end-plate cracking and pressure-tube fretting) at Ontario Hydro's Bruce-B and Darlington stations. The R and D programs are generating a more complete understanding of CANDU fuel behaviour, while the CANDU Owners Group (COG) Fuel Technology Program is being re-aligned to a more exclusive focus on the needs of operating stations. Technical highlights and realized benefits from the COG program are summarized. Re-organization of AECL to provide a one-company focus, with an outward looking view to new CANDU markets, has strengthened R and D in advanced fuel cycles. Progress in AECL's key fuel cycle programs is also summarized. (author)

Input modelling of ASSERT-PV V2R8M1 for RUFIC fuel bundle

Energy Technology Data Exchange (ETDEWEB)

Park, Joo Hwan; Suk, Ho Chun

2001-02-01

This report describes the input modelling for subchannel analysis of CANFLEX-RU (RUFIC) fuel bundle which has been developed for an advanced fuel bundle of CANDU-6 reactor, using ASSERT-PV V2R8M1 code. Execution file of ASSERT-PV V2R8M1 code was recently transferred from AECL under JRDC agreement between KAERI and AECL. SSERT-PV V2R8M1 which is quite different from COBRA-IV-i code has been developed for thermalhydraulic analysis of CANDU-6 fuel channel by subchannel analysis method and updated so that 43-element CANDU fuel geometry can be applied. Hence, ASSERT code can be applied to the subchannel analysis of RUFIC fuel bundle. The present report was prepared for ASSERT input modelling of RUFIC fuel bundle. Since the ASSERT results highly depend on user's input modelling, the calculation results may be quite different among the user's input models. The objective of the present report is the preparation of detail description of the background information for input data and gives credibility of the calculation results.

Technical report on implementation of reactor internal 3D modeling and visual database system

Energy Technology Data Exchange (ETDEWEB)

Kim, Yeun Seung; Eom, Young Sam; Lee, Suk Hee; Ryu, Seung Hyun [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1996-06-01

In this report was described a prototype of reactor internal 3D modeling and VDB system for NSSS design quality improvement. For improving NSSS design quality several cases of the nuclear developed nation`s integrated computer aided engineering system, such as Mitsubishi`s NUWINGS (Japan), AECL`s CANDID (Canada) and Duke Power`s PASCE (USA) were studied. On the basis of these studies the strategy for NSSS design improvement system was extracted and detail work scope was implemented as follows : 3D modelling of the reactor internals were implemented by using the parametric solid modeler, a prototype system of design document computerization and database was suggested, and walk-through simulation integrated with 3D modeling and VDB was accomplished. Major effects of NSSS design quality improvement system by using 3D modeling and VDB are the plant design optimization by simulation, improving the reliability through the single design database system and engineering cost reduction by improving productivity and efficiency. For applying the VDB to full scope of NSSS system design, 3D modelings of reactor coolant system and nuclear fuel assembly and fuel rod were attached as appendix. 2 tabs., 31 figs., 7 refs. (Author) .new.

Radionuclide migration in groundwater at a low-level waste disposal site: a comparison of predictive performance modeling versus field observations

International Nuclear Information System (INIS)

Robertson, D.E.; Myers, D.A.; Bergeron, M.P.; Champ, D.R.; Killey, R.W.D.; Moltyaner, G.L.; Young, J.L.

1985-08-01

This paper describes a project which is structured to test the concept of modeling a shallow land low-level waste burial site. The project involves a comparison of the actual observed radionuclide migration in groundwaters at a 30-year-old well-monitored field site with the results of predictive transport modeling. The comparison is being conducted as a cooperative program with the Atomic Energy of Canada Ltd. (AECL) at the low-level waste management area at the Chalk River Nuclear Laboratories, Ontario, Canada. A joint PNL-AECL field inviestigation was conducted in 1983 and 1984 to complement the existing extensive data base on actual radionuclide migration. Predictive transport modeling is currently being conducted for this site; first, as if it were a new location being considered for a low-level waste shallow-land burial site and only minimal information about the site were available, and second, utilizing the extensive data base available for the site. The modeling results will then be compared with the empirical observations to provide insight into the level of effort needed to reasonably predict the spacial and temporal movement of radionuclides in the groundwater enviroment. 8 refs., 5 figs.,

Geological disposal concept hearings

International Nuclear Information System (INIS)

1996-01-01

The article outlines the progress to date on AECL spent-nuclear fuel geological disposal concept. Hearings for discussion, organised by the federal Environmental Assessment Review Panel, of issues related to this type of disposal method occur in three phases, phase I focuses on broad societal issues related to long term management of nuclear fuel waste; phase II will focus on the technical aspects of this method of disposal; and phase III will consist of community visits in New Brunswick, Quebec, Ontario, Manitoba and Saskatchewan. This article provides the events surrounding the first two weeks of phase I hearings (extracted from UNECAN NEWS). In the first week of hearings, where submissions on general societal issues was the focus, there were 50 presentations including those by Natural Resources Canada, Energy Probe, Ontario Hydro, AECL, Canadian Nuclear Society, Aboriginal groups, environmental activist organizations (Northwatch, Saskatchewan Environmental Society, the Inter-Church Uranium Committee, and the Canadian Coalition for Nuclear responsibility). In the second week of hearings there was 33 presentations in which issues related to siting and implementation of a disposal facility was the focus. Phase II hearings dates are June 10-14, 17-21 and 27-28 in Toronto

Experience gained in the production of licensable safety-critical software for Darlington NGS

International Nuclear Information System (INIS)

Crane, R.H.

1992-01-01

The Darlington Nuclear Generating Station is a new station, consisting of four 935 Mw units, built by Ontario Hydro, on the north shore of Lake Ontario, approximately 50 miles east of Toronto. In May, 1987, the first of the four units of this station was approaching the point where Ontario Hydro would be requesting a license to load fuel, and then proceed to first criticality. At this point, however, the regulatory authority, the Atomic Energy Control Board (AECB) started to show increasing concerns related to the Trip Computer Software associated with Darlington's newly-designed computerized shutdown systems. The concerns centered around whether or not the safety reliability, reviewability, and maintainability of this software could be demonstrated by Ontario Hydro or the system designer, Atomic Energy of Canada Limited (AECL). In order to back up the validity of their concerns, they hired a well-known consultant, who reviewed the code, and made recommendations concerning its design, implementation, and documentation. Considerable effort was required by Ontario Hydro and AECL in order to comply with those recommendations. This paper describes those efforts, outlines the difficulties encountered, and assesses the lessons learned from them

Advanced air detritiation dryer

International Nuclear Information System (INIS)

Anon.

1989-01-01

The isotopic exchange principle has proved effective in increasing air detritiation factors of atmospheric dryers. A CFFTP/AECL Chalk River program has demonstrated detritiation factors of 100,000 in trials. The technology is designed for application on regenerating atmospheric dryers using molecular sieve desiccant beds, used in rooms likely to encounter airborne tritium contamination. Dryer design concepts for dryers at JET (Joint European Torus, England) and ITER have been prepared by Alan Dombra of AECL, using the isotopic exchange technology. The isotopic exchange method works by passing tritiated air over a detritiated desiccant bed. Airborne tritium atoms are exchanged in the bed for ordinary hydrogen atoms from the bed's residual moisture loading. Tritium remains on the bed until it is discharged in a regeneration cycle. During regeneration, the desiccant bed is first heated with hot, dry air to drive off collected tritiated moisture. Airborne tritium removed from the air is collected as a tritiated water distillate and stored for later processing. During the second part of the regeneration cycle, the desiccant bed is washed with clean moist air to elute remaining traces of tritium and to refresh the bed to ready it for another tritium absorption period

Technical summary of AECL's Mine-by Experiment phase I: Excavation response

International Nuclear Information System (INIS)

Read, R.S.; Martin, C.D.

1996-02-01

The first phase of the Mine-by Experiment was conducted at the 420 Level of the Underground Research Laboratory (URL) to investigate the response induced in the rock mass by excavating a 3.5-m-diameter circular tunnel using a non-explosive technique. The main objective of the experiment was to study the processes involved in progressive failure and the development of excavation-induced damage around underground openings. To this end, state-of-the-art geomechanical and geophysical instrumentation was used to monitor the excavation of the 46-m-long Mine-by Experiment test tunnel. The results from the experiment show that progressive failure in compressive regions around the tunnel initiates at stresses about 50% of the rock strength measured in uniaxial compression tests in the laboratory. The difference between the laboratory and in situ behaviour is attributed to complex stress changes that occur during excavation of the tunnel, especially in the vicinity of the advancing face. These effects are not simulated in standard laboratory tests. Numerical modelling and in situ characterization studies were conducted to establish the extent and characteristics of the damaged zone around the test tunnel. As part of this study, in situ stresses and material properties were established through back analysis of measured displacements and strains. Using these boundary conditions, it was shown that the damaged zone was limited to within 1 m of the original tunnel perimeter. The characteristics of the damaged zone, however, were found to be highly variable around the tunnel, and were dependent on the nature of the stress concentrations, geology, stress magnitudes and orientations and, to a lesser extent, the excavation method and sequence. (author) 136 refs., 14 tabs., 103 figs

Nuclear research centres in the 21st century: An AECL perspective

International Nuclear Information System (INIS)

Fehrenbach, P.J.

2001-01-01

The nuclear energy programme of Canada started at Chalk River Laboratories with the setting up of Zero Energy Experimental Site in 1945. One of the early research reactors of Canada, the National Research Universal (NRU) continues to provide 70% of the world requirement of isotopes for medical and industrial applications. A CANDU prototype (208 MW(e)) came on line in 1967 and based on this concept, Canada has a large nuclear power programme. The role of nuclear research centres has evolved with time starting with strategic research in the initial phases through to implementation of technology, building and supporting industry, and carrying out advanced technology development. Most of these centres have important assets in terms of licensed sites, trained personnel, research reactors, shielded facilities and expertise for handling large quantities of radioactivity and high tech laboratories for advanced R and D. These centres would, therefore, continue to play an important role in emission free and economic energy generation, nuclear medicine, food irradiation and industrial applications. Nuclear research centres in different countries are at various stages of development and have many unique features. However, there are generic issues and much will be gained by developing a shared vision for the future and implementing programmes in a collaborative manner. (author)

Year in review 1994

International Nuclear Information System (INIS)

Richman, J.

1995-01-01

The past year saw a basic restructuring and reorganization of operations at AECL and at the CNA. Ontario Hydro saw a record electricity export sales. The CANDU units continue to rank among the world leaders in lifetime reliability. The sale of two CANDU 6 reactors to China is under negotiation after the signing of a bilateral Nuclear Cooperation Agreement between China and Canada. 1 tab., 2 figs

Verification of the thermal module in the ELESIM code and the associated uncertainty analysis

International Nuclear Information System (INIS)

Arimescu, V.I.; Williams, A.F.; Klein, M.E.; Richmond, W.R.; Couture, M.

1997-01-01

Temperature is a critical parameter in fuel modelling because most of the physical processes that occur in fuel elements during irradiation are thermally activated. The focus of this paper is the temperature distribution calculation used in the computer code ELESIM, developed at AECL to model the steady state behaviour of CANDU fuel. A validation procedure for fuel codes is described and applied to ELESIM's thermal calculation

SLOWPOKE

International Nuclear Information System (INIS)

Law, Charles.

