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Sample records for canadian nru reactor

  1. A description of the Canadian irradiation-research facility proposed to replace the NRU reactor

    Energy Technology Data Exchange (ETDEWEB)

    Lee, A G; Lidstone, R F; Bishop, W E; Talbot, E F; McIlwain, H [Atomic Energy of Canada Ltd., Pinawa, MB (Canada). Whiteshell Labs.

    1996-12-31

    To replace the aging NRU reactor, AECL has developed the concept for a dual-purpose national Irradiation Research Facility (IRF) that tests fuel and materials for CANDU (CANada Deuterium Uranium) reactors and performs materials research using extracted neutron beams. The IRF includes a MAPLE reactor in a containment building, experimental facilities, and support facilities. At a nominal reactor power of 40 MW{sub t}, the IRF will generate powers up to 1 MW in natural-uranium CANDU bundles, fast-neutron fluxes up to 1.4 x 10{sup 18} n{center_dot}m{sup -2}{center_dot}s{sup -1} in Zr-alloy specimens, and thermal-neutron fluxes matching those available to the NRU beam tubes. (author). 9 refs., 5 tabs., 2 figs.

  2. Balancing the risks: the NRU reactor and the isotope crisis in Canada

    International Nuclear Information System (INIS)

    Morrison, B.; Meneley, D.

    2008-01-01

    The extended shutdown of the NRU reactor at Chalk River at the end of 2007 caused a critical shortage of medical radioisotopes in Canada and the world, led to a unique meeting of Canada's Parliament to pass emergency legislation, and cost the President of the Canadian Nuclear Safety Commission her job. This paper, based on the public record, reviews these events from the perspective of the balance of risk between the safety of the NRU reactor and the impact of a shortage of isotopes. This leads to important questions about the mandate, independence and flexibility of the nuclear regulator, relations between the regulator, the government, and the licensee, and the government's overall management of risks. We argue that the government approaches individual risks in isolation and needs a mechanism to deal with multiple risks. (author)

  3. 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)

  4. A licence renewal approach for the NRU research reactor

    International Nuclear Information System (INIS)

    Natalizio, A.; Gumley, P.

    1991-01-01

    Licence Renewal is not only a subject that is being addressed for power reactors, but it is one of immediate interest for a number of research facilities, world-wide. In Canada, research reactors and power reactors are issued an operating licence for a limited term (typically two years), hence, licence renewal is done on a regular basis. Therefore, licence renewal in the Canadian context is different than in the context of this topical meeting. The NRU research reactor facility is being assessed for a licence renewal beyond its original design life. This paper describes the licence renewal approach, the assessments being performed to establish the condition of the facility, and the Safety Assessment Basis which defines the requirements for licence renewal. The current status of the assessments is also described. (author)

  5. Summary of loops in the Chalk River NRX and NRU reactors

    International Nuclear Information System (INIS)

    Nishimura, D.T.

    1980-12-01

    The design and operating parameters of the high pressure, high temperature light water loops in the NRX and NRU reactors are presented to assist experimenters reviewing these facilities for their experiments. The NRX and NRU reactor design and operating data of interest to the experimenters are also presented. (author)

  6. 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)

  7. 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

  8. NRU vessel repair and return to service: enhancing a Canadian R and D asset for the future

    Energy Technology Data Exchange (ETDEWEB)

    Cox, D.S.; Arnold, J.B.; Lee, J.K., E-mail: coxd@aecl.ca [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada)

    2013-07-01

    The National Research Universal (NRU) reactor was successfully returned to high power operation in 2010 August, after completing extensive inspections and repairs of the calandria vessel, in response to a small leak of heavy water that was discovered in 2009 May. The aluminum alloy vessel material had corroded from the outside surface over many years, and required application of weld build-up and plated weld repair at ten locations, executed by remote tooling deployed from inside the reactor vessel. Many specialized remotely operated tools were developed for inspection, sampling and repair operations. In parallel with the repair efforts, important maintenance activities were performed, enabled by the de-fuelled state with the heavy water drained from the vessel. Two annual inspection cycles have now been completed since the reactor was returned to high power operation, confirming the fitness of the vessel for continued operation. The NRU reactor is now entering its 56th year of operation and the current operating licence extends to 2016. Based on the outcome of a comprehensive Integrated Safety Review, AECL is continuing to implement major equipment upgrades and process improvements to support safe and reliable operation through 2021, for the benefit of Canadians and the world. (author)

  9. Monte Carlo applications to core-following of the National Research Universal reactor (NRU)

    International Nuclear Information System (INIS)

    Nguyen, T.S.; Wang, X.; Leung, T.

    2014-01-01

    Reactor code TRIAD, relying on a two-group neutron diffusion model, is currently used for core-following of NRU - to track reactor assembly locations and burnups. The Monte Carlo (MCNP or SERPENT) full-reactor models of NRU can be used to provide the core power distribution for calculating fuel burnups, with WIMS-AECL providing fuel depletion calculations. The MCNP/WIMS core-following results were in good agreement with the measured data, within the expected biases. The Monte Carlo methods, still very time-consuming, need to be able to run faster before they can replace TRIAD for timely support of NRU operations. (author)

  10. Current developments and future challenges in physics analyses of the NRU heavy water research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Nguyen, S.; Wilkin, B.; Leung, T., E-mail: nguyens@aecl.ca, E-mail: leungt@aecl.ca [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada)

    2011-07-01

    The National Research Universal (NRU) reactor is heavy water cooled and moderated, with on-power fueling capability. TRIAD, a 3D two-group diffusion code, is currently used for support of day-to-day NRU operations. Recently, an MCNP full reactor model of NRU has been developed for benchmarking TRIAD. While reactivity changes and flux and power distributions from both methods are in reasonably good agreement, MCNP appears to eliminate a k-eff bias in TRIAD. Beyond TRIAD's capability, MCNP enables the assessment of radiation in the NRU outer structure. Challenges include improving TRIAD accuracy and MCNP performance, as well as performing NRU core-following using MCNP. (author)

  11. NRX and NRU reactor research facilities and irradiation and examination charges

    International Nuclear Information System (INIS)

    1960-08-01

    This report details the irradiation and examination charges on the NRX and NRU reactors at the Chalk River Nuclear Labs. It describes the NRX and NRU research facilities available to external users. It describes the various experimental holes and loops available for research. It also outlines the method used to calculate the facilities charges and the procedure for applying to use the facilities as well as the billing procedures.

  12. Core management and reactor physics aspects of the conversion of the NRU reactor to LEU

    International Nuclear Information System (INIS)

    Atfield, M.D.

    1985-01-01

    Results of work done to assess the effects of converting the NRU reactor to LEU are presented. The effects are small, and the operational rules and safety analysis, appropriate to the HEU core, will still apply. (author)

  13. Design basis neutronics calculations for NRU-LOCA experiments

    International Nuclear Information System (INIS)

    Heaberlin, S.W.; Jenquin, U.P.; McNair, G.W.; Perry, R.T.; Trapp, T.J.; Zimmerman, M.G.

    1979-08-01

    The report describes the neutronics analysis for the LOCA simulation experiments in the NRU reactor. The experimental program will provide greater understanding of nuclear fuel assembly behavior during the heatup, reflood and quench sequence of a hypothetical LOCA. The decay heat and stored heat, which are the energy source in a LOCA will be simulated by fission heat provided by the NRU reactor. The reactor, the test and test operation are described

  14. Final safety and hazards analysis for the Battelle LOCA simulation tests in the NRU reactor

    International Nuclear Information System (INIS)

    Axford, D.J.; Martin, I.C.; McAuley, S.J.

    1981-04-01

    This is the final safety and hazards report for the proposed Battelle LOCA simulation tests in NRU. A brief description of equipment test design and operating procedure precedes a safety analysis and hazards review of the project. The hazards review addresses potential equipment failures as well as potential for a metal/water reaction and evaluates the consequences. The operation of the tests as proposed does not present an unacceptable risk to the NRU Reactor, CRNL personnel or members of the public. (author)

  15. Experiment operations plan for the MT-4 experiment in the NRU reactor

    International Nuclear Information System (INIS)

    Russcher, G.E.; Wilson, C.L.; Parchen, L.J.; Marshall, R.K.; Hesson, G.M.; Webb, B.J.; Freshley, M.D.

    1983-06-01

    A series of thermal-hydraulic and cladding materials deformation experiments were conducted using light-water reactor fuel bundles as part of the Pacific Northwest Laboratory Loss-of-Coolant Accident (LOCA) Simulation Program. This report is the formal operations plan for MT-4 - the fourth materials deformation experiment conducted in the National Research Universal (NRU) reactor, Chalk River, Ontario, Canada. A major objective of MT-4 was to simulate a pressurized water reactor LOCA that could induce fuel rod cladding deformation and rupture due to a short-term adiabatic transient and a peak fuel cladding temperature of 1200K (1700 0 F)

  16. New about research reactors

    International Nuclear Information System (INIS)

    Egorenkov, P.M.

    2001-01-01

    The multi-purpose research reactor MAPLE (Canada) and concept of new reactor MAPLE-CNF as will substitute the known Canadian research reactor NRU are described. New reactor will be used as contributor for investigations into materials, neutron beams and further developments for the CANDU type reactor. The Budapest research reactor (BRR) and its application after the last reconstruction are considered also [ru

  17. 235U Determination using In-Beam Delayed Neutron Counting Technique at the NRU Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Andrews, M. T. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Bentoumi, G. [Canadian Nuclear Labs., Chalk River, ON (Canada); Corcoran, E. C. [Royal Military College of Canada, Kingston, ON (United States); Dimayuga, I. [Canadian Nuclear Labs., Chalk River, ON (Canada); Kelly, D. G. [Royal Military College of Canada, Kingston, ON (United States); Li, L. [Canadian Nuclear Labs., Chalk River, ON (Canada); Sur, B. [Canadian Nuclear Labs., Chalk River, ON (Canada); Rogge, R. B. [Canadian Nuclear Labs., Chalk River, ON (Canada)

    2015-11-17

    This paper describes a collaborative effort that saw the Royal Military College of Canada (RMC)’s delayed neutron and gamma counting apparatus transported to Canadian Nuclear Laboratories (CNL) for use in the neutron beamline at the National Research Universal (NRU) reactor. Samples containing mg quantities of fissile material were re-interrogated, and their delayed neutron emissions measured. This collaboration offers significant advantages to previous delayed neutron research at both CNL and RMC. This paper details the determination of 235U content in enriched uranium via the assay of in-beam delayed neutron magnitudes and temporal behavior. 235U mass was determined with an average absolute error of ± 2.7 %. This error is lower than that obtained at RMCC for the assay of 235U content in aqueous solutions (3.6 %) using delayed neutron counting. Delayed neutron counting has been demonstrated to be a rapid, accurate, and precise method for special nuclear material detection and identification.

  18. L-Area STS MTR/NRU/NRX Grapple Assembly Closure Mechanics Review

    International Nuclear Information System (INIS)

    Huizenga, D. J.

    2016-01-01

    A review of the closure mechanics associated with the Shielded Transfer System (STS) MTR/NRU/NRX grapple assembly utilized at the Savannah River Site (SRS) was performed. This review was prompted by an operational event which occurred at the Canadian Nuclear Laboratories (CNL) utilizing a DTS-XL grapple assembly which is essentially identical to the STS MTR/NRU/NRX grapple assembly used at the SRS. The CNL operational event occurred when a NRU/NRX fuel basket containing spent nuclear fuel assemblies was inadvertently released by the DTS-XL grapple assembly during a transfer. The SM review of the STS MTR/NRU/NRX grapple assembly will examine the operational aspects of the STS and the engineered features of the STS which prevent such an event at the SRS. The design requirements for the STS NRU/NRX modifications and the overall layout of the STS are provided in other documents.

  19. Post-irradiation examination of Al-61 wt% U3Si fuel rods from the NRU reactor

    International Nuclear Information System (INIS)

    Sears, D.F.; Wang, N.

    1997-01-01

    This paper describes the post-irradiation examination of 4 intact low enrichment uranium (LEU) fuel rods from the national research universal (NRU) reactor at the Chalk River Laboratories of AECL. The rods were irradiated during the period 1993 through 1995, under typical driver fuel operating conditions in NRU, i.e., nominal D 2 O coolant inlet temperature 37E C, inlet pressure 654 kPa and mass flow 12.4 L/s. Irradiation exposures ranged from 147 to 251 full-power days, corresponding to 40 to 84 atom % 235 U burnup. The maximum rod power was ∼2 MW, with element linear power ratings up to 68 kW/m. Post-irradiation examinations, conducted in 1997, focused on optical metallography to measure cladding oxide thickness and fuel core and cladding microstructural examinations. The cladding oxide was approximately 24 : m thick at the mid-plane of fuel rods irradiated to 251 full-power days, with small areas up to 34 : m thick on the fins. The cladding retained significant ductility after irradiation, and its microstructure appeared unchanged. Fuel core diametral increases were small (up to 4%) and within the range previously observed on Al-61 wt% U 3 Si fuel irradiated in the NRU reactor. (author)

  20. NRU analysis support experiments performed in ZED-2

    International Nuclear Information System (INIS)

    Arbique, G.M.; French, P.M.

    1985-09-01

    A series of measurements have been performed in ZED-2 to investigate voiding in a simulated NRU loop site containing uniform and non-uniform UO 2 fuel strings. The objective of the measurements was to provide experimental data to validate NRU reactor physics codes. Using a simulated NRU loop site containing various UO 2 fuel strings, in a simulated NRU lattice in ZED-2, measurements were made of: a) reactivity effects, as measured by critical height changes, associated with the loop site and its contents, b) detailed and macroscopic flux shapes at the loop site and throughout the lattice, respectively, and c) Westcott spectral parameters. The report describes and presents the results of the experiments and is the second of a two part set of reports on this series of measurements. 6 refs

  1. Post-irradiation examination of A1-61 wt % U3Si fuel rods from the NRU reactor

    International Nuclear Information System (INIS)

    Sears, D.F.; Wang, N.

    1997-09-01

    This paper describes the post-irradiation examination of 4 intact low-enrichment uranium (LEU) fuel rods from the national research universal (NRU) reactor at the Chalk River Laboratories of AECL. The rods were irradiated during the period 1993 through 1995, under typical driver fuel operating conditions in NRU, i.e., nominal D 2 0 coolant inlet temperature 37 degrees C, inlet pressure 654 kPa and mass flow 12.4 L/s. Irradiation exposures ranged from 147 to 251 full-power days, corresponding to 40 to 84 atom % 235 U burnup. The maximum rod power was ∼2 MW, with element linear power ratings up to 68 kW/m. Post-irradiation examinations, conducted in 1997, focused on optical metallography to measure cladding oxide thickness and fuel core and cladding microstructural examinations. The cladding oxide was approximately 24 μm thick at the mid-plane of fuel rods irradiated to 251 full-power days, with small areas up to 34 μm thick on the fins. The cladding retained significant ductility after irradiation, and its microstructure appeared unchanged. Fuel core diametral increases were small (up to 4%) and within the range previously observed on A1-61 wt % U 3 Si fuel irradiated in the NRU reactor. (author)

  2. The conversion of NRU from HEU to LEU fuel

    International Nuclear Information System (INIS)

    Sears, D.F.; Atfield, M.D.; Kennedy, I.C.

    1990-01-01

    The program at Chalk River Nuclear Laboratories (CRNL) to develop and test low-enriched uranium fuel (LEU, 3 Si, USiAl, USi Al and U 3 Si 2 (U-3.96 wt% Si; U-3.5 wt% Si-1.5 wt% AL; U-3.2 wt%; Si-3 wt% Al; U-7.3 wt% Si, respectively). Fuel elements were fabricated with uranium loadings suitable for NRU, 3.15 gU/cm 3 , and for NRX, 4.5 gU/cm 3 , and were irradiated under normal fuel-operating conditions. Eight experimental irradiations involving 100 mini-elements and 84 full-length elements (7X12-element rods) were completed to qualify the LEU fuel and the fabrication technology. Post irradiation examinations confirmed that the performance of the LEU fuel, and that of a medium enrichment uranium (MEU, 45% U-235) alloy fuel tested as a back-up, was comparable to the HEU fuel. The uranium silicide dispersion fuel swelling was approximately linear up to burnups exceeding NRU's design terminal burnup (80 at%). NRU was partially converted to LEU fuel when the first 31 prototype fuel rods manufactured with industrial scale production equipment were installed in the reactor. The rods were loaded in NRU at a fuelling rate of about two rods per week over the period 1988 September to December. This partial LEU core (one third of a full NRU core) has allowed the reactor engineers and physicists to evaluate the bulk effects of the LEU conversion on NRU operations. As expected, the irradiation is proceeding without incident

  3. Coolant radiolysis studies in the high temperature, fuelled U-2 loop in the NRU reactor

    International Nuclear Information System (INIS)

    Elliot, A.J.; Stuart, C.R.