1979-01-01

The SLOWPOKE (Safe Low Power Critical Experiment) reactor was developed by AECL at Whiteshell and Chalk River between 1968 and 1970. It is a neutron-producing reactor of low power with minimal fuel, shielding, and cooling requirements and intrinsic safety. Four Canadian universities and one German one have acquired SLOWPOKE reactors for neutron activation analyses and for student research in nuclear engineering and reactor physics. (LL)

List of publications 1993 January - December

International Nuclear Information System (INIS)

1994-04-01

AECL research is engaged in research and development related to the peaceful applications of nuclear energy. Specifically, the company's mission is to perform the research, development, demonstration and marketing required to apply nuclear sciences and their related technologies for the maximum benefit of Canada. Among our most important products are scientific reports, publications and conference presentations. This document lists our publications for 1993. (author)

Topics in industrial mathematics

International Nuclear Information System (INIS)

Vatsya, S.R.

1992-01-01

Mathematical methods are widely used to solve practical problems arising in modern industry. This article outlines some of the topics relevant to AECL programmes. This covers the applications of transmission and neutron transport tomography to determine density distributions in rocks and two phase flow situations. Another example covered is the use of variational methods to solve the problems of aerosol migration and control theory. (author). 7 refs

List of publications. 1992 January - December

International Nuclear Information System (INIS)

1993-04-01

AECL Research is engaged in research and development related to the peaceful applications of nuclear energy. Specifically, the company's mission is to perform the research, development, demonstration and marketing required to apply nuclear sciences and their related technologies for the maximum benefit of Canada. Among our most important products are scientific reports, publications and conference presentations. This document lists our publications for 1992. (author)

List of publications. 1992 January - December

Energy Technology Data Exchange (ETDEWEB)

NONE

1993-04-01

AECL Research is engaged in research and development related to the peaceful applications of nuclear energy. Specifically, the company`s mission is to perform the research, development, demonstration and marketing required to apply nuclear sciences and their related technologies for the maximum benefit of Canada. Among our most important products are scientific reports, publications and conference presentations. This document lists our publications for 1992. (author).

List of publications 1993 January - December

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-04-01

AECL research is engaged in research and development related to the peaceful applications of nuclear energy. Specifically, the company`s mission is to perform the research, development, demonstration and marketing required to apply nuclear sciences and their related technologies for the maximum benefit of Canada. Among our most important products are scientific reports, publications and conference presentations. This document lists our publications for 1993. (author).

An assessment of prediction methods of CHF in tubes with a large experimental data bank

International Nuclear Information System (INIS)

Leung, L.K.H.; Groeneveld, D.C.

1993-01-01

An assessment of prediction methods of CHF in tubes has been carried out using an expanded CHF data bank at Chalk River Laboratories (CRL). It includes eight different CHF look-up tables (two AECL versions and six USSR (or Russian) versions) and three empirical correlations. These prediction methods were developed from relatively large data bases and therefore have a wide range of application. Some limitations, however, were imposed in this study, to avoid any invalid predictions due to extrapolation of these methods. Therefore, these comparisons are limited to the specific data base that is tailored to suit the range of an individual method. This has resulted in a different number of data used in each case. The comparison of predictions against the experimental data is based on the constant inlet-condition approach (i.e., the pressure, mass flux, inlet fluid temperature and tube geometry are the primary parameters). Overall, the AECL tables have the widest range of application. They are assessed with 21 771 data points and the root-mean-square error is only 8.3%. About 60% of these data were used in the development of the AECL tables. The best version of the USSR/Russian CHF table is valid for 13 300 data points with a root-mean-square error of 8.8%. The USSR/Russian table that has the widest range of application covers a total of 18 800 data points, but the error increases to 9.3%. The range of application for empirical correlations, however, are generally much narrower than those covered by the CHF tables. The number of data used to assess these correlations is therefore further limited. Among the tested correlations, the Becker and Persson correlation covers the least amount of data (only 7 499 data points), but has the best accuracy (with a root-mean-square error of 9.71%). 33 refs., 2 figs., 3 tabs

Economic viability of Cernavoda project

International Nuclear Information System (INIS)

Condu, M.; Popescu, D.; Chirica, T.; Glodeanu, F.

1998-01-01

Cernavoda project started in 1978, when the CANDU technology procurement contract and other contracts for engineering, technical assistance and procurement were signed with AECL. The works on site started in 1980. In February 1981, a contract was signed with GE - USA and Ansaldo - Italy for balance of plant. After 1989 the concept for project implementation was essentially changed. The completion of Cernavoda NPP Unit-1, established as the first priority by Romanian authorities was implemented by AECL-Ansaldo Consortium (AAC). The objective of the contract signed with AAC consisted in overtaking the management of Cernavoda Unit-1 project, in order to complete, commission and operate the plant for 18 months. The plant was successfully completed, commissioned and commercially operated since December 2, 1996. As concerns Unit-2, only preservation and some remedial works were performed since 1991. In order to support the decision to complete Unit-2, a complete process was initiated: - identification of the activities and associated costs required for plan completion; - plant integration in the utility's least cost development study; - Unit-2 cash flow analysis. A joint RENEL-AECL-ANSALDO team performed a detailed analysis using Cernavoda Unit-1 as reference project and taking advantage of the experience gained during construction, commissioning and operation of the first unit. The least cost power generation development study finalized by SEP and EDF, based on a PHARE funding, ranked Cernavoda Unit-2 on the second place, after two small hydroelectric plants of 53 and 8 Mw e. A cash flow model developed by a RENEL-ANSALDO joint team shows that Cernavoda Unit-2 is an economically feasible project. The financing scenario provides that all resources will be from loans. Other arguments for completion of Cernavoda Unit-2 are: - good performances in operation of Unit-1; - the need to provide jobs for the specialists in the nuclear field; - opportunity for electricity export

Validation of physics and thermalhydraulic computer codes for advanced Candu reactor applications

International Nuclear Information System (INIS)

Wren, D.J.; Popov, N.; Snell, V.G.

2004-01-01

Atomic Energy of Canada Ltd. (AECL) is developing an Advanced Candu Reactor (ACR) that is an evolutionary advancement of the currently operating Candu 6 reactors. The ACR is being designed to produce electrical power for a capital cost and at a unit-energy cost significantly less than that of the current reactor designs. The ACR retains the modular Candu concept of horizontal fuel channels surrounded by a heavy water moderator. However, ACR uses slightly enriched uranium fuel compared to the natural uranium used in Candu 6. This achieves the twin goals of improved economics (via large reductions in the heavy water moderator volume and replacement of the heavy water coolant with light water coolant) and improved safety. AECL has developed and implemented a software quality assurance program to ensure that its analytical, scientific and design computer codes meet the required standards for software used in safety analyses. Since the basic design of the ACR is equivalent to that of the Candu 6, most of the key phenomena associated with the safety analyses of ACR are common, and the Candu industry standard tool-set of safety analysis codes can be applied to the analysis of the ACR. A systematic assessment of computer code applicability addressing the unique features of the ACR design was performed covering the important aspects of the computer code structure, models, constitutive correlations, and validation database. Arising from this assessment, limited additional requirements for code modifications and extensions to the validation databases have been identified. This paper provides an outline of the AECL software quality assurance program process for the validation of computer codes used to perform physics and thermal-hydraulics safety analyses of the ACR. It describes the additional validation work that has been identified for these codes and the planned, and ongoing, experimental programs to extend the code validation as required to address specific ACR design

NRU licence extension via integrated safety review

Energy Technology Data Exchange (ETDEWEB)

Mantifel, N. [Atomic Energy of Canada Limited, Chalk River, ON (Canada)

2014-07-01

The National Research Reactor, NRU at AECL Chalk River Laboratories achieved first criticality in November 1957. The completion of an Integrated Safety Review (ISR) in 2011, and subsequent Global Assessment Report (GAR), and Integrated Implementation Plan (IIP) has given confidence in the safe and reliable operation of NRU, therefore extending the licensing case to safely and reliably operate NRU until 2021 and beyond (64+ years of operation). The key vehicle to achieve this confidence is the IIP, that resulted from the ISR. NRU's IIP is a 10 year plan that addresses the gaps identified in the ISR between modern codes and standards in a prioritized approach. AECL is currently in year 3 of the IIP execution, is on or ahead of schedule to complete the identified improvements. The IIP in conjunction with a License Condition Handbook has replaced the licensing protocol with the Canadian Nuclear Safety Commission, (CNSC). Execution of the IIP to plan supports the continued safe operation of NRU. The ISR was carried out with the recognition that the NRU reactor is a research and isotope producing reactor approaching license renewal and not a power reactor undergoing refurbishment and life extension. Therefore, the IIP is being executed while NRU continues to deliver on its three missions: production of medical isotopes, support for fuels and materials research, and serving as a high flux neutron source in support of research relying on neutron scattering. The IIP is grouped into 5 Global Issue Groups, (GIGs) to support focused execution. The activities and tasks within the five GIGs are being executed via a matrix organization through the use of the Chalk River Laboratories Corrective Action Program to ensure the assignment of actions, completion and evidence to support closure is documented and retained. This paper discusses the approach taken by AECL to license and ensure safe, reliable operation of NRU until 2021 and beyond. (author)

Innovation to reality for improved pump seal performance

International Nuclear Information System (INIS)

Wong, W.; Eyvindson, A.; Rhodes, D.B.

2003-01-01

'Full-Text:' The nuclear industry requires reliable pump seals. Extended operating conditions for aging plants (i.e., low pressure starts, pressure and temperature transients) and increasing demands from new plants (larger sizes, higher speeds) are pushing the operating envelope for seals. This means that many seals that were previously considered adequate are now requiring increased attention and care. Operating utilities have taken different approaches to addressing their existing, or emerging, seal problems. Primary concerns include maintenance practices, seal design, and monitoring capabilities, as well as operating conditions, transients, pump and motor design. Success in this area requires ongoing dialogue among the station operators, pump manufacturers and seal designers. Regardless of the design, the basic requirement in CANDU is a reliable seal lifetime exceeding 5 years. This paper describes AECL's efforts to meet this requirement through an ongoing program of research and development in seal technology. Current work includes rigorous testing and evaluation of new seal materials and coatings to maximize seal stability and minimize friction and wear (i.e., pressure/temperature transients produce unpredictable shaft movement that can significantly alter face deflections affecting leak rates and seal stability, and sometimes cause the seal to hang-up and de-stage). Also required is a practical method for on-line monitoring of the condition of the seal, whether it is newly installed or after several years of reliable performance. This provides crucial information for inventory, maintenance and outage planning. While new concepts may look good on paper, it is only after they have been demonstrated under fully representative station operating conditions that they can truly be considered ready for field use. AECL CAN-seals lead the nuclear industry in reliability and seal life. They effectively save operators millions of dollars in outage time and person

Emergency core cooling strainers-the Candu experience

International Nuclear Information System (INIS)

Eyvindson, A.; Rhodes, D.; Carson, P.; Makdessi, G.