    2008-06-01

    An understanding of the radiolysis-induced chemistry in the coolant water of nuclear reactors is an important key to the understanding of materials integrity issues in reactor coolant systems. Significant materials and chemistry issues have emerged in Pressurized Water Reactors (PWR), Boiling Water Reactors (BWR) and CANDU reactors that have required a detailed understanding of the radiation chemistry of the coolant. For each reactor type, specific computer radiolysis models have been developed to gain insight into radiolysis processes and to make chemistry control adjustments to address the particular issue. In this respect, modelling the radiolysis chemistry has been successful enough to allow progress to be made. This report contains a description of the water radiolysis tests performed in the U-2 loop, NRU reactor in 1995, which measured the CHC under different physical conditions of the loop such as temperature, reactor power and steam quality. (author)

  4. 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)

  5. 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)

  6. ZED-2 experiments on the effect of a Co absorber rod on an NRU loop

    International Nuclear Information System (INIS)

    Arbique, G.M.; French, P.M.

    1983-02-01

    A series of experiments has been performed in ZED-2 to measure the perturbing effects of an NRU cobalt absorber rod on a simulated NRU loop site containing graded enrichment U0 2 fuel. The objective of the measurements was to provide data useful in validating NRU reactor physics codes. Using a simulated NRU lattice containing a simulated NRU loop site and an asymmetrically placed Co absorber rod, measurements were made of: (a) reactivity effects, as measured by critical height changes, associated with voiding the loop and stepped insertion of the Co absorber rod, (b) flux perturbations at the simulated loop site and throughout the lattice induced by the Co rod, (c) Westcott r√T/Tsub(o) values throughout the lattice

  7. 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)

  8. 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)

  9. Safety aspects of the emergency filtration system (EFS) for NRU reactor

    International Nuclear Information System (INIS)

    Hickey, D.L.; Lounsbury, R.I.

    1990-01-01

    A description of the NRU emergency filter system (EFS) is presented, including operation, testing and hazards. Operation of the NRU EFS reduces the dose to the thyroid for members of the public and site personnel by a factor of 100. The calculated thyroid doses for off-site and on-site locations for the current system configuration are 91 and 160 mSv, respectively. An unavailability analysis was performed on the control system which recognized subtle problems in the current system. Modifications to the system result in a system unavailability of 2.0 E-3. The thyroid risk analysis revealed that these improvements in system availability result in risk reduction by approximately a factor of three. Improvements beyond the availability analysis recommendations do not result in substantial risk benefit for members of the public or on-site personnel

  10. Analysis of the fast-neutron spectrum inside the experimental cavity of the NRU Mk4 FN rod

    International Nuclear Information System (INIS)

    Leung, T.C.

    1995-01-01

    The fast-neutron (FN) rods in the NRU reactor provide a facility to study the effects of irradiation on CANDU reactor materials. The Mark 4 (Mk4) FN rods use natural uranium and supply fast-neutrons for experiments on irradiation creep and growth, and corrosion, for pressure- and calandria-tube materials. The neutron fluxes above 1 MeV are up to 2.7x10 17 n.m -2 .s -1 . This paper describes a calculation of the fast-neutron spectrum inside the NRU Mk4 FN rod cavity. The calculation was performed using the WIMS-AECL code, which is a multi-group transport code with two dimensional capabilities using the collision-probability method. Results for the fast-neutron spectrum above 1 MeV are presented in nine groups. The analysis confirms that the spectrum in the fast-neutron irradiation facility in NRU is representative of the actual irradiation spectrum for fast-neutron damage in a CANDU reactor. The effects of changes in specimen holder size, temperature, coolant density and fuel burnup on the fast neutron spectrum are also presented. (author). 9 refs., 3 tabs., 4 figs

  11. Reduced enrichment fuels for Canadian research reactors - Fabrication and performance

    Energy Technology Data Exchange (ETDEWEB)

    Wood, J C; Foo, M T; Berthiaume, L C; Herbert, L N; Schaefer, J D; Hawley, D [Atomic Energy of Canada Limited, Chalk River Nuclear Laboratories, Chalk River, ON KOJ 1JO (Canada)

    1985-07-01

    Our facilities have been upgraded to manufacture fuel rods comprising dispersions of U{sub 3}Si in aluminum, to complement the dispersions of U{sub 3}Si alloyed with 1.5 and 3.0 wt% Al fabricated and tested previously. Further advances have been made in process optimization particularly in core extrusion where production rate has been doubled while maintaining high quality standards. Our mini-element irradiations of Al-61.5 wt% (U,3.5 wt% Si, 1.5 wt% Al) and Al-62.4 wt% (U,3.2 wt% Si, 30 wt% Al) have been completed successfully up to the terminal burnup of 93 atomic percent. Fuel core swelling remained marginally below 1% per 10 atomic percent burnup over the whole irradiation. Also mini-elements containing Al-72.4 wt% USiAl and Al-73.4 wt% USi*Al have been irradiated to 82 atomic percent burnup, their swelling rate marginally exceeding 1% per 10 atomic percent burnup. Three full-size 12-element NRU assemblies containing Al-62.4 wt% USi*Al have been fabricated and installed in the NRU reactor where they have performed normally without problems. The cores for four more full-size 12-element NRU assemblies containing Al-61.0 wt% U{sub 3}Si have been manufactured. (author)

  12. Reduced enrichment fuels for Canadian research reactors - Fabrication and performance

    International Nuclear Information System (INIS)

    Wood, J.C.; Foo, M.T.; Berthiaume, L.C.; Herbert, L.N.; Schaefer, J.D.; Hawley, D.

    1985-01-01

    Our facilities have been upgraded to manufacture fuel rods comprising dispersions of U 3 Si in aluminum, to complement the dispersions of U 3 Si alloyed with 1.5 and 3.0 wt% Al fabricated and tested previously. Further advances have been made in process optimization particularly in core extrusion where production rate has been doubled while maintaining high quality standards. Our mini-element irradiations of Al-61.5 wt% (U,3.5 wt% Si, 1.5 wt% Al) and Al-62.4 wt% (U,3.2 wt% Si, 30 wt% Al) have been completed successfully up to the terminal burnup of 93 atomic percent. Fuel core swelling remained marginally below 1% per 10 atomic percent burnup over the whole irradiation. Also mini-elements containing Al-72.4 wt% USiAl and Al-73.4 wt% USi*Al have been irradiated to 82 atomic percent burnup, their swelling rate marginally exceeding 1% per 10 atomic percent burnup. Three full-size 12-element NRU assemblies containing Al-62.4 wt% USi*Al have been fabricated and installed in the NRU reactor where they have performed normally without problems. The cores for four more full-size 12-element NRU assemblies containing Al-61.0 wt% U 3 Si have been manufactured. (author)

  13. Long-term performance of the CANDU-type of vanadium self-powered neutron detectors in NRU

    Energy Technology Data Exchange (ETDEWEB)

    Leung, T.C. [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada)]. E-mail: leungt@aecl.ca

    2007-07-01

    The CANDU-type of in-core vanadium self-powered neutron flux detectors have been installed in NRU to monitor the axial neutron flux distributions adjacent to the loop fuel test sites since 1996. This paper describes how the thermal neutron fluxes were measured at two monitoring sites, and presents a method of correcting the vanadium burn-up effect, which can be up to 2 to 3% per year, depending on the detector locations in the reactor. It also presents the results of measurements from neutron flux detectors that have operated for over eight-years in NRU. There is good agreement between the measured and simulated neutron fluxes, to within {+-} 6.5%, and the long-term performance of the CANDU-type of vanadium neutron flux detectors in NRU is satisfactory. (author)

  14. Lessons learned from the NRU vessel leak repair and return to service projects

    International Nuclear Information System (INIS)

    Heeney, P.; Turcotte, J.

    2011-01-01

    In May 2009 the National Research Universal (NRU) reactor was shut down due to a small leak detected from the reactor vessel into the annulus surrounding the reactor. What ensued was a challenging, yet successful, 15 month long Repair and Return to Service Outage. This Repair and Return to Service Outage presented many first-of-a-kind challenges that provide learning opportunities which have been incorporated into subsequent planned outages. These lessons learned are invaluable tools to be used in the planning and execution of future outages. Following the repair of the NRU vessel, AECL was required to conduct annual inspections of the vessel wall. These inspections require an annual Extended Outage (up to 4 weeks in length). A planned Extended Outage was conducted in May/June 2011 and provided an opportunity to implement some of the lessons learned during the Repair and Return to Service Outage. Lessons learned from that Extended Outage have been incorporated in the subsequent monthly maintenance outages, with lessons learned sessions being held after each outage to ensure that the execution of outages is constantly improving. (author)

  15. Application of plant life management program and experience at NRU

    International Nuclear Information System (INIS)

    Nickerson, J.; Dam, R.; Arnold, J.; See Hoye, D.

    2004-01-01

    The National Research Universal (NRU) reactor has seen extensive and excellent service since going into operation in 1957. During that time, significant investments in upgrading and improving the facility have been implemented. Recently, as part of the NRU Licenseability Extension (LE) program, AECL has developed a Plant Life Management (PLiM) program to support planned operation to at least 2012. The objective of the PLiM program is to systematically assess the various aging related degradation mechanisms in order to evaluate both current condition and the potential for further extending service life. Another objective is to identify the associated maintenance, surveillance and inspection strategy for service life extension of important Structures, Systems, and Components (SSCs). The strategy uses approaches that build on AECL's PLiM/PLEx experience at CANDU plants, but also utilizes previous Age Management and refurbishment work performed at NRU. The program is multi-faceted, systematic and integrated, and involves the facility operations organization in the assessment process. The PLiM program has used a number of pilot studies in the initial stages to test out PLiM procedures, gain experience with the various aging assessment techniques and enhance effectiveness of interfaces between the aging assessment team and the facility staff. The aging assessment process begins with the screening and prioritization of the facility SSCs. Selection of the appropriate assessment technique is based on priority and component type. Life and condition assessment techniques used at other plants have been adapted to NRU and performed on important components and structures. For important systems, a combination of condition assessment and systematic maintenance assessment techniques are being used. Detailed PLiM procedures have been developed and are in trial use in pilot studies. These procedures are currently being updated with the experience gained during the pilot studies. In

  16. Information infrastructure development in NRU «MPEI»

    Directory of Open Access Journals (Sweden)

    E. G. Gridina

    2016-01-01

    Full Text Available The article describes the work on support and development of information infrastructure NRU «MPEI». Information infrastructure have different approaches to the defi nition. The authors defi ne the information infrastructure as a set of basic information services, computing, storage and data transmission systems that provide user access to information resources. New conditions dictate new approaches to building the education system in general and the educational process in each educational institution. NRU «MPEI» working to create a modern information infrastructure, including automated control systems, information resources and services, modular systems disciplines. This article describes the requirements for a modern information infrastructure of the NRU «MPEI», that provides students and teachers with the necessary services. Information infrastructure includes a set of software and hardware to ensure interaction between the participants of the educational process. All services and NRU «MPEI» system included in the unifi ed information educational environment (UIEE. Architecture UIEE NRU «MPEI» is displayed in the article. UIEE NRU «MPEI» is deployed on the basis of information network NRU «MPEI» and enables a comprehensive optimization of university management in various areas. Information and Computing Center supporting information and computer network NRU «MPEI», bought more than 4800 licenses in 43 different license versions of the software manufacturers. The server segment information network NRU «MPEI» contains a complex infrastructure and application servers for processing and storing information.The segment there are 20 high-performance server and storage system capacity of over 30 TB. In the server segment deployed complex systems to meet the needs in the various fi elds of activity NRU «MPEI», and the educational system to support the economic , scientifi c and human complex. Currently, ICC also pays great

  17. Pre-test prediction and post-test analysis of PWR fuel rod ballooning in the MT-3 in-pile LOCA simulation experiment in the NRU reactor

    International Nuclear Information System (INIS)

    Donaldson, A.T.; Horwood, R.A.; Healey, T.

    1983-01-01

    The USNRC and the UKAEA have jointly funded a series of in-pile LOCA simulation experiments in the Canadian NRU reactor in order to secure further information on the thermal hydraulic and clad deformation response of PWR fuel rod bundles. Test MT-3 in the series was performed using reflood rate and rod internal pressure conditions specified by the UK nuclear industry. The parameters were selected to ensure the development of a near-isothermal clad temperature history during which zircaloy was required to balloon and rupture near the alpha-alpha/beta phase transition. Specification of the reflood rate conditions was assisted by the performance of a precursor test on an unpressurised rod bundle and by complementary application of appropriate thermal hydraulic analyses. Identification of the rod internal pressure needed to cause ballooning and rupture was achieved using a creep deformation model, BALLOON, in conjunction with the clad thermal history defined by the prior thermal hydraulic test. This paper presents the basis of the BALLOON analysis and describes its application in calculating the fill gas pressure for rods MT-3, their axial ballooning profile and the clad temperature at peak radial strain elevations. (author)

  18. 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

  19. The development of lower enrichment fuels for Canadian research reactors

    Energy Technology Data Exchange (ETDEWEB)

    Feraday, M A; Belanger, L; Grolway, C M [AECL, Atomic Energy of Canada Limited, Chalk River, ON (Canada); Foo, M T [CRNL, Combustion Engineering Superheater Ltd., Moncton, NB (Canada)

    1983-08-01

    As part of the world wide move to proliferation resistant fuels, new fuels which use reduced enrichment uranium are being developed for use in the NRX and NRU reactors. A fuel consisting of particles of a USiAl alloy dispersed in an Al matrix has been selected for development along with Al-37 wt% U alloy and Al-U{sub 3}O{sub 8} cermet as backup fuels. This report outlines the progress made in the development of the Al-USiAl and Al-37 wt% U. Results show that good quality extruded rods containing either fuel can be made with techniques similar to those used to fabricate the current NRX and NRU fuels. However, the new fuels will be more expensive to make. Although the oxidation behaviour of the Al-USiAl is not as good as that of the Al-U alloys, its corrosion behaviour in high temperature water does not seem much worse. The oxidation and aqueous corrosion of A-37 wt% U are not much different from those of the Al-U alloys currently used. (author)

  20. Manufacture of components for Canadian reactor programs

    International Nuclear Information System (INIS)

    Perry, L.P.

    Design features, especially those relating to calandrias, are pointed out for many CANDU-type reactors and the Taiwan research reactor. The special requirements shouldered by the Canadian suppliers of heavy reactor components are analyzed. (E.C.B.)

  1. Post-irradiation examination of prototype Al-64 wt% U3Si2 fuel rods from NRU

    International Nuclear Information System (INIS)

    Sears, D.F.; Primeau, M.F.; Buchanan, C.; Rose, D.

    1997-01-01

    Three prototype fuel rods containing Al-64 wt% U 3 Si 2 (3.15 gU/cm 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 3 Si fuel fabrication at Chalk River Laboratories, and special equipment developed for U 3 Si 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 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

  2. Status of LEU fuel development and conversion of NRU

    International Nuclear Information System (INIS)

    Sears, D.F.; Herbert, L.N.; Vaillancourt, K.D.

    1989-11-01

    The status of the low-enrichment uranium (LEU) fuel development and NRU conversion program at Chalk River Nuclear Laboratories is reviewed. Construction of a new fuel fabrication facility is essentially completed and installation of LEW fuel manufacturing equipment has begun. The irradiation of 31 prototype Al-61 wt% U 3 Si dispersion fuel rods, approximately one third of a full NRU core, is continuing without incident. Recent post-irradiation examination of spent fuel rods revealed that the prototype LEU fuel achieved the design burnup (80 at%) in excellent condition, confirming that the Al-U 3 Si 2 dispersion fuel to complement out Al-U 3 Si capability. Three full-size NRU rods containing Al-U 3 Si 2 dispersion fuel have been fabricated for a qualification irradiation in NRU. Post-irradiation examinations of mini-elements containing Al-U 3 Si 2 fuel revealed that the U 3 Si 2 behaved similarly to U 3 Si 2 fuel revealed that the U 3 Si 2 particles and the aluminum matrix, and fission gas bubbles up to 10 μm in diameter, could be seen in the particles after 60 at% and 80 at% burnup. The mini-elements contained a variety of silicide particle sizes; however, no significant swelling dependence on particle size distribution was observed

  3. The evolution of Canadian research reactors, 1942 to 1992

    International Nuclear Information System (INIS)

    Lidstone, R.F.

    1993-01-01

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

  4. 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)

  5. Materials research with neutron beams from a research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Root, J.; Banks, D. [Canadian Neutron Beam Centre, Chalk River Laboratories, Chalk River, Ontario (Canada)

    2015-03-15

    Because of the unique ways that neutrons interact with matter, neutron beams from a research reactor can reveal knowledge about materials that cannot be obtained as easily with other scientific methods. Neutron beams are suitable for imaging methods (radiography or tomography), for scattering methods (diffraction, spectroscopy, and reflectometry) and for other possibilities. Neutron-beam methods are applied by students and researchers from academia, industry and government to support their materials research programs in several disciplines: physics, chemistry, materials science and life science. The arising knowledge about materials has been applied to advance technologies that appear in everyday life: transportation, communication, energy, environment and health. This paper illustrates the broad spectrum of materials research with neutron beams, by presenting examples from the Canadian Neutron Beam Centre at the NRU research reactor in Chalk River. (author)

  6. The fabrication and performance of Canadian silicide dispersion fuel for test reactors

    International Nuclear Information System (INIS)

    Sears, D.F.; Wood, J.C.; Berthiaume, L.C.; Herbert, L.N.; Schaefer, J.D.