2004-01-01

The Canadian nuclear industry, including Atomic Energy of Canada Limited (AECL) and the four nuclear utilities (New Brunswick Power, Hydro-Quebec, Ontario Power Generation and Bruce Power) have been heavily involved in strainer clogging issues since the late 1990's. A substantial knowledge base has been obtained with support from various organisations, including the CANDU Owners Group (COG), AECL and the CANDU utilities. Work has included debris assessments at specific stations, debris characterisation, transport, head loss measurements across strainers, head loss models and investigations into paints and coatings. Much of this work was performed at AECL's Chalk River Laboratories and has been used to customize strainer solutions for several CANDU (PWR-type) stations. This paper summarises the CANDU experience, describing problems encountered and lessons learned from strainer implementation at stations. Between 1999 and 2003, AECL supplied strainers to six different CANDU stations, representing 12 units with a total power output of approximately 8.2 GWe. Each station had unique needs with respect to layout, effective area, allowable head loss and installation schedule. Challenges at various sites included installation in a covered trench with single-point access, allowing for field adjustments to accommodate large variations in floor level and pump suction location, on-power installation, very high levels of particulate relative to fibrous debris, and relatively low allowable head loss. The following are key points to consider during any station assessment or strainer implementation: - a realistic testing model and method is essential for accurate predictions of head loss, and the limits of the model must be understood; - assessment of station debris must be sufficiently conservative to overcome uncertainties in debris generation and transport models; - appropriate and reliable data (e.g. flow rate, layout, size of test model, method of debris generation and

Insights from the panel review process

International Nuclear Information System (INIS)

Searborn, B.

1998-01-01

The environmental review process for nuclear waste management and disposal was unusual in that the Panel was asked to examine a concept rather than a specific project at a specific site. The Panel was charged with commenting on the safety and acceptability of the AECL concept, examining criteria for determining the safety and acceptability of any concept for managing nuclear fuel waste, and examining future steps which should be taken. In short, it was asked to provide policy advice to governments. The Panel concluded that safety is a key part, but only one part, of acceptability, and that safety must be viewed from both a technical and a social perspective. It judged that safety of the AECL concept had been adequately demonstrated from a technical perspective, but not from a social perspective. It also concluded that the AECL concept does not have the required level of public acceptability to be adopted as Canada's approach for managing nuclear fuel wastes. The paper examines in some detail the various aspects of the public concerns surrounding the nuclear cycle in general, and the safety of the proposals put forward by AECL for nuclear fuel waste management in particular. It notes the differences between those who look at safety from a technical perspective, and those who look at safety from a social perspective. And it lists the concerns related to acceptability in addition to the key factor of safety. After outlining the Panel's recommendations to governments on future steps to be taken, the paper discusses the extent to which the recommendations respond to the public's concerns. It stresses the importance of Aboriginal participation; of the creation of a new agency to deal with the full range of activities, technical and social, related to long-term management; of the public and decision-makers having more than one viable option to choose from; and of the essentiality of an inter-active process of public participation at all stages of decision-making. Finally

Thermal-hydraulic interfacing code modules for CANDU reactors

Energy Technology Data Exchange (ETDEWEB)

Liu, W.S.; Gold, M.; Sills, H. [Ontario Hydro Nuclear, Toronto (Canada)] [and others

1997-07-01

The approach for CANDU reactor safety analysis in Ontario Hydro Nuclear (OHN) and Atomic Energy of Canada Limited (AECL) is presented. Reflecting the unique characteristics of CANDU reactors, the procedure of coupling the thermal-hydraulics, reactor physics and fuel channel/element codes in the safety analysis is described. The experience generated in the Canadian nuclear industry may be useful to other types of reactors in the areas of reactor safety analysis.

The new business model for nuclear

International Nuclear Information System (INIS)

Galange, D.

2006-01-01

New nuclear development will require new business models that ensure maximum risk mitigation for the plant owner and rate payers. To deliver this model, AECL has joined with leading members of the nuclear industry to form Team CANDU. This presentation will introduce contracting structures that have been used by Team CANDU members to reduce plant delivery risk in an ongoing record of successful project completions over the last decade. (author)

Optimization of the fuel assembly for the Canadian Supercritical Water-cooled Reactor (SCWR)

Energy Technology Data Exchange (ETDEWEB)

French, C.; Bonin, H.; Chan, P., E-mail: Corey.French@rmc.ca [Royal Military College of Canada, Dept. of Chemistry and Chemical Engineering, Kingston, Ontario (Canada)

2013-07-01

A parametric optimization of the Canadian Supercritical Water-cooled Reactor (SCWR) lattice geometry and fresh fuel content is performed in this work. With the potential to improve core physics and performance, significant gains to operating and safety margins could be achieved through slight progressions. The fuel performance codes WIMS-AECL and SERPENT are used to calculate performance factors, and use them as inputs to an optimization algorithm. (author)

CANDU plant life management - An integrated approach

International Nuclear Information System (INIS)

Hopkins, J.R.

1998-01-01

An integrated approach to plant life management has been developed for CANDU reactors. Strategies, methods, and procedures have been developed for assessment of critical systems structures and components and for implementing a reliability centred maintenance program. A Technology Watch program is being implemented to eliminate 'surprises'. Specific work has been identified for 1998. AECL is working on the integrated program with CANDU owners and seeks participation from other CANDU owners

Thermal-hydraulic interfacing code modules for CANDU reactors

International Nuclear Information System (INIS)

Liu, W.S.; Gold, M.; Sills, H.

1997-01-01

The approach for CANDU reactor safety analysis in Ontario Hydro Nuclear (OHN) and Atomic Energy of Canada Limited (AECL) is presented. Reflecting the unique characteristics of CANDU reactors, the procedure of coupling the thermal-hydraulics, reactor physics and fuel channel/element codes in the safety analysis is described. The experience generated in the Canadian nuclear industry may be useful to other types of reactors in the areas of reactor safety analysis

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.)

Extending the world's uranium resources through advanced CANDU fuel cycles

Energy Technology Data Exchange (ETDEWEB)

De Vuono, Tony; Yee, Frank; Aleyaseen, Val; Kuran, Sermet; Cottrell, Catherine

2010-09-15

The growing demand for nuclear power will encourage many countries to undertake initiatives to ensure a self-reliant fuel source supply. Uranium is currently the only fuel utilized in nuclear reactors. There are increasing concerns that primary uranium sources will not be enough to meet future needs. AECL has developed a fuel cycle vision that incorporates other sources of advanced fuels to be adaptable to its CANDU technology.

A review of the prospects for fusion breeding of fissile material

International Nuclear Information System (INIS)

Geiger, J.S.; Bartholomew, G.A.

1981-10-01

This report is the result of an eight month study by the AECL Fusion Status Study Group. The objectives of this study were to review the current status of fusion research, to evaluate the neutronic performance of various fusion-breeder systems, and to assess the economic and technological outlook for the fusion breeder as a source of fissile material to support CANDU reactors operating on the thorium fuel cycle

Material and fabrication considerations for the CANDU-PHWR heat transport system

International Nuclear Information System (INIS)

Filipovic, A.; Price, E.G.; Barber, D.; Nickerson, J.

1987-03-01

CANDU PHWR nuclear systems have used carbon steel material for over 25 years. The accumulated operating experience of over 200 reactor years has proven this unique AECL approach to be both technically and economically attractive. This paper discusses design, material and fabrication considerations for out-reactor heat transport system major components. The contribution of this unique choice of materials and equipment to the outstanding CANDU performance is briefly covered

Technologies for tritium control in fission reactors moderated with heavy water; Tecnologias para control de tritio en reactores de fision moderados con agua pesada

Energy Technology Data Exchange (ETDEWEB)

Ramilo, L B; Gomez de Soler, S M [Comision Nacional de Energia Atomica, San Martin (Argentina). Unidad de Actividad Reactores y Centrales Nucleares

1997-12-31

This study was done within a program one of whose objectives was to analyze the possible strategies and technologies, to be applied to HWR at Argentine nuclear power plants, for tritium control. The high contribution of tritium to the total dose has given rise to the need by the operators and/or designers to carry out developments and improvements to try to optimize tritium control technologies. Within a tritium control program, only that one which includes the heavy water detritiation will allow to reduce the tritium concentrations at optimum levels for safety and cost-effective power plant operation. The technology chosen to be applied should depend not only on the technical feasibility but also on the analysis of economic and juncture factors such as, among others, the quantity of heavy water to be treated. It is the authors` belief that AECL tendency concerning heavy water treatment in its future reactors would be to employ the CECE technology complemented with immobilization on titanium beds, with the `on-line` detritiation in each nuclear power plant. This would not be of immediate application since our analysis suggests that AECL would assume that the process is under development and needs to be tested. (author). 21 refs.

Lessons learned from current Qinshan CANDU project and the impact on future NPP's

International Nuclear Information System (INIS)

Hedges, K. R.; Didsbury, R.; Yu, S. K. W.

2000-01-01

AECL has adopted an evolutionary approach to the development of the CANDU 6 and CANDU 9 Nuclear Power Plant (NPP) designs. Each new NPP project benefits from previous projects and contains an increasing number of fully proven enhancements. In accordance with this evolutionary design approach, AECL has built on the Wolsong and Qinshan successes and the solid performance of the reference CANDU stations to define, review and implement the enhancements for the CANDU 9 NPP. Some of these enhancements include fully integrated project information systems and databases, safety enhancements coming from PSA studies and licensing activities, distributed control systems for plant-wide control and an advanced control center which addresses human factors engineering concepts. Examples of the Qinshan CANDU project delivery enhancements are the utilization of electronic engineering tools for the complete plant, and the linking of these tools with the project material management system and document management systems. The project information is reviewed and approved at the engineering office in Canada and then transmitted to site electronically. Once the electronic data is at site the information packages are extracted as necessary to enable construction and facilitate contract needs with minimum effort. This paper will provide details of the CANDU Qinshan project experiences as well as describing some of the corresponding CANDU 9 enhancements. (author)

CANDU 6 - the highly successful medium sized reactor

International Nuclear Information System (INIS)

Hedges, K. R.; Allen, P. J.; Hopwood, J. M.

2000-01-01

The CANDU 6 Pressurized Heavy Water Reactor system, featuring horizontal fuel channels and heavy water moderator continues to evolve, supported by AECL's strong commitment to comprehensive R and D programs. The initial CANDU 6 design started in the 1970's. The first plants went into service in 1983, and the latest version of the plant is under construction in China. With each plant the technology has evolved giving the dual advantages of proveness and modern technology. CANDU 6 delivers important advantages of the CANDU system with benefit to small and medium-sized grids. This technology has been successfully adopted by, and localized to varying extents in, each of the CANDU 6 markets. For example, all CANDU owners obtain their fuel from domestic suppliers. Progressive CANDU development continues at AECL to enhance this medium size product CANDU 6. There are three key CANDU development strategic thrusts: improved economics, fuel cycle flexibility, and enhanced safety. The CANDU 6 product is also enhanced by incorporating improvements and advanced features that will be arising from our CANDU Technology R and D programs in areas such as heavy water and tritium, control and instrumentation, fuel and fuel cycles, systems and equipment and safety and constructability. (author)

Assessment of Siemens plessey electronic personal dosimeter

International Nuclear Information System (INIS)

Hirning, C.R.; Lopez, S.; Yuen, P.S.

1994-01-01

This report presents the results of a laboratory assessment of the performance of a new type of personal dosimeter. The Electronic Personal Dosimeter, or EPD, was developed jointly by the National Radiological Protection Board and Siemens Plessey Controls Limited, both of the United Kingdom. Twenty pre-production units of the EPD and a reader were purchased by Ontario Hydro for the assessment. The tests were conducted jointly by Ontario Hydro's Health and Safety Division and AECL Research's Chalk River Laboratories (CRL), with funding from the Candu Owner's Group. A total of 26 tests were conducted, divided between Ontario Hydro and AECL. The test results were compared with the relevant requirements of three standards. In general, the performance of the EPD was found to be quite acceptable. It met most of the relevant requirements of the three standards and most of the design specifications. However, the following deficiencies were found: slow response time; sensitivity to high-frequency EMF; poor resistance to dropping; and an alarm that is not loud enough. In addition, the response of the EPD to low-energy beta rays may be too low for some applications. There were serious problems with the reliability of operation of the pre production EPDs used in these tests. 9 refs., 34 tabs., 20 figs

The pressurized heavy water reactor programme in the Republic of Korea

International Nuclear Information System (INIS)

Young Eek Jung

1997-01-01

KEPCO (Korea Electric Power Corporation) opened its HWR program in 1977 by starting the construction of Wolsong 1 (CANDU-6). Wolsong 1 completed its construction in 1983 and has been operated successfully achieving an average lifetime capacity factor of 85%. As far as PHWR technology is concerned, KEPCO did not have self reliance program like PWR but for the PHWR technology development of Korea, KEPCO and AECL made technology transfer agreement for the CANDU-6 NSSS design at the time of Wolsong 3 and 4 contracts. Under this agreement, AECL has provided the CANDU-6 design technology and it is contributing to the development of Korean PHWR design technology. In the field of fuel, KAERI (Korea Atomic Energy Research Institute) is carrying out the feasibility study of CANFLEX and DUPIC. Planning of future CANDU projects in Korea as well as type and capacity if constructed is under study by KEPCO. The economic aspects of CANDU-6, the future prospects of CANDU-9 technology development and availability of construction site will be the important points of study and it will be finished next year. The result of study will be reflected to the new Korean electric power development plan, which will extend Korean power plant construction schedule until 2010

Point Lepreau refurbishment: plant condition assessment

International Nuclear Information System (INIS)

Allen, P.J.; Soulard, M.R.; David, F.; Clefton, G.; Weeks, R.

2001-01-01

New Brunswick Power (NB Power) has initiated a study into the refurbishment of the Point Lepreau Generating Station, with the objective to extend plant operation another 25 to 30 years. The end product of this study will be a business case that compares the costs of refurbishing Point Lepreau with costs of alternate means of generation. The Project Execution Plan and business case are being developed by an integrated team of AECL, NB Power and subcontractor staff under the project management of AECL. The refurbishment scope will include replacement of the pressure tubes, calandria tubes and part of the feeder piping. Planning of these replacements is part of the refurbishment study work. Planning is also underway for the environmental, safety and licensing issues that would need to be addressed to ensure future operation of the unit. In addition to these studies, a systematic review of the plant has been carried out to determine what other equipment refurbishment or replacement will be required due to ageing or obsolescence of plant equipment. This Plant Condition Assessment (PCA) follows a highly structured approach to ensure consistency. This paper presents an overview of the engineering process and the main findings from the work. (author)

The advanced MAPLE reactor concept

International Nuclear Information System (INIS)

Lidstone, R.F.; Lee, A.G.; Gillespie, G.E.; Smith, H.J.

1989-01-01

In Canada the need for advanced neutron sources has long been recognized. During the past several years Atomic Energy of Canada Limited (AECL) has been developing the new MAPLE multipurpose reactor concept. To date, the MAPLE program has focused on the development of a modest-cost multipurpose medium-flux neutron source to meet contemporary requirements for applied and basic research using neutron beams, for small-scale materials testing and analysis and for radioisotope production. The basic MAPLE concept incorporates a compact light-water cooled and moderated core within a heavy water primary reflector to generate strong neutron flux levels in a variety of irradiation facilities. In view of renewed Canadian interest in a high-flux neutron source, the MAPLE group has begun to explore advanced concepts based on AECL's experience with heavy water reactors. The overall objective is to define a high-flux facility that will support materials testing for advanced power reactors, new developments in extracted neutron-beam applications, and/or production of radioisotopes. The design target is to attain performance levels of HFR-Grenoble, HFBR, HFIR in a new heavy water-cooled, -moderated,-reflected reactor based on rodded LEU fuel. Physics, shielding, and thermohydraulic studies have been performed for the MAPLE heavy water reactor. 14 refs., 4 figs., 1 tab

Technologies for tritium control in fission reactors moderated with heavy water

International Nuclear Information System (INIS)

Ramilo, L.B.; Gomez de Soler, S.M.

1996-01-01

This study was done within a program one of whose objectives was to analyze the possible strategies and technologies, to be applied to HWR at Argentine nuclear power plants, for tritium control. The high contribution of tritium to the total dose has given rise to the need by the operators and/or designers to carry out developments and improvements to try to optimize tritium control technologies. Within a tritium control program, only that one which includes the heavy water detritiation will allow to reduce the tritium concentrations at optimum levels for safety and cost-effective power plant operation. The technology chosen to be applied should depend not only on the technical feasibility but also on the analysis of economic and juncture factors such as, among others, the quantity of heavy water to be treated. It is the authors' belief that AECL tendency concerning heavy water treatment in its future reactors would be to employ the CECE technology complemented with immobilization on titanium beds, with the 'on-line' detritiation in each nuclear power plant. This would not be of immediate application since our analysis suggests that AECL would assume that the process is under development and needs to be tested. (author). 21 refs

Assessment of Siemens plessey electronic personal dosimeter

Energy Technology Data Exchange (ETDEWEB)

Hirning, C R; Lopez, S [Ontario Hydro, Toronto, ON (Canada); Yuen, P S [Atomic Energy of Canada Ltd., Chalk River, ON (Canada). Chalk River Nuclear Labs.

1994-01-01

This report presents the results of a laboratory assessment of the performance of a new type of personal dosimeter. The Electronic Personal Dosimeter, or EPD, was developed jointly by the National Radiological Protection Board and Siemens Plessey Controls Limited, both of the United Kingdom. Twenty pre-production units of the EPD and a reader were purchased by Ontario Hydro for the assessment. The tests were conducted jointly by Ontario Hydro`s Health and Safety Division and AECL Research`s Chalk River Laboratories (CRL), with funding from the Candu Owner`s Group. A total of 26 tests were conducted, divided between Ontario Hydro and AECL. The test results were compared with the relevant requirements of three standards. In general, the performance of the EPD was found to be quite acceptable. It met most of the relevant requirements of the three standards and most of the design specifications. However, the following deficiencies were found: slow response time; sensitivity to high-frequency EMF; poor resistance to dropping; and an alarm that is not loud enough. In addition, the response of the EPD to low-energy beta rays may be too low for some applications. There were serious problems with the reliability of operation of the pre production EPDs used in these tests. 9 refs., 34 tabs., 20 figs.

Enhancing PLiM/LCM through integration strategies

International Nuclear Information System (INIS)

Dam, R.F.; Watson, P.; Nickerson, J.H.

2004-01-01

Plant Life Management and Life Cycle Management activities continue to become an increasingly important part of NPP planning and O and M efforts. AECL, as a developer and provider of PLiM/LCM products and services, has been working towards providing effective and efficient tools and processes to support this activity. As these products evolve, it is becoming evident that there are significant benefits from ensuring that AECL and their utility partners engage in an Integrated PLiM approach. The integration of PLiM products and services goes far beyond simply relating the various aspects of the technology. The strategy to enhance the integration of PLiM includes three specific areas; namely the integrated aging knowledge base, the integrated assessment technology, and the integrated implementation within the plant. Through integration at all these levels the PLiM technology is able to be adaptive, providing a means for improved design and assessment capability, enhanced asset management capabilities, as well as providing for a flexible and more efficient delivery of PLiM services according to utility needs. This paper explores each of the three areas of integration, the resulting Enhanced PLiM/LCM capability, and how this capability translates to benefits for the operating stations both new and old. (author)

Feeder replacement tooling and processes

International Nuclear Information System (INIS)

Mallozzi, R.; Goslin, R.; Pink, D.; Askari, A.

2008-01-01

Primary heat transport system feeder integrity has become a concern at some CANDU nuclear plants as a result of thinning caused by flow accelerated corrosion (FAC). Feeder inspections are indicating that life-limiting wall thinning can occur in the region between the Grayloc hub weld and second elbow of some outlet feeders. In some cases it has become necessary to replace thinned sections of affected feeders to restore feeder integrity to planned end of life. Atomic Energy of Canada Limited (AECL) and Babcock and Wilcox Canada Ltd. (B and W) have developed a new capability for replacement of single feeders at any location on the reactor face without impacting or interrupting operation of neighbouring feeders. This new capability consists of deploying trained crews with specialized tools and procedures for feeder replacements during planned outages. As may be expected, performing single feeder replacement in the congested working environment of an operational CANDU reactor face involves overcoming many challenges with respect to access to feeders, available clearances for tooling, and tooling operation and performance. This paper describes some of the challenges encountered during single feeder replacements and actions being taken by AECL and B and W to promote continuous improvement of feeder replacement tooling and processes and ensure well-executed outages. (author)

Reactor coolant pump seals: improving their performance

International Nuclear Information System (INIS)

Pothier, N.E.; Metcalfe, R.

1986-06-01

Large CANDU plants are benefitting from transient-resistant four-year reliable reactor coolant pump seal lifetimes, a direct result of AECL's 20-year comprehensive seal improvement program involving R and D staff, manufacturers, and plant designers and operators. An overview of this program is presented, which covers seal modification design, testing, post-service examination, specialized maintenance and quality control. The relevancy of this technology to Light Water Reactor Coolant Pump Seals is also discussed

Radar sounding of bedrock and water table at Chalk River

International Nuclear Information System (INIS)

Annan, A.P.; Davis, J.L.

1979-01-01

When a spill of radioactive waste occurs, one of the main concerns is the flow pattern of ground water in the area of the spill. Ground probing radar is a relatively new geophysical technique which can provide high resolution data on the surficial geology and water distribution. The results of some preliminary radar experiments conducted at Chalk River Nuclear Laboratories (CRNL) of the Atomic Energy of Canada Limited (AECL), Chalk River, Ontario are presented. (auth)

The CANDU 80

International Nuclear Information System (INIS)

Hart, R.S.

1998-01-01

AECL has completed the conceptual design of a small CANDU plant with an output, in the range of 300 MWth (called the CANDU 80), suitable for a variety of electrical and co-generation applications including desalination, oil sands oil extraction and processing, and the provision of electricity and heat to areas with low demand. This paper provides a brief overview of the CANDU 80, and discusses key features contributing to safety and operational margins

The formation and characteristics of hydride blisters in c.w. Zircaloy-2 pressure tubes

Energy Technology Data Exchange (ETDEWEB)

Price, E G [ed.

1994-09-01

Under the auspices of the IAEA, a consultants` meeting was arranged in Vienna, 1994 July 25-29, at which a Canadian delegation, consisting of AECL and Ontario Hydro Technologies personnel, presented information on their knowledge of the behaviour of hydride blisters in Zircaloy-2 pressure tubes. This document contains the 10 papers presented by the Canadian delegation to the meeting. It is believed that they represent a good reference document on hydride blister phenomena.

The Cigar Lake analog study: An international R ampersand D project

International Nuclear Information System (INIS)

Cramer, J.J.; Sargent, F.P.

1994-01-01

This paper provides background information and summarizes the results of AECL's analog study on the Cigar Lake uranium deposit. This R ampersand D project includes national and international cooperation with many organizations directly or indirectly involved in nuclear waste management research. The emphasis is on the analog aspects of this deposit and the implications of modelling activities related to the environmental and safety assessment of the Canadian disposal concept for nuclear fuel waste

A registry for the study of the health of radiation workers employed by Atomic Energy of Canada Limited

International Nuclear Information System (INIS)

Weeks, J.L.