    1985-01-01

    Fuel fabrication effort is now concentrated on the commissioning of large-scale process equipment, defining product specifications, developing a quality assurance plan, and setting up a mini-computer material accountancy system. In the irradiation testing program, full-size NRU assemblies containing 20% enriched silicide dispersion fuel have been Irradiated successfully to burnups in the range 65-80 atomic percent. Irradiations have also been conducted on mini-elements having 1.2 mm diameter holes In their mid-sections, some drilled before irradiation and others after irradiation to 22-83 atomic percent burnup. Uranium was lost to the coolant in direct proportion to the surface area of exposed core material. Pre-irradiation in the intact condition appeared to reduce in-reactor corrosion. Fuel cores developed for the NRU reactor are dimensionally very stable, swelling by only 6-8% at the very high burnup of 93 atomic percent. Two important factors contributing to this good performance are cylindrical clad restraint and coarse silicide particles. Thermal ramping tests were conducted on irradiated silicide aspersion fuels. Small segments of fuel cores released 85 Kr starting at about 520 deg. C and peaking at about 680 deg C. After a holding period of 1 hour at 720 deg. C a secondary 85 Kr peak occurred during cooling (at about 330 deg. C) probably due to thermal contraction cracking. Whole mini-elements irradiated to 93 atomic percent burnup were also ramped thermally, with encouraging results. After about 0.25 h at 530 deg. C the aluminum cladding developed very localized small blisters, some with penetrating pin-hole cracks preventing gross pillowing or ballooning. (author)

  7. The fabrication and performance of Canadian silicide dispersion fuel for test reactors

    Energy Technology Data Exchange (ETDEWEB)

    Sears, D F; Wood, J C; Berthiaume, L C; Herbert, L N; Schaefer, J D

    1985-07-01

    Fuel fabrication effort is now concentrated on the commissioning of large-scale process equipment, defining product specifications, developing a quality assurance plan, and setting up a mini-computer material accountancy system. In the irradiation testing program, full-size NRU assemblies containing 20% enriched silicide dispersion fuel have been Irradiated successfully to burnups in the range 65-80 atomic percent. Irradiations have also been conducted on mini-elements having 1.2 mm diameter holes In their mid-sections, some drilled before irradiation and others after irradiation to 22-83 atomic percent burnup. Uranium was lost to the coolant in direct proportion to the surface area of exposed core material. Pre-irradiation in the intact condition appeared to reduce in-reactor corrosion. Fuel cores developed for the NRU reactor are dimensionally very stable, swelling by only 6-8% at the very high burnup of 93 atomic percent. Two important factors contributing to this good performance are cylindrical clad restraint and coarse silicide particles. Thermal ramping tests were conducted on irradiated silicide aspersion fuels. Small segments of fuel cores released {sup 85}Kr starting at about 520 deg. C and peaking at about 680 deg C. After a holding period of 1 hour at 720 deg. C a secondary {sup 85}Kr peak occurred during cooling (at about 330 deg. C) probably due to thermal contraction cracking. Whole mini-elements irradiated to 93 atomic percent burnup were also ramped thermally, with encouraging results. After about 0.25 h at 530 deg. C the aluminum cladding developed very localized small blisters, some with penetrating pin-hole cracks preventing gross pillowing or ballooning. (author)

  8. 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.

  9. IFPE/MT4-MT6A-LOCA, Large-break LOCA in-reactor fuel bundle materials tests at NRU

    International Nuclear Information System (INIS)

    Cunningham, Mitchel E.; Turnbull, J.A.

    2003-01-01

    Description - Objectives - Results: The U.S. Nuclear Regulatory Commission (NRC) conducted a series of thermal-hydraulic and cladding mechanical deformation tests in the National Research Universal (NRU) reactor at the Chalk River National Laboratory in Canada. The objective of these tests was to perform simulated loss-of-coolant-accident (LOCA) experiments using full-length light-water reactor fuel rods to study mechanical deformation, flow blockage, and coolability. Three phases of a LOCA (i.e., heat-up, reflood, and quench) were performed in situ using nuclear fissioning to simulate the low-level decay power during a LOCA after shutdown. All tests used PWR-type, non-irradiated fuel rods. Provided here is information on two materials tests, MT-6A and MT-4, which PNNL considers the better characterized for the purposes of setting up computer cases. The NRU reactor is a heterogeneous, thermal, tank-type research reactor. It has a power level of 135 MWth and is heavy-water moderated and cooled. The coolant has an inlet temperature of 310 K at a pressure of 0.65 MPa. The MT tests were conducted in a specially designed test train to supply the specified coolant conditions of flowing steam, stagnant steam, and then reflood. Typical instrumentation for the MT tests included fuel centerline thermocouples, cladding inner surface thermocouples, cladding outer surface thermocouples, rod internal gas pressure transducers or pressure switches, coolant channel steam probes, and self-powered neutron detectors. This instrumentation allowed for determining rupture times and cladding temperature. The test rods for the LOCA cases in the NRU reactor were irradiated in flowing steam prior to the transient, stagnant steam during the transient and prior to reflood, and then reflood conditions to complete the transient. Both cladding inner surface and outer surface temperatures were measured, in addition to coolant temperatures. However, only cladding inner surface temperatures were

  10. Modelling of a Naphtha Recovery Unit (NRU with Implications for Process Optimization

    Directory of Open Access Journals (Sweden)

    Jiawei Du

    2018-06-01

    Full Text Available The naphtha recovery unit (NRU is an integral part of the processes used in the oil sands industry for bitumen extraction. The principle role of the NRU is to recover naphtha from the tailings for reuse in this process. This process is energy-intensive, and environmental guidelines for naphtha recovery must be met. Steady-state models for the NRU system are developed in this paper using two different approaches. The first approach is a statistical, data-based modelling approach where linear regression models have been developed using Minitab® from plant data collected during a performance test. The second approach involves the development of a first-principles model in Aspen Plus® based on the NRU process flow diagram. A novel refinement to this latter model, called “withdraw and remix”, is proposed based on comparing actual plant data to model predictions around the two units used to separate water and naphtha. The models developed in this paper suggest some interesting ideas for the further optimization of the process, in that it may be possible to achieve the required naphtha recovery using less energy. More plant tests are required to validate these ideas.

  11. A history of ZED-2

    International Nuclear Information System (INIS)

    Jones, R.

    2010-01-01

    The ZED-2 Reactor at Chalk River Laboratories was 50 years old this fall. First criticality occurred in September 1960. ZED-2 is perhaps not very well known in the Canadian Nuclear Industry, certainly not as well known as the various CANDU power reactors or the research reactors NRU and NRX. Part of the reason for this I suspect is that when casually judging the importance of reactors the first parameters that spring to mind are power generated (for power reactors) or neutron flux (for research reactors), bigger being 'better in both cases. By these standards ZED-2 does indeed appear puny: the maximum allowed power is 200W and the corresponding flux about 10 8 to 10 9 neutrons cm -2 s -1 , both numbers being about a factor of 500,000 smaller than the corresponding values for NRU. So, what is it all about? How is it that such an apparently insignificant reactor has operated for 50 years?, longer than any other Canadian reactor except NRU and the McMaster Reactor. What is it used for? What contributions has it made to the Canadian industry? Maybe one might also ask for how long is it going to continue? Well, that's what this talk is about, although I think I will leave the final question to wiser heads than mine. ZED-2 is a descendant of famous progenitors: starting with Enrico Farm's first critical pile of graphite and uranium (created at the University of Chicago in 1942) through Canada's ZEEP (first reactor to go critical outside the USA) that went critical in 1945. These early critical facilities were first about proof of principle that a self sustaining nuclear chain reaction could be established and controlled in a reasonable sized facility and second, in the longer term, developing understanding of the underlying reactor physics and the development of theories and methods to accurately predict the important properties of critical assemblies generally. (author)

  12. Severe accident considerations in Canadian nuclear power reactors

    International Nuclear Information System (INIS)

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

    1990-08-01

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

  13. Power flattening and reactivity suppression strategies for the Canadian supercritical water reactor concept

    International Nuclear Information System (INIS)

    McDonald, M.; Colton, A.; Pencer, J.

    2015-01-01

    The Canadian supercritical water-cooled reactor (SCWR) is a conceptual heavy water moderated, supercritical light water cooled pressure tube reactor. In contrast to current heavy water power reactors, the Canadian SCWR will be a batch fuelled reactor. Associated with batch fuelling is a large beginning-of-cycle excess reactivity. Furthermore, radial power peaking arising as a consequence of batch refuelling must be mitigated in some way. In this paper, burnable neutron absorber (BNA) added to fuel and absorbing rods inserted into the core are considered for reactivity management and power flattening. A combination of approaches appears adequate to reduce the core radial power peaking, while also providing reactivity suppression. (author)

  14. 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

  15. CRNL research reactor retrofit Emergency Filtration System

    International Nuclear Information System (INIS)

    Philippi, H.M.