1979-05-01

Factors to be considered in formulating a study of the health of radiation workers are discussed, and a proposal is made for the establishment of such a study in relation to the employees of Atomic Energy of Canada Limited. By setting up a registry of AECL radiation workers, data could be accumulated suitable for the long-term followup of their health, and for preparing periodic interim reports on mortality and morbidity. (author)

MAPLE research reactor beam-tube performance

International Nuclear Information System (INIS)

Lee, A.G.; Lidstone, R.F.; Gillespie, G.E.

1989-05-01

Atomic Energy of Canada Limited (AECL) has been developing the MAPLE (Multipurpose Applied Physics Lattice Experimental) reactor concept as a medium-flux neutron source to meet contemporary research reactor applications. This paper gives a brief description of the MAPLE reactor and presents some results of computer simulations used to analyze the neutronic performance. The computer simulations were performed to identify how the MAPLE reactor may be adapted to beam-tube applications such as neutron radiography

Lessons learned in applying function analysis

International Nuclear Information System (INIS)

Mitchel, G.R.; Davey, E.; Basso, R.

2001-01-01

This paper summarizes the lessons learned in undertaking and applying function analysis based on the recent experience of utility, AECL and international design and assessment projects. Function analysis is an analytical technique that can be used to characterize and asses the functions of a system and is widely recognized as an essential component of a 'systematic' approach to design, on that integrated operational and user requirements into the standard design process. (author)

Summary of geoscience work at the AECL research site near Atikokan, Ontario

International Nuclear Information System (INIS)

Stone, D.

1984-03-01

Since 1979 June, geolgical, geophysical and hydro-geological investigations have been conducted at Research Area 4 north of Atikokan, Ontario as part of the Canadian Nuclear Fuel Waste Management Program. Composition, shape and internal structure of the Eye-Dashwa pluton were the subjects of regional field studies. Detailed research concentrated on the detection and characterization of surface and subsurface fractures within a 400-m x 800-m grid area, where five boreholes were drilled to depths of between 200 m and 1100 m. Fracture zones in the area were readily detected by surface mapping, ground very low frequency electromagnetic (VLF-EM) surveys and borehole logging. Borehole logs, downhole tube-wave seismic surveys, and thermal and television logging were successful in detecting open fractures in boreholes

Microbial analysis of the buffer/container experiment at AECL's Underground Research Laboratory

International Nuclear Information System (INIS)

Stroes-Gascoyne, S.; Hamon, C.J.; Haveman, S.A.; Delaney, T.L.

1996-05-01

The Buffer/Container experiment was carried out for 2.5 years to examine the in-situ performance of compacted buffer material in a single emplacement borehole under vault-relevant conditions. During decommissioning of this experiment, numerous samples were taken for microbial analysis to determine if the naturally present microbial population in buffer material survived to conditions and to determine which groups of microorganisms would be dominant in such a simulated vault environment. Microbial analyses were initiated within 24 hour of sampling for all types of samples taken. The culture results showed an almost universal disappearance of viable microorganisms in the samples taken from near the heater surface. The microbial activity measurements confirmed the lack of viable organisms with very weak or no activity measured in most of these samples. Generally, aerobic heterotrophic culture conditions gave the highest mean colony-forming units (CFU) values at both 25 and 50 C. Under anaerobic conditions, and especially at 50 C, lower mean CFU values were obtained. In all samples analyzed, numbers of sulfate reducing bacteria were less than 1000 CFU/g dry material. Methanogens were either not present or were found in very low numbers. Anaerobic sulfur oxidizing bacteria were found in higher numbers in most sample types with sufficient moisture. The statistical evaluation of the culture data demonstrated clearly that the water content was the variable limiting the viability of the bacteria present, and not the temperature. 68 refs, 35 figs, 37 tabs

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

Contribution of international cooperation in achieving the Romanian nuclear power objectives

International Nuclear Information System (INIS)

Diaconu, Daniela

2002-01-01

The international cooperation implied by the Romanian nuclear power program has on the short term the goal of supporting the Romanian effort of obtaining new nuclear fuels, improving the radioactive waste management, developing the technology and software transfer, training of Romanian researchers and participations in international projects. On long term the international cooperation is aiming at rising the scientific standards and the degree of global integration of Romanian research and technology. This policy is supported also by the agreements convened with different international organizations as for instance 'The Agreement for Nuclear Safety' or 'Common agreement for safe management of spent fuel and radioactive waste'. The INR at Pitesti and CITON - Bucharest are involved in works for cooperation technical projects supported by IAEA Vienna aiming at the nuclear safe and safeguard and power programs. At present underway are research contracts concerning the CANDU pressure tube, the corrosion in the primary cooling circuit of the CANDU reactors, as well as, the behavior under irradiation and intermediate disposal of oxide fuels. In the frame of IAEA assisted technical programs the TRIGA reactor of INR Pitesti is transferred from HEU to LEU fuels, new technologies for using recovered uranium and slightly enriched uranium fuels are developed, as well as a data acquisition system with advanced on-line characteristics. The cooperation between INR Pitesti and AECL Canada comprised in the frame of the 1998 agreement is oriented towards three fields of common interest: nuclear safety, nuclear fuel and management of in-service life of NPPs. Already transferred were computer codes from AECL devoted to accident analysis (WIMS, CATHENA and ELOCA) which were implemented and reproduced accurately all the test cases provided by AECL. For installing these codes specialists from our institute participated in training courses, on-the-job training, as well as, in validation

Deconstructing the Nature of Safety and Acceptability in Nuclear Fuel Waste Management, Canada

International Nuclear Information System (INIS)

Murphy, Brenda L.

2003-01-01

Since the Hare report was released in 1977, Canada's nuclear fuel waste management policies have been focused on one option, deep geologic disposal. However, since new legislation, called the Nuclear Fuel Waste Management Act came into force on November 15, 2002, the newly established Nuclear Waste Management Organisation has been mandated to review, over the next three years, not only deep geologic disposal but also to consider a suite of other options including reactor-site and centralised storage, and both above and below ground options. At this point in time, the process for the study and the criteria by which it will be evaluated are still quite unclear. The need for this new approach to NFW management in Canada was highlighted by an Environmental Assessment Panel (EA Panel) report in 1998. This EA Panel reviewed the 1994 environmental impact statement submitted by Atomic Energy Canada Limited (AECL) regarding the concept of deep geologic disposal in the Canadian Shield (Disposal Concept EA). The EA Panel's key conclusion was: From a technical perspective, safety of the AECL concept has been on balance adequately demonstrated for a conceptual stage of development, but from a social perspective, it has not. As it stands, the AECL concept for deep geological disposal has not been demonstrated to have broad public support. The concept in its current form does not have the required level of acceptability to be adopted as Canada's approach for managing nuclear fuel wastes. AECL's study consisted of a review of the deep geologic disposal concept, since no site has yet been selected. It is generally understood that this type of disposal facility, if eventually sited, will be located on the Ontario portion of the Canadian Shield because Ontario power generators own and manage about 90% of Canada's NFW. This key EA Panel conclusion is predicated on the use of two key decision-making criteria - safety and acceptability. This paper reviews and assesses the specific ways

Accelerating the Whiteshell Laboratories Decommissioning Through the Implementation of a Projectized and Delivery-Focused Organization - 13074

Energy Technology Data Exchange (ETDEWEB)

Wilcox, Brian; Mellor, Russ; Michaluk, Craig [Atomic Energy of Canada Limited, Whiteshell Laboratories, Pinawa, Manitoba (Canada)

2013-07-01

Whiteshell Laboratories (WL) is a nuclear research site in Canada that was commissioned in 1964 by Atomic Energy of Canada Limited. It covers a total area of approximately 4,375 hectares (10,800 acres) and includes the main campus site, the Waste Management Area (WMA) and outer areas of land identified as not used for or impacted by nuclear development or operations. The WL site employed up to 1100 staff. Site activities included the successful operation of a 60 MW organic liquid-cooled research reactor from 1965 to 1985, and various research programs including reactor safety research, small reactor development, fuel development, biophysics and radiation applications, as well as work under the Canadian Nuclear Fuel Waste Management Program. In 1997, AECL made a business decision to discontinue research programs and operations at WL, and obtained government concurrence in 1998. The Nuclear Legacy Liabilities Program (NLLP) was established in 2006 by the Canadian Government to remediate nuclear legacy liabilities in a safe and cost effective manner, including the WL site. The NLLP is being implemented by AECL under the governance of a Natural Resources Canada (NRCan)/AECL Joint Oversight Committee (JOC). Significant progress has since been made, and the WL site currently holds the only Canadian Nuclear Safety Commission (CNSC) nuclear research site decommissioning license in Canada. The current decommissioning license is in place until the end of 2018. The present schedule planned for main campus decommissioning is 30 years (to 2037), followed by institutional control of the WMA until a National plan is implemented for the long-term management of nuclear waste. There is an impetus to advance work and complete decommissioning sooner. To accomplish this, AECL has added significant resources, reorganized and moved to a projectized environment. This presentation outlines changes made to the organization, the tools implemented to foster projectization, and the benefits

Improving chemistry performance in CANDU plants

International Nuclear Information System (INIS)

Turner, C.; Guzonas, D.

2010-01-01

There is a strong interplay between coolant chemistry and materials selection in any nuclear power plant system. To achieve the design life of reactor components it is necessary to monitor and control relevant chemistry parameters, such as ionic conductivity, pH, concentrations of dissolved ions and redox species (e.g., hydrogen, hydrazine, oxygen) and the concentrations of suspended corrosion products. Chemistry specifications are set to achieve a balance between the sometimes conflicting requirements to minimize corrosion and radiological dose and to minimize operating and maintenance costs over the lifetime of the plant. For the past decade, Atomic Energy of Canada Limited (AECL) has taken a rigorous and disciplined approach to reviewing and updating all aspects of chemistry control in the CANDU® nuclear power plant (NPP). This approach has included proactively reviewing chemistry operating experience from existing CANDU® and other water-cooled NPPs worldwide to identify and address emerging issues, updating all of our chemistry control documentation to ensure that each chemistry parameter is linked to a specific requirement (e.g., reduce activity transport, monitor for condenser leak) and incorporating the latest results from our Research and Development (R and D) programs to ensure that all chemistry specifications are supported by a sound rationale. The results of this review and update have been incorporated into updated chemistry specifications and, in some cases, modified operating procedures for new and existing plants. In addition, recommendations have been made for design modifications to improve chemistry control in new build plants, especially during periods of shutdown and startup when chemistry control has traditionally been more challenging. Chemistry control in new-build CANDU® plants will rely increasingly on the use of on-line instrumentation interfaced directly to AECL's state-of-the-art chemistry monitoring, diagnostics and analysis

Discharge Burnup Evaluation of Natural Uranium Loaded CANFLEX-43 Fuel Bundle

International Nuclear Information System (INIS)

Roh, Gyu Hong; Kim, Yong Hee; Kim, Won Young; Park, Joo Hwan

2009-11-01

Using WIMS-AECL code, which is 2-dimensional lattice core used in CANDU physics calculation, the discharge burnup of the natural uranium loaded CANFLEX-43 fuel bundle was evaluated by comparing the discharge burnup of standard 37 element fuel bundle. When the discharge burnup of the standard 37 element fuel is 7,200 MWd/MTU, that of the CANFLEX 43 fuel bundle was evaluated as 7,077 MWd/MTU, by applying the same lattice conditions for both fuel bundles

A neutron scattering device for void fraction measurement in channels of the RD-14M thermalhydraulics test facility

Energy Technology Data Exchange (ETDEWEB)

Han, P; Hussein, E M.A. [New Brunswick Univ., Fredericton (Canada). Dept. of Mechanical Engineering; Ingham, P J [Atomic Energy of Canada Ltd., Pinawa, MB (Canada). Whiteshell Labs.

1996-12-31

This paper presents a neutron scattering device designed for measuring the void fraction of two-phase flow in the channels or heated sections of the RD-14M Thermalhydraulics Test Facility, located at the AECL Whiteshell Laboratories. The results of an on-line test of the device are presented. The performance of the scatterometer is assessed and is shown to be in agreement with the results inferred from other independent process-parameter measurements. (author). 2 refs., 7 figs.

Achieving CANDU excellence through collaboration

Energy Technology Data Exchange (ETDEWEB)

Dermarkar, F. [CANDU Owners Group Inc., Toronto, Ontario (Canada)

2015-07-01

All Operators of CANDU/PHWR Worldwide, and AECL, are members of Candu Owners Group (COG). COG has evolved to become primarily an Operators Owners Group with annual turnover of $75M. It is all about value to the members providing a diverse offering of services to meet a broad spectrum of member needs, linking our members together prioritizing and organizing to enable members to access what they need, when they need it. Collaboration benefits both COG and EPRI.

In situ sampling for pressure tube deuterium concentration

International Nuclear Information System (INIS)

Harrington, A.J.; Kittmer, C.A.

1988-01-01

The present method of assessing the useful life of pressure tubes in CANDU (CANada Deuterium Uranium) reactors requires the periodic removal and examination of a tube. Special tooling was developed at Atomic Energy of Canada Limited (AECL) to obtain a sample of material from a pressure tube without removing the tube from the reactor. The sampling tool concept has been successfully used by Ontario Hydro during scheduled outages at the Pickering Nuclear Generating Station (PNGS). (author)

Marketing CANDU internationally

International Nuclear Information System (INIS)

Langstaff, J.H.

1980-06-01

The market for CANDU reactor sales, both international and domestic, is reviewed. It is reasonable to expect that between five and ten reactors can be sold outside Canada before the end of the centry, and new domestic orders should be forthcoming as well. AECL International has been created to market CANDU, and is working together with the Canadian nuclear industry to promote the reactor and to assemble an attractive package that can be offered abroad. (L.L.)

TASCC newsletter volume 7 no. 2

International Nuclear Information System (INIS)

Thomson, L.

1993-02-01

A newsletter produced by Chalk River's Tandem Accelerator Superconducting Cyclotron Facility. Included in this February issue are notices on upcoming visits to TASCC by the Nuclear and Particle Physics Advisory Panel and a visit by the Deputy Minister of Industry, Science and Technology. The future of TASCC employees being of concern, a notice of terminations at AECL, none yet to TASCC. A facility report and the operating record plus a listing of experiments conducted in February

Validation of the COBRA code for dry out power calculation in CANDU type advanced fuels

International Nuclear Information System (INIS)

Daverio, Hernando J.

2003-01-01

Stern Laboratories perform a full scale CHF testing of the CANFLEX bundle under AECL request. This experiment is modeled with the COBRA IV HW code to verify it's capacity for the dry out power calculation . Good results were obtained: errors below 10 % with respect to all data measured and 1 % for standard operating conditions in CANDU reactors range . This calculations were repeated for the CNEA advanced fuel CARA obtaining the same performance as the CANFLEX fuel. (author)

Design verification of the CANFLEX fuel bundle - quality assurance requirements for mechanical flow testing

International Nuclear Information System (INIS)

Alavi, P.; Oldaker, I.E.; Chung, C.H.; Suk, H.C.

1997-01-01

As part of the design verification program for the new fuel bundle, a series of out-reactor tests was conducted on the CANFLEX 43-element fuel bundle design. These tests simulated current CANDU 6 reactor normal operating conditions of flow, temperature and pressure. This paper describes the Quality Assurance (QA) Program implemented for the tests that were run at the testing laboratories of Atomic Energy of Canada Limited (AECL) and Korea Atomic energy Research Institute (KAERI). (author)

Annual health, safety and environmental performance report for 1992

International Nuclear Information System (INIS)

Orman, R.F.; Richards, S.

1993-12-01

This report summarizes the safety and environmental record of the operations of Atomic Energy of Canada Limited (AECL) during 1992. An introduction highlights the results and describes the facilities and organizational systems. Subsequent sections indicate the performance of the company with respect to personnel radiation exposures, occupational injuries, the handling of wastes and the release of materials into the environment. Programs in health, safety and environmental protection are presented, along with site remediation and emergency preparedness practices

Annual health, safety and environmental performance report for 1992

International Nuclear Information System (INIS)

Orman, R.F.; Richards, S.

1993-12-01

This report summarizes the safety and environmental record of the operations of Atomic Energy of Canada Limited (AECL) during 1992. an introduction highlights the results and describes the facilities and organizational systems. Subsequent sections indicate the performance of the company with respect to personnel radiation exposures, occupational injuries, the handling of wastes and the release of materials into the environment. Programs in health, safety and environmental protection are presented, along with site remediation and emergency preparedness practices

Achieving CANDU excellence through collaboration

International Nuclear Information System (INIS)

Dermarkar, F.

2015-01-01

All Operators of CANDU/PHWR Worldwide, and AECL, are members of Candu Owners Group (COG). COG has evolved to become primarily an Operators Owners Group with annual turnover of $75M. It is all about value to the members providing a diverse offering of services to meet a broad spectrum of member needs, linking our members together prioritizing and organizing to enable members to access what they need, when they need it. Collaboration benefits both COG and EPRI.

Annual report, 1981-82

International Nuclear Information System (INIS)

1982-01-01

Recent operational restructuring implemented grouped the Engineering, Chemical, and International Companies under CANDU Operations. The Research Company was charged with finding products and markets to bridge the gap in new orders for reactors apparent for the next few years. Net income rose 46 percent to $19.7 million. Economic slowdown in Canada and elsewhere had little effect as AECL continued to fufill obligations on previously negotiated multi-year contracts. Over 60 percent of commercial revenue came from outside Canada, and at $234 million was marginally higher than 1980-81. Development of the superconducting cyclotron continued at Chalk River, with successful testing of magnetic field and radiofrequency systems. The nuclear fuel waste management program continued, with selection of a site for an underground research laboratory near Pinawa, Manitoba. The Therac-25 high energy accelerator for cancer therapy neared completion of its development and manufacturing program. There are more than 10 orders already booked. A record 15.2 million curies of cobalt 60 were shipped, an increase of 25 percent in orders for gamma irradiation processing. The prototype Douglas Point generating station was returned to full power and reached its highest annual capacity factor since 1975. Conceptual design of the new standardized two 950MW-unit CANDU PHWR generating station was completed. AECL responded to a request for quotations from the Mexican government for its nuclear power program

Design capability of CANDU heat transport pump shafts against cracking

International Nuclear Information System (INIS)

Kumar, A.N.; Sheikh, Z.B.; Padgett, A.

1993-01-01

During 1986 three different Light Water Reactors (LWR's) in the U.S. reported either a cracked or fractured shaft on one or more of their reactor coolant (RC) pumps. The RC pumps for all these stations were supplied by Byron Jackson (BJ) Pump Company. A majority of CANDU heat transport (HT) pumps (equivalent of RC pumps) are supplied by BJ Pump Company and are similar in design to RC pumps. Hence the failure of these RC pumps in the U.S. utilities caused concern regarding the relevance of these failures to the BJ supplied CANDU HT pumps (HTP). This paper presents the results of AECL assessment to establish the capability of the HT pump shaft against cracking. Two methods were used for assessment: (a) detailed comparative design review of the HTP and RCP shafts; (b) semi-empirical analysis of the HTP shafts. The results of the AECL assessment showed significant differences in detailed design, materials, assembly and fits of various components and the control of operating parameters between the HT and RC pumps. It was concluded that because of these differences the failures similar to RC pump shafts are not likely to appear in HT pump shafts. This conclusion is further reinforced by about 140,000 hours of operating history of the longest running HT pump of comparable size to RC Pumps, without failures

Discussing spent nuclear fuel in high school classrooms: addressing public fears through early education

International Nuclear Information System (INIS)

Winkel, S.; Sullivan, J.; Jones, S.; Sullivan, K.; Hyland, B.; Pencer, J.; Colton, A.

2013-01-01

The Inreach program combines the Deep River Science Academy (DRSA) 'learning through research' approach with state of the art communication technology to bring scientific research to high school classrooms. The Inreach program follows the DRSA teaching model where a university student tutor works on a research project with scientific staff at AECL's Chalk River Laboratories. Participating high school classes are located across Canada. The high school students learn about the ongoing research activities via weekly web conferences. In order to engage the students and encourage participation in the conferences, themed exercises linked to the research project are provided to the students. The DRSA's Inreach program uses a cost-effective internet technology to reach a wide audience, in an interactive setting, without anyone leaving their desks or offices. An example Inreach research project is presented here: an investigation of the potential of the Canadian supercritical water cooled reactor (SCWR) concept to burn transuranic elements (Np, Pu, Am, Cm) to reduce the impact of used nuclear fuel. During this project a university student worked with AECL (Atomic Energy of Canada Limited) researchers on technical aspects of the project, and high school students followed their progress and learned about the composition, hazards, and disposition options for used nuclear fuel. Previous projects included the effects of tritium on cellular viability and neutron diffraction measurement of residual stresses in automobile engines

The Cernavoda project - past and future

International Nuclear Information System (INIS)

Glodeanu, F.; Campureanu, T.; Chirica, T.; Popescu, D.

1995-01-01

The history of the Cernavoda nuclear power station in Romania is traced. It was conceived in 1977 as five unit CANDU-6 station and agreements were concluded on engineering, procurement and financial assistance with Atomic Energy of Canada Ltd (AECL) and Ansaldo of Italy. Delays in construction were created from the first, however, by efforts to manufacture as many components as possible in Romania, unfamiliarity with nuclear project management and the disadvantages of a highly centralised economy. Political changes since December 1989 have led to a new approach to project implementation. The Romanian Electricity Authority (RENEL), signed a new contract with AECL and Ansaldo in August 1991 to perform the project management for the completion of Cernavoda 1. The project has progressed very well and by the beginning of 1995 more than 90% of the plant systems were ready for commissioning and a full operating shift was in place. As a second phase of the nuclear power programme RENEL plans to complete Cernavoda 2, the construction of which was suspended at 30% completion. The three other units will be preserved in their present preliminary stage of construction up to 2000 while finance is sought for their completion. Nuclear power is seen as an environmentally clean means of meeting Romania's growing energy demand as the economy develops. (UK)

A review of critical heat flux prediction technique and its application in CANDU reactor

International Nuclear Information System (INIS)

Park, Jee Won; Roh, Gyu Hong

1997-09-01

The CHF prediction method being used for CANDU reactor have been critically reviewed. The AECL's CHF prediction totally depends on the look-up table which has been developed from many CHF databank. These databanks include not only the water-cooled bundle-CHF data but also the freon-cooled bundle-CHF data. The CHF look-up tables have been developed by smoothing and interpolating (with some extrapolations) the experimental data to construct a practically useful CHF table. Therefore, the table look-up method has advantages of accuracy, consistency in a wide range of thermal-hydraulic parameters. It seems, however, that since the existing look-up table is constructed by many steps of modification of the original experimental data (e.g., the look-up table is constructed not only using the horizontal flow data but also the vertical flow data), one should be very careful when one try to generate a look-up table for other fuel geometries. In other words, a reliable look-up table can be constructed by performing experiments for new fuel geometry. Finally, it should be noted that the modifications to the original experimental data has simple form with many modification parameters for taking into account of different geometrical effects. This report presents the backbone and the validity of AECL CHF look-up table. (author). 22 refs., 2 tabs., 2 figs

Evaluation of the linear power of HANARO test fuel bundles

Energy Technology Data Exchange (ETDEWEB)

Lee, Choong Sung; Seo, C. G.; Lee, B. C.; Kim, H. R

2001-02-01

The HANARO fuel was developed by AECL and it is configured in a bundle of rods containing uranium silicide. AECL has conducted a variety of tests using specimen in order to achieve its qualification and licensing and the highest linear power was evaluated to be 112.8kW/m. In design stage of HANARO, the best estimated maximum linear power at hot spot was found to occur in the transition core from the initial to the equilibrium and its value was 108kW/m, which exceeds 112.8kW/m if the physics uncertainty of the HANARO nuclear design model is taken into account. Consequently, the licensing body issued the conditional permit to operate HANARO and the fuel integrity at the linear power higher than 112.8kW/m was requested to be confirmed through irradiation tests by realizing its repeatability. Hereby, KAERI designed uninstrumented and instrumented test fuel bundles and conducted their burnup tests. In parallel with the tests, the nuclear design model has been revised and updated to enable us to pursue the pin-by-pin power history. This report describes the best estimated power history of the test fuel bundles using the revised model. In conclusion, HANARO fuel keeps its integrity at power condition greater than 120kW/m.