    1990-01-01

    This paper presents a brief history of NRX and NRU research reactor effluent air treatment systems before describing the selection and design of an appropriate retrofit Emergency Filtration System (EFS) to serve these reactors and the future MX-10 isotope production reactor. The conceptual design of the EFS began in 1984. A standby concrete shielding filter-adsorber system, sized to serve the reactor with the largest exhaust flow, was selected. The standby system, bypassed under normal operating conditions, is equipped with normal exhaust stream shutoff and diversion valves to be activated manually when an emergency is anticipated, or automatically when emergency levels of gamma radiation are detected in the exhaust stream. The first phase of the EFS installation, that is the construction of the EFS and the connection of NRU to the system, was completed in 1987. The second phase of construction, which includes the connection of NRX and provisions for the future connection of MX-10, is to be completed in 1990

  16. The evolution of Canadian research reactors: 1942 to 1992

    International Nuclear Information System (INIS)

    Lidstone, R.F.

    1992-01-01

    Research reactors have played a central role in the development of the Canadian nuclear program. Major benefits arising from the operation of Canada's research reactors include the development and demonstration of Canada deuterium uranium (CANDU) power reactors and the creation of an international business based on the production of medical and industrial radioisotopes. Insofar as practicable, nuclear engineers have based each design on the evolutionary development of appropriate technology for Canada. This approach has resulted in several generations of multipurpose reactors with a common heritage of neutronic efficiency. A focus on neutronic efficiency stemmed from the incentive for direct use of Canada's abundant uranium resources; the desired reliance on natural-uranium fuels promoted interest in efficient moderators, especially heavy water, and structural materials with a low affinity for absorbing neutrons, such as aluminum and zirconium alloys

  17. A Canadian isotope success story

    International Nuclear Information System (INIS)

    Malkoske, G.

    1997-01-01

    This paper provides some historical background on the commercial production of radioisotopes in Canada, and the evolution of the present vendor, MDS Nordion. The chief isotopes are molybdenum 99, iodine 131, and cobalt 60. Cobalt 60 for medical sterilization and irradiation is considered to be a significant growing market. Food irradiation is believed to be a big marketing opportunity, although attempts to popularize it have so far met with limited success. Candu reactors supply the bulk of the world's 60 Co supply. Eighty percent of the world's 99 Mo supply for medical imaging comes from Canada, and is at present produced in NRU Reactor, which is to be replaced by two Maple reactors coming into production in 1999 and 2000

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

    International Nuclear Information System (INIS)

    James, R.A.

    1996-01-01

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

  19. Status of LEU fuel development and conversion of NRU

    International Nuclear Information System (INIS)

    Sears, D.F.; Herbert, L.N.; Vaillancourt, K.D.

    1991-01-01

    This paper reviews the status of the LEU conversion program and the progress made in the fuel development program over the last year. The results from post-irradiation examinations of prototype NRU fuel rods containing Al-U 3 Si dispersion fuel, and of mini-elements containing Al-U 3 Si 2 dispersion fuel, are presented. (orig.)

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

    International Nuclear Information System (INIS)

    Vickerd, Meggan; Kenny, Stephen

    2016-01-01

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

  1. Calculation of fast neutron flux in reactor pressure tubes and experimental facilities

    Energy Technology Data Exchange (ETDEWEB)

    Barnett, P. C. [Canadian General Electric (Canada)

    1968-07-15

    The computer program EPITHET was used to calculate the fast neutron flux (>1 MeV) in several reactor pressure tubes and experimental facilities in order to compare the fast neutron flux in the different cases and to provide a self-consistent set of flux values which may be used to relate creep strain to fast neutron flux . The facilities considered are shown below together with the calculated fast neutron flux (>1 MeV). Fast flux 10{sup 13} n/cm{sup 2}s: NPD 1.14, Douglas Point 2.66, Pickering 2.89, Gentilly 2.35, SGHWR 3.65, NRU U-1 and U-2 3.25'' pressure tube - 19 element fuel 3.05, NRU U-1 and U-2 4.07'' pressure tube - 28 element fuel 3.18, NRU U-1 and U-2 4.07'' pressure tube - 18 element fuel 2.90, NRX X-5 0.88, PRTR Mk I fuel 2.81, PRTR HPD fuel 3.52, WR-1 2.73, Mk IV creep machine (NRX) 0.85, Mk VI creep machine (NRU) 2.04, Biaxial creep insert (NRU U-49) 2.61.

  2. Planning a new research reactor for AECL: The MAPLE-MTR concept

    International Nuclear Information System (INIS)

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

    1992-01-01

    AECL Research is assessing its needs and options for future irradiation research facilities. A planning team has been assembled to identify the irradiation requirements for AECL's research programs and compile options for satisfying the irradiation requirements. The planning team is formulating a set of criteria to evaluate the options and will recommend a plan for developing an appropriate research facility. Developing the MAPLE Materials Test Reactor (MAPLE-MTR) concept to satisfy AECL's irradiation requirements is one option under consideration by the planning team. AECL is undertaking this planning phase because the NRU reactor is 35 years old and many components are nearing the end of their design life. This reactor has been a versatile facility for proof testing CANDU components and fuel designs because the CANDU irradiation environment was simulated quite well. However, the CANDU design has matured and the irradiation requirements have changed. Future research programs will emphasize testing CANDU components near or beyond their design limits. To provide these irradiation conditions, the NRU reactor needs to be upgraded. Upgrading and refurbishing the NRU reactor is being considered, but the potentially large costs and regulatory uncertainties make this option very challenging. AECL is also developing the MAPLE-MTR concept as a potential replacement for the NRU reactor. The MAPLE-MTR concept starts from the recent MAPLE-X10 design and licensing experience and adapts this technology to satisfy the primary irradiation requirements of AECL's research programs. This approach should enable AECL to minimize the need for major advances in nuclear technology (e.g., fuel design, heat transfer). The preliminary considerations for developing the MAPLE-MTR concept are presented in this report. A summary of AECL's research programs is presented along with their irradiation requirements. This is followed by a description of safety criteria that need to be taken into

  3. 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)

  4. 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)

  5. Physical aspects of the Canadian generation IV supercritical water-cooled pressure tube reactor plant design

    Energy Technology Data Exchange (ETDEWEB)

    Gaudet, M.; Yetisir, M.; Haque, Z. [Atomic Energy of Canada Limited, Chalk River, ON (Canada)

    2014-07-01

    The form of the containment building is a function of the requirements imposed by various systems. In order to provide sufficient driving force for naturally-circulated emergency cooling systems, as well as providing a gravity-driven core flooding pool function, the Canadian SCWR reactor design relies on elevation differences between the reactor and the safety systems. These elevation differences, the required cooling pool volumes and the optimum layout of safety-related piping are major factors influencing the plant design. As a defence-in-depth, the containment building and safety systems also provide successive barriers to the unplanned release of radioactive materials, while providing a path for heat flow to the ultimate heat sink, the atmosphere. Access to the reactor for refuelling is from the top of the reactor, with water used as shielding during the refuelling operations. The accessibility to the reactor and protection of the environment are additional factors influencing the plant design. This paper describes the physical implementation of the major systems of the Canadian SCWR within the reactor building, and the position of major plant services relative to the reactor building. (author)

  6. Control of Canadian once-through direct cycle supercritical water-cooled reactors

    International Nuclear Information System (INIS)

    Sun, Peiwei; Wang, Baosheng; Zhang, Jianmin; Su, Guanghui

    2015-01-01

    Highlights: • Dynamic characteristics of Canadian SCWR are analyzed. • Hybrid feedforward and feedback control is adopted to deal with cross-coupling. • Gain scheduling control with smooth weight is applied to deal with nonlinearity. • It demonstrates through simulation that the control requirements are satisfied. - Abstract: Canadian supercritical water-cooled reactor (SCWR) can be modelled as a Multiple-input Multiple-output (MIMO) system. It has a high power-to-flow ratio, strong cross-coupling and high degree of nonlinearity in its dynamic characteristics. Among the outputs, the steam temperature is strongly affected by the reactor power and the most challenging to control. It is difficult to adopt a traditional control system design methodology to obtain a control system with satisfactory performance. In this paper, feedforward control is applied to reduce the effect on steam temperature from the reactor power. Single-input Single-output (SISO) feedback controllers are synthesized in the frequency domain. Using the feedforward controller, the steam temperature variation due to disturbances at the reactor power has been significantly suppressed. The control system can effectively maintain the overall system stability and regulate the plant around a specified operating condition. To deal with the nonlinearities, gain scheduling control strategy is adopted. Different sets of controllers combined by smooth weight functions are used for the plant at different load conditions. The proposed control strategies have been evaluated under various operating scenarios. Simulation results show that satisfactory performance can successfully achieved by the designed control system

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

    International Nuclear Information System (INIS)

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

    2012-01-01

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

  8. The Canadian development program for conditioning CANDU reactor wastes for disposal

    International Nuclear Information System (INIS)

    Charlesworth, D.H.; Bourns, W.T.; Buckley, L.P.