Romanian nuclear fuel fabrication and in-reactor fuel operational experience

International Nuclear Information System (INIS)

Budan, O.

2003-01-01

A review of the Romanian nuclear program since mid 60's is made. After 1990, the new Romanian nuclear power authority, RENEL-GEN, elaborated a realistic Nuclear Fuel Program. This program went through the Romanian nuclear fuel plant qualification with the Canadian (AECL and ZPI) support, restarting in January 1995 of the industrial nuclear fuel production, quality evaluation of the fuel produced before 1990 and the recovery of this fuel. This new policy produced good results. FCN is since 1995 the only CANDU fuel supplier from outside Canada recognised by AECL as an authorised CANDU fuel manufacturer. The in-reactor performances and behaviour of the fuel manufactured by FCN after its qualification have been excellent. Very low - more then five times lesser than the design value - fuel defect rate has been recorded up to now and the average discharge of this fuel was with about 9% greater than the design value. Since mid 1998 when SNN took charge of the production of nuclear generated electricity, FCN made significant progresses in development and procurement of new and more efficient equipment and is now very close to double its fuel production capacity. After the completion of the recovery of the fuel produced before June 1990, FCN is already prepared to shift its fuel production to the so-called 'heavy' bundle containing about 19.3 kg of Uranium per bundle

Safety upgrades to the NRU research reactor

International Nuclear Information System (INIS)

DeAbreu, B.; Mark, J.M.; Mutterback, E.J.

1998-01-01

The NRU (National Research Universal) Reactor is a 135 MW thermal research facility located at Chalk River Laboratories, and is owned and operated by Atomic Energy of Canada Limited. One of the largest and most versatile research reactors in the world, it serves as the R and D workhorse for Canada's CANDU business while at the same time filling the role as one of the world's major producers of medical radioisotopes. AECL plans to extend operation of the NRU reactor to approximately the year 2005 when a new replacement, the Irradiation Research Facility (IRF) will be available. To achieve this, AECL has undertaken a program of safety reassessment and upgrades to enhance the level of safety consistent with modem requirements. An engineering assessment/inspection of critical systems, equipment and components was completed and seven major safety upgrades are being designed and installed. These upgrades will significantly reduce the reactor's vulnerability to common mode failures and external hazards, with particular emphasis on seismic protection. The scheduled completion date for the project is 1999 December at a cost approximately twice the annual operating cost. All work on the NRU upgrade project is planned and integrated into the regular operating cycles of the reactor; no major outages are anticipated. This paper describes the safety upgrades and discusses the technical and managerial challenges involved in extending the operating life of the NRU reactor. (author)

Simulation of transient heat transfer in MACSTOR/KN-400 module storing irradiated CANDU fuel

Energy Technology Data Exchange (ETDEWEB)

Sabourin, G. [Atomic Energy of Canada Limited, Montreal, Quebec (Canada); Lee, K.-H.; Yoon, J.-H.; Choi, B.-I.; Lee, H.-Y.; Song, M.-J. [KHNP, Nuclear Environment Technology Inst., Taejon (Korea, Republic of)

2004-07-01

Korea Hydro and Nuclear Power (KHNP), in collaboration with Atomic Energy of Canada Limited (AECL), are developing a new module for the dry storage of spent fuel from the four CANDU 6 nuclear reactors at the Wolsong site in South Korea, the MACSTOR/KN-400. The simulation of transient conditions for AECL's spent fuel dry storage systems, presented in this paper, has not been performed before and is considered a major achievement of the present work. In a fist step, CATHENA was compared to MACSTOR-200 temperature measurements and the accuracy of the results were very good. In a second step, CATHENA was applied to the MACSTOR/KN-400. Four cases were performed for the MACSTOR/KN-400: Off-normal cases in summer and winter and reduced air flow cases in summer and winter. The maximum local concrete temperatures were predicted to be 63{sup o}C for the off-normal case and 65{sup o}C in the reduced air flow case. The maximum temperature gradients in the concrete are predicted to be 28{sup o}C for the off-normal case and 30{sup o}C in the reduced air flow case, incorporating a 3{sup o}C uncertainty. This paper shows that the maximum temperature for the module is expected to meet the temperature limitations of appropriate standards. (author)

Fuel cycles - a key to future CANDU success

International Nuclear Information System (INIS)

Kuran, S.; Hopwood, J.; Hastings, I.J.

2011-01-01

Globally, fuel cycles are being evaluated as ways of extending nuclear fuel resources, addressing security of supply and reducing back-end spent-fuel management. Current-technology thermal reactors and future fast reactors are the preferred platform for such fuel cycle applications and as an established thermal reactor with unique fuel-cycle capability, CANDU will play a key role in fulfilling such a vision. The next step in the evolution of CANDU fuel cycles will be the introduction of Recovered Uranium (RU), derived from conventional reprocessing. A low-risk RU option applicable in the short term comprises a combination of RU and Depleted Uranium (DU), both former waste streams, giving a Natural Uranium Equivalent (NUE) fuel. This option has been demonstrated in China, and all test bundles have been removed from the Qinshan 1 reactor. Additionally, work is being done on an NUE full core, a Thorium demonstration irradiation and an Advanced Fuel CANDU Reactor(AFCR). AECL is developing other fuel options for CANDU, including actinide waste burning. AECL has developed the Enhanced CANDU 6 (EC6) reactor, upgraded from its best-performing CANDU 6 design. High neutron economy, on-power refueling and a simple fuel bundle provide the EC6 with the flexibility to accommodate a range of advanced fuels, in addition to its standard natural uranium. (author)

CANDU physics considerations for the disposition of weapons-grade plutonium

Energy Technology Data Exchange (ETDEWEB)

Pitre, J; Chan, P; Dastur, A [Atomic Energy of Canada Ltd., Mississauga, ON (Canada)

1996-12-31

At the request of the US Department of Energy AECL has examined the feasibility of using CANDU for the disposition of weapons grade plutonium. Utilizing existing CANDU technology, the feasibility of using MOX (mixed oxide) fuel in an existing CANDU reactor was studied. The results of this study indicate that the target disposition for disposal of weapons grade plutonium can be met without the requirement of any major modifications to existing plant design. (author). 3 refs., 4 tabs., 5 figs.

Field test of wireless sensor network in the nuclear environment

International Nuclear Information System (INIS)

Li, L.; Wang, Q.; Bari, A.; Deng, C.; Chen, D.; Jiang, J.; Alexander, Q.; Sur, B.

2014-01-01

Wireless sensor networks (WSNs) are appealing options for the health monitoring of nuclear power plants due to their low cost and flexibility. Before they can be used in highly regulated nuclear environments, their reliability in the nuclear environment and compatibility with existing devices have to be assessed. In situ electromagnetic interference tests, wireless signal propagation tests, and nuclear radiation hardness tests conducted on candidate WSN systems at AECL Chalk River Labs are presented. The results are favourable to WSN in nuclear applications. (author)

Field test of wireless sensor network in the nuclear environment

Energy Technology Data Exchange (ETDEWEB)

Li, L., E-mail: lil@aecl.ca [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada); Wang, Q.; Bari, A. [Univ. of Western Ontario, London, Ontario (Canada); Deng, C.; Chen, D. [Univ. of Electronic Science and Technology of China, Chengdu, Sichuan (China); Jiang, J. [Univ. of Western Ontario, London, Ontario (Canada); Alexander, Q.; Sur, B. [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada)

2014-06-15

Wireless sensor networks (WSNs) are appealing options for the health monitoring of nuclear power plants due to their low cost and flexibility. Before they can be used in highly regulated nuclear environments, their reliability in the nuclear environment and compatibility with existing devices have to be assessed. In situ electromagnetic interference tests, wireless signal propagation tests, and nuclear radiation hardness tests conducted on candidate WSN systems at AECL Chalk River Labs are presented. The results are favourable to WSN in nuclear applications. (author)

CANDU physics considerations for the disposition of weapons-grade plutonium

International Nuclear Information System (INIS)

Pitre, J.; Chan, P.; Dastur, A.

1995-01-01

At the request of the US Department of Energy AECL has examined the feasibility of using CANDU for the disposition of weapons grade plutonium. Utilizing existing CANDU technology, the feasibility of using MOX (mixed oxide) fuel in an existing CANDU reactor was studied. The results of this study indicate that the target disposition for disposal of weapons grade plutonium can be met without the requirement of any major modifications to existing plant design. (author). 3 refs., 4 tabs., 5 figs

Comments on nuclear reactor safety in Ontario

International Nuclear Information System (INIS)

1987-08-01

The Chalk River Technicians and Technologists Union representing 500 technical employees at the Chalk River Nuclear Laboratories of AECL submit comments on nuclear reactor safety to the Ontario Nuclear Safety Review. Issues identified by the Review Commissioner are addressed from the perspective of both a labour organization and experience in the nuclear R and D field. In general, Local 1568 believes Ontario's CANDU nuclear reactors are not only safe but also essential to the continued economic prosperity of the province

Atomic Energy of Canada Limited 2007 annual financial report

International Nuclear Information System (INIS)

2007-01-01

This is the annual report of Atomic Energy of Canada Limited for the year ending March 31, 2007 and summarizes the financial activities of AECL during the period 2006-2007. The highlights for this period include increase in consolidated commercial revenue by 40%, progress on the Cernavoda reactor, increased investment in the safety and performance of the CANDU fleet and a memorandum of understanding with Natural Resources Canada to govern implementation of a five-year waste management and decommissioning plan.

Assessing inventories of past radioactive waste arisings at Chalk River Laboratories

International Nuclear Information System (INIS)

Csullog, G.W.; TerHuurne, M.A.; Miller, M.T.; Edwards, N.W.; Hulley, V.R.; McCann, D.J.