    1978-07-01

    Currently, radioactive wastes arising from the operation of Canadian nuclear reactors are placed in interim storage in concrete containment structures except for gaseous and liquid wastes containing small amounts of radioactivity which are dispersed. With the objective of replacing storage by permanent disposal, a program is underway to develop and demonstrate an integrated process for converting all reactor wastes to a stable, leach-resistant form which will immobilize the radionuclides in the waste repository. The major tool for this development is a Waste Treatment Centre, now being constructed at Chalk River Nuclear Laboratories, which will combine reverse-osmosis, incineration, evaporation and bituminizing processes. (author)

  9. 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

  10. 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

  11. Comparison of computer codes (CE-THERM, FRAP-T5, GT3-FLECHT, and TRUMP-FLECHT) with data from the NRU-LOCA thermal hydraulic tests

    International Nuclear Information System (INIS)

    Mohr, C.L.; Rausch, W.N.; Hesson, G.M.

    1981-07-01

    The LOCA Simulation Program in the NRU reactor is the first set of experiments to provide data on the behavior of full-length, nuclear-heated PWR fuel bundles during the heatup, reflood, and quench phases of a loss-of-coolant accident (LOCA). This paper compares the temperature time histories of 4 experimental test cases with 4 computer codes: CE-THERM, FRAP-T5, GT3-FLECHT, and TRUMP-FLECHT. The preliminary comparisons between prediction and experiment show that the state-of-the art fuel codes have large uncertainties and are not necessarily conservative in predicting peak temperatures, turn around times, and bundle quench times

  12. Canadian supercritical water reactor modeling using G4STORK

    International Nuclear Information System (INIS)

    Ford, W.; Buijs, A.

    2015-01-01

    The Canadian Supercritical Water Reactor design was simulated using G4STORK. The results showed the expected trends but the determined Keff of 1.253±0.001 with a Coolant Void Reactivity (CVR) of -25mk differed greatly from the results achieved using MCNP of Keff=1.2914 and a CVR of -14mk. This discrepancy is partly due to the different data libraries used and the mixing of different temperature libraries in MCNP, but is also likely due to a difference in the physics methodology. Work is ongoing to further clarify reasons for discrepancies and improve the efficiency of the simulation. (author)

  13. Canadian supercritical water reactor modeling using G4STORK

    Energy Technology Data Exchange (ETDEWEB)

    Ford, W.; Buijs, A. [McMaster University, Hamilton, ON (Canada)

    2015-07-01

    The Canadian Supercritical Water Reactor design was simulated using G4STORK. The results showed the expected trends but the determined Keff of 1.253±0.001 with a Coolant Void Reactivity (CVR) of -25mk differed greatly from the results achieved using MCNP of Keff=1.2914 and a CVR of -14mk. This discrepancy is partly due to the different data libraries used and the mixing of different temperature libraries in MCNP, but is also likely due to a difference in the physics methodology. Work is ongoing to further clarify reasons for discrepancies and improve the efficiency of the simulation. (author)

  14. Conference summaries of the Canadian Nuclear Association 30. annual conference, and the Canadian Nuclear Society 11. annual conference

    International Nuclear Information System (INIS)

    1990-01-01

    This volume contains conference summaries for the 30. annual conference of the Canadian Nuclear Association, and the 11. annual conference of the Canadian Nuclear Society. Topics of discussion include: energy needs and challenges facing the Canadian nuclear industry; the environment and nuclear power; the problems of maintaining and developing industrial capacity; the challenges of the 1990's; programmes and issues for the 1990's; thermalhydraulics; reactor physics and fuel management; nuclear safety; small reactors; fuel behaviour; energy production and the environment; computer applications; nuclear systems; fusion; materials handling; and, reactor components

  15. 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.

  16. Transient fission product release during reactor shutdown and startup

    International Nuclear Information System (INIS)

    Hunt, C.E.L.; Lewis, B.J.

    1995-01-01

    Sweep gas experiments performed at CRL from 1979 to 1985 have been analysed to determine the fraction of the fission product gas inventory that is released on reactor shutdown and startup. Empirical equations were derived and applied to calculate the xenon release from companion fuel elements and from a well documented experimental fuel bundle irradiated in the NRU reactor. The measured gas release could be matched to within about a factor of two for an experimental irradiation with a burnup of 217 MWh/kgU. (author)

  17. Extending reactor time-to-poison and reducing poison shutdown time by pre-shutdown power alterations

    Energy Technology Data Exchange (ETDEWEB)

    Kerr, Edward

    1963-10-15

    Manipulation of reactor power prior to shutdown and increasing the time- to-poison a sufficient amount to enable the required maintenance work to be completed and the reactor immediately restarted are discussed. The method employed in the NRU Reactor to gain the maximum timeto-poison with the least production loss is outlined. The method is based on intuition and is described by means of an analog of the iodine--xenon equations rather than the equations themselves. (C.E.S.)

  18. The Canadian R and D program targeted at CANDU reactors

    International Nuclear Information System (INIS)

    Moeck, E.O.

    1988-01-01

    CANDU reactors produce electricity cheaply and reliably, with miniscule risk to the population and minimal impact on the environment. About half of Ontario's electricity and a third of New Brunswick's are generated by CANDU power plants. Hydro Quebec and utilities in Argentina, India, Pakistan, and the Republic of Korea also successfully operate CANDU reactors. Romania will soon join their ranks. The proven record of excellent performance of CANDUs is due in part to the first objective of the vigorous R and D program: namely, to sustain and improve existing CANDU power-plant technology. The second objective is to develop improved nuclear power plants that will remain competitive compared with alternative energy supplies. The third objective is to continue to improve our understanding of the processes underlying reactor safety and develop improved technology to mitigate the consequences of upset conditions. These three objectives are addressed by individual R and D programs in the areas of CANDU fuel channels, reduced operating costs, reduced capital costs, reactor safety research, and IAEA safeguards. The work is carried out mainly at three centres of Atomic Energy of Canada Limited--the Chalk River Nuclear Laboratories, the Whiteshell Nuclear Research Establishment, and the Sheridan Park Engineering Laboratories--and at Ontario Hydro's Research Laboratories. Canadian universities, consultants, manufacturers, and suppliers also provide expertise in their areas of specialization

  19. Research reactor put Canada in the nuclear big time

    International Nuclear Information System (INIS)

    Anon.

    1988-01-01

    The history of the NRX reactor is briefly recounted. When NRX started up in 1947, it was the most powerful neutron source in the world. It is now the oldest research reactor still operating. NRX had to be rebuilt after an accident in 1952, and its calandria was changed again in 1970. Loops in NRX were used to test fuel for the Nautilus submarine, and the first zircaloy pressure tube in the world. At the present time, NRX is in a 'hot standby' condition as a backup to the NRU reactor, which is used mainly for isotope production. NRX will be decommissioned after completion and startup of the new MAPLE-X reactor

  20. 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)

  1. LOCA simulation in the NRU reactor: materials test-1

    International Nuclear Information System (INIS)

    Russcher, G.E.; Marshall, R.K.; Hesson, G.M.; Wildung, N.J.; Rausch, W.N.

    1981-10-01

    A simulated loss-of-coolant accident was performed with a full-length test bundle of pressurized water reactor fuel rods. This second experiment of the program produced peak fuel cladding temperatures of 1148K (1607 0 F) and resulted in six ruptured fuel rods. Test data and initial results from the experiment are presented here in the form of photographs and graphical summaries. These results are also compared with the preceding prototypic thermal-hydraulic test results and with computer model test predictions

  2. Reduce, reuse and recycle: a green solution to Canada's medical isotope shortage.

    Science.gov (United States)

    Galea, R; Ross, C; Wells, R G

    2014-05-01

    Due to the unforeseen maintenance issues at the National Research Universal (NRU) reactor at Chalk River and coincidental shutdowns of other international reactors, a global shortage of medical isotopes (in particular technetium-99m, Tc-99m) occurred in 2009. The operation of these research reactors is expensive, their age creates concerns about their continued maintenance and the process results in a large amount of long-lived nuclear waste, whose storage cost has been subsidized by governments. While the NRU has since revived its operations, it is scheduled to cease isotope production in 2016. The Canadian government created the Non-reactor based medical Isotope Supply Program (NISP) to promote research into alternative methods for producing medical isotopes. The NRC was a member of a collaboration looking into the use of electron linear accelerators (LINAC) to produce molybdenum-99 (Mo-99), the parent isotope of Tc-99m. This paper outlines NRC's involvement in every step of this process, from the production, chemical processing, recycling and preliminary animal studies to demonstrate the equivalence of LINAC Tc-99m with the existing supply. This process stems from reusing an old idea, reduces the nuclear waste to virtually zero and recycles material to create a green solution to Canada's medical isotope shortage. © 2013 Published by Elsevier Ltd.