1998-01-01

Internationally, a great deal of progress has been made in improving the management of currently accumulating and anticipated future radioactive wastes. Progress includes improved waste collection, segregation, characterization and documentation in support of disposal facility licensing and operation. These improvements are not often very helpful for assessing the hazards of wastes collected prior to their implementation, since, internationally, historic radioactive wastes were not managed and documented according to today's methods. This paper provides an overview of Atomic Energy of Canada Limited's (AECL) unique approach to managing its currently accumulating, low-level radioactive wastes at Chalk River Laboratories (CRL) and it describes the novel method AECL-CRL has developed to assess its historic radioactive wastes. Instead of estimating the characteristics of current radioactive wastes on a package-by-package basis, process knowledge is used to infer the average characteristics of most wastes. This approach defers, and potentially avoids, the use of expensive analytical technologies to characterize wastes until a reasonable certainty is gained about their ultimate disposition (Canada does not yet have a licensed radioactive waste disposal facility). Once the ultimate disposition is decided, performance assessments determine if inference characterization is adequate or if additional characterization is required. This process should result in significant cost savings to AECL since expensive, resource-intensive, up-front characterization may not be required for low-impact wastes. In addition, as technological improvements take place, the unit cost of characterization usually declines, making it less expensive to perform any additional characterization for current radioactive wastes. The WIP-III data management system is used at CRL to 'warehouse' the average characteristics of current radioactive wastes. This paper describes how this 'warehouse of information

Information Exchange among COG Member Stations, Utility/AECL Design and External Nuclear Organizations

International Nuclear Information System (INIS)

Turner, Dave

1998-01-01

The paper presents the COG Information Exchange Program the mandate of which reads: 'To promote the safety reliability and excellence of CANDU plants worldwide by facilitating the sharing of operating experience amongst the members of COG'. To fulfill its mandate the COG operates Information Exchange Program which: 1. Provides a user-friendly facility, COGNET, for staff of COG member organizations to communicate with each other and with external stations, utilities and organizations on topics applicable to CANDU operation, safety, maintenance, design and performance; 2. Offers one-stop shopping for information applicable to the design, operation, maintenance, safety and performance of CANDU's; 3. Reports and compares the performance of all CANDU stations; 4. Organizes opportunities for individuals involved with the operation of CANDU's to meet with their peers and with CANDU industry experts to share operating experience; 5. Facilitates the identification of generic CANDU problems which leads to the addressing of these problems by others through co-operative projects, designer feedback and R and D programs. The paper has the following content: 1. COGNET; 1.1. COGNET Message Forums; 1.2. COGNET Operations Forums; 1.3. COGNET Private Messages; 2. Report Databases and Library; 2.1. REPEX (Technical Reports); 2.2. PCN (CANDU Plant Modifications); 2.3. SEREX (CANDU Station Events); 2.4. INPO (International Events); 3. CANDU Performance; 3.1. COG NEWSLETTERS; 3.2. Performance Indicators; 4. Workshops; 4.1. COG Workshops

Canada's high-level nuclear waste disposal concept and its evaluation process

International Nuclear Information System (INIS)

Sheng, Grant; Shemilt, L.W.

2004-01-01

The concept of disposing high-level nuclear waste in granitic rocks in the Canadian Shield, developed by Atomic Energy of Canada Limited (AECL), is anticipated to undergo a national public review within two years. The disposal concept, its documentation, and its process of evaluation, including the role of the public, government and the scientific/engineering community, are summarized. A Technical Advisory Committee (TAC) has provided external peer review of the Program since 1979 and its findings are published in annual reports which are publicly available. (author)

Annual health, safety and environmental performance report for 1993

Energy Technology Data Exchange (ETDEWEB)

Gallapher, J D; Wright, M G

1994-05-01

This report summarizes the occupational health and safety and the environmental protection record of the operations of Atomic Energy of Canada Limited (AECL) during 1993. An introduction highlights the results and describes the facilities and organizational systems. Subsequent sections indicate the performance of the company with respect to personnel radiation exposures, occupational injuries, the handling of wastes, and the release of materials into the environment. Programs in health, safety and environmental protection are presented, along with site remediation and emergency preparedness practices. (author). 14 figs.

Annual health, safety and environmental performance report for 1993

International Nuclear Information System (INIS)

Gallapher, J.D.; Wright, M.G.

1994-05-01

This report summarizes the occupational health and safety and the environmental protection record of the operations of Atomic Energy of Canada Limited (AECL) during 1993. An introduction highlights the results and describes the facilities and organizational systems. Subsequent sections indicate the performance of the company with respect to personnel radiation exposures, occupational injuries, the handling of wastes, and the release of materials into the environment. Programs in health, safety and environmental protection are presented, along with site remediation and emergency preparedness practices. (author). 14 figs

Validation of computer codes used in the safety analysis of Canadian research reactors

International Nuclear Information System (INIS)

Bishop, W.E.; Lee, A.G.

1998-01-01

AECL has embarked on a validation program for the suite of computer codes that it uses in performing the safety analyses for its research reactors. Current focus is on codes used for the analysis of the two MAPLE reactors under construction at Chalk River but the program will be extended to include additional codes that will be used for the Irradiation Research Facility. The program structure is similar to that used for the validation of codes used in the safety analyses for CANDU power reactors. (author)

In situ stress determination research study

International Nuclear Information System (INIS)

Austin, W.G.; Thompson, P.M.

1994-01-01

The objectives of this study are to evaluate and implement rock stress determination instruments and techniques developed by Atomic Energy of Canada Limited (AECL) at its Underground Research Laboratory (URL) for use in jointed rock and to continue the development of analytical and interpretation methods for stress determination results including effects of scale, structure and anisotropy. Testing and evaluation of the instruments and methods developed at URL need to be done in a similar rock type prior to underground access at the Yucca Mountain Site Characterization Project

Specifics of forced-convective heat transfer in supercritical carbon dioxide

Energy Technology Data Exchange (ETDEWEB)

Saltanov, A.E.; Mann, B.D.; Harvel, C.G.; Pioro, D.I., E-mail: Eugene.saltanov@hotmail.com [University of Ontario Institute of Technology, Oshawa, ON (Canada)

2015-07-01

The appropriate description of heat-transfer to coolants at supercritical state is one of the main challenges in development of supercritical-fluids applications for the Generation-IV reactors. In this paper the basis for comparison of relatively recent experimental data on supercritical carbon dioxide (CO{sub 2}) obtained at facilities of the Korea Atomic Energy Research Institute (KAERI) and Chalk River Laboratories (CRL) of Atomic Energy of Canada Limited (AECL) is discussed, and a preliminary heat-transfer correlation for joint CRL and KAERI datasets is presented. (author)

Economics of gamma processing in cobalt-60 irradiation facilities

International Nuclear Information System (INIS)

Gay, H. G.; Kotler, J. G.

1985-01-01

Gamma processing by cobalt-60 is well established. However, since irradiation of food is relatively new from the commercial point of view, it is important to assess costs of gamma irradiation in the context of food processing. Five different types of AECL-RCC irradiation equipment are examined in terms of their throughputs, and capital and operating costs. Using these figures, costs of irradiation of nine types of food products are presented. In general, these represent about 2-10% of the wholesale cost of these products

Build your own Candu reactor

International Nuclear Information System (INIS)

Carruthers, J.

1979-01-01

The author discusses the marketing of Candu reactors, particularly the export trade. Future sales will probably be of the nuclear side of a station only, thus striking a compromise between licensing and 'turnkey' sales. It is suggested that AECL might have made more money in the past had it not given the right to manufacture Candu fuel away to Canadian industry. Future sales to certain potential customers may be limited by the requirement of strict safeguards, which will almost certainly never be relaxed. (N.D.H.)

Atomic Energy of Canada Limited 2008 annual financial report

International Nuclear Information System (INIS)

2008-01-01

This is the annual report of Atomic Energy of Canada Limited for the year ending March 31, 2008 and summarizes the financial activities of AECL during the period 2007-2008. The major highlights for this period include increase of consolidated revenue by 4%, significant progress on Liquid Waste Transfer and Storage (LWTS) and the Fuel Packaging and Storage (FPS) project, feasibility study of a new ACR-1000 plant in New Brunswick and a memorandum of understanding with CNSC for pre project design review of ACR-1000.

Atomic Energy of Canada Limited annual report 2002-2003

International Nuclear Information System (INIS)

2003-01-01

This is the annual report of Atomic Energy of Canada Limited for the year ending March 31, 2003 and summarizes the activities of AECL during the period 2002-2003. It outlines the strategic objectives that include growing the market and market share, maximize return on resources, evolve the business structure to support business growth, grow knowledge assets, be a technology and knowledge-based innovative leader, leverage intellectual property to provide marketable products and services and establish nuclear power as a clean air and public policy solution.

Validation study of safety assessment model for radioactive waste disposal

Energy Technology Data Exchange (ETDEWEB)

Munakata, Masahiro; Takeda, Seiji; Kimura, Hideo [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

2001-12-01

The JAERI-AECL collaboration research program has been conducted to validate a groundwater flow and radionuclide transport models for safety assessment. JAERI have developed a geostatistical model for radionuclide transport through a heterogeneous geological media and verify using experimental results of field tracer tests. The simulated tracer plumes explain favorably the experimental tracer plumes. A regional groundwater flow and transport model using site-scale parameter obtained from tracer tests have been verified by comparing simulation results with observation ones of natural environmental tracer. (author)

Research on cement-based grouts for the OECD/NEA international Stripa project

International Nuclear Information System (INIS)

Onofrei, M.

1994-01-01

This paper deals with the work that has been carried out on cement-based by AECL research in Canada. The results indicate that it is possible to manufacture low water content high-performance cement-grouts, the performance of which would be acceptable for at least thousands of years and probably for much longer periods. Moreover, these grouts were shown to have negligible hydraulic conductivity, associated with very low porosity and to be highly leach resistant in repository conditions. (TEC). 18 refs., 1 tab., 6 figs

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

Factors affecting the differences in reactivity and dissolution rates between UO2 and spent nuclear fuel

International Nuclear Information System (INIS)

Shoesmith, D.W.; Tait, J.C.; Sunder, S.; Steward, S.; Russo, R.E.; Rudnicki, J.D.

1996-08-01

Strategies for the permanent disposal of spent nuclear fuel are being investigated by the U.S. Department of Energy at the Yucca Mountain site and by Atomic Energy of Canada Limited (AECL) in plutonic rock formations in the Canadian Shield. Uranium dioxide is the primary constituent of spent nuclear fuel and dissolution of the matrix is regarded as a necessary step for the release of radionuclides to repository groundwaters. In order to develop models to describe the dissolution of the U0 2 fuel matrix and subsequent release of radionuclides, it is necessary to understand both chemical and oxidative dissolution processes and how they can be affected by parameters such as groundwater composition, pH, temperature, surface area, radiolysis and redox potential. This report summarizes both published and on-going dissolution studies of U0 2 and both LWR and CANDU spent fuels being conducted at the Pacific Northwest Laboratory, Lawrence Livermore National Laboratory and Lawrence Berkeley Laboratory in the U.S. and at AECL's Whiteshell Laboratories in Canada. The studies include both dissolution tests and electrochemical experiments to measure uranium dissolution rates. The report focuses on identifying differences in reactivity towards aqueous dissolution between U0 2 and spent fuel samples as well as estimating bounding values for uranium dissolution rates. This review also outlines the basic tenets for the development of a dissolution model that is based on electrochemical principles. (author). 49 refs., 2 tabs., 11 figs