  3. Overview on recent developments: alternative isotope production methods in Canada

    International Nuclear Information System (INIS)

    Huynh, K.

    2012-01-01

    The purpose of this paper is to provide an update on the Government of Canada's programs in alternative isotope production methods for securing supply of technetium 99m for Canadians. The supply disruptions of isotopes in 2007 and 2009/2010 caused by unplanned outages at AECL's National Research Universal (NRU) reactor highlighted the fragility of the supply chain that delivers medical isotopes, specifically Technetium 99m (Tc99m) to patients in Canada and globally. Tc99m, which is derived from its parent, molybdenum99 (Mo99) is the most widely used medical isotope for imaging, and accounts for 80 percent of nuclear medicine diagnostic procedures. Prior to the outage, nearly all the Mo99 produced for the world market came from five aging government owned research reactors in Canada, France, the Netherlands, Belgium and South Africa. The NRU, the largest of these, produced about 30 to 40 percent of the world supply of isotopes prior to 2009 - since its return to service in 2010, its world market share is estimated at 15 to 20%.

  4. Proceedings of the Canadian Nuclear Society 12. annual conference

    International Nuclear Information System (INIS)

    1991-01-01

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

  5. Transient fission-product release during reactor shutdown and startup

    International Nuclear Information System (INIS)

    Hunt, C.E.L.; Lewis, B.J.; Dickson, L.W.

    1997-12-01

    Sweep-gas experiments performed at AECL's Chalk River Laboratories from 1979 to 1985 have been further analysed to determine the fraction of the gaseous fission-product inventory that is released on reactor shutdown and startup. Empirical equations were derived and applied to calculate the stable xenon release from companion fuel elements and from a well-documented experimental fuel bundle irradiated in the NRU reactor. The calculated gas release could be matched to the measured values within about a factor of two for an experimental irradiation with a burnup of 217 MWh/kgU. There was also limited information on the fraction of the radioactive iodine that was exposed, but not released, on reactor shutdown. An empirical equation is proposed for calculating this fraction. (author)

  6. 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

  7. Return on experience on nuclear accidents

    International Nuclear Information System (INIS)

    Barre, Bertrand

    2015-09-01

    After a presentation of the International Nuclear and radiological Events Scale (INES scale), of its levels and criteria, this article proposes brief recalls of some nuclear accidents which occurred in nuclear reactors: Chalk River in Canada (1952), Windscale in England (1957), the universal Canadian reactor (NRU in 1958), the SL1 reactor of the Idaho National Laboratory in the USA (1961), the Swiss Lucens reactor (1969), Saint-Laurent des Eaux in France (1969 and 1980). More detailed descriptions are then given for the Three Mile Island accident in 1979, the Chernobyl accident in 1986, and the Fukushima accident in 2011. The main causes of these accidents are identified: loss of control of chain reaction, cooling defect on a stopped reactor, cooling defect on an operated reactor. Some lessons are drawn from these facts, and some characteristics of the EPR are outlined with respect with problems encountered in these accidents

  8. Canadian capabilities in fusion fuels technology and remote handling

    International Nuclear Information System (INIS)

    1987-10-01

    This report describes Canadian expertise in fusion fuels technology and remote handling. The Canadian Fusion Fuels Technology Project (CFFTP) was established and is funded by the Canadian government, the province of Ontario and Ontario Hydro to focus on the technology necessary to produce and manage the tritium and deuterium fuels to be used in fusion power reactors. Its activities are divided amongst three responsibility areas, namely, the development of blanket, first wall, reactor exhaust and fuel processing systems, the development of safe and reliable operating procedures for fusion facilities, and, finally, the application of these developments to specific projects such as tritium laboratories. CFFTP also hopes to utilize and adapt Canadian developments in an international sense, by, for instance, offering training courses to the international tritium community. Tritium management expertise is widely available in Canada because tritium is a byproduct of the routine operation of CANDU reactors. Expertise in remote handling is another byproduct of research and development of of CANDU facilities. In addition to describing the remote handling technology developed in Canada, this report contains a brief description of the Canadian tritium laboratories, storage beds and extraction plants as well as a discussion of tritium monitors and equipment developed in support of the CANDU reactor and fusion programs. Appendix A lists Canadian manufacturers of tritium equipment and Appendix B describes some of the projects performed by CFFTP for offshore clients

  9. MAPLE: a Canadian multipurpose reactor concept for national nuclear development

    International Nuclear Information System (INIS)

    Lidstone, R.F.

    1984-06-01

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

  10. Proceedings of the Canadian Nuclear Society 15. annual conference

    Energy Technology Data Exchange (ETDEWEB)

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

    1994-12-31

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

  11. Proceedings of the Canadian Nuclear Society 15. annual conference

    International Nuclear Information System (INIS)

    Huynh, H.M.

    1994-01-01

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

  12. 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

  13. MOX fuel: a contribution to disarmament. U.S. utilities' response to DOE's plutonium disposition decision

    International Nuclear Information System (INIS)

    Wallace, M.

    1997-01-01

    The author is chairman of the Nuclear Energy Institute Plutonium Disposition Working Group, which includes 11 nuclear utilities, including Ontario Hydro, and all the European fabricators of mixed oxide (MOX) fuel. A feasibility study is going on, to see if Russian or other weapons grade plutonium made into MOX fuel can be used in US, Canadian, or other power reactors. The US nuclear power industry is going through a period of change, and its primary responsibility must be the safe, reliable and economic operation of its plants. There is no current US MOX capacity, but the Europeans have have manufactured and burned over 400 tons of MOX fuel since 1963. Canada may be involved, initially through a pilot-scale experiment in NRU reactor

  14. 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

  15. Distributed production system for 99mTc-I: System overview

    International Nuclear Information System (INIS)

    Bennett, R.G.; Terry, W.K.; Grover, S.B.

    1997-01-01

    Technetium-99m is the radioisotope of choice for >80% of all nuclear medical imaging procedures today in the United States. There are > 12 million 99m Tc scans performed in the United States per year. Since the development of fission-based radio nuclide generators for 99 Mo, 99m Tc use has grown steadily over the past 20 yr. Despite the widespread demand for 99m Tc in medicine, a reliable and assured supply of the parent, 99 Mo, does not exist. Construction of Maple-1 and -2, two new Canadian isotope production reactors intended to replace the aging National Research Universal (NRU) reactor, has been approved in an agreement among Atomic Energy of Canada Limited, MDS Nordion, and the Canadian government. However, the project is expensive: The anticipated cost of Maple-1 and -2 is $C140 million. Outlays toward this cost have recently driven the price of 99 Mo up by 40%, even though the Canadian 99 Mo production will continue to be heavily subsidized by an interest-free construction loan. Research and development for an accelerator-based facility has been undertaken and is described

  16. Reactor loops at Chalk River

    International Nuclear Information System (INIS)

    Sochaski, R.O.

    1962-07-01

    This report describes broadly the nine in-reactor loops, and their components, located in and around the NRX and NRU reactors at Chalk River. First an introduction and general description is given of the loops and their function, supplemented with a table outlining some loop specifications and nine simplified flow sheets, one for each individual loop. The report then proceeds to classify each loop into two categories, the 'main loop circuit' and the 'auxiliary circuit', and descriptions are given of each circuit's components in turn. These components, in part, are comprised of the main loop pumps, the test section, loop heaters, loop coolers, delayed-neutron monitors, surge tank, Dowtherm coolers, loop piping. Here again photographs, drawings and tables are included to provide a clearer understanding of the descriptive literature and to include, in tables, some specifications of the more important components in each loop. (author)

  17. Digital computer control on Canadian nuclear power plants -experience to date and the future outlook

    International Nuclear Information System (INIS)

    Pearson, A.

    1977-10-01

    This paper discusses the performance of the digital computer control system at Pickering through the years 1973 to 1976. This evaluation is based on a study of the Pickering Generating Station operating records. The paper goes on to explore future computer architectures and the advantages that could accrue from a distributed system approach. Also outlined are the steps being taken to develop these ideas further in the context of two Chalk River projects - REDNET, an advanced data acquisition system being installed to process information from engineering experiments in NRX and NRU reactors, and CRIP, a prototype communications network using cable television technology. (author)

  18. A preliminary CATHENA thermalhydraulic model of the Canadian SCWR for safety analysis

    Energy Technology Data Exchange (ETDEWEB)

    Wang, D.F.; Wang, S., E-mail: wangd@aecl.ca [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada)

    2014-06-15

    The supercritical water-cooled reactor (SCWR) is one of six reactor concepts under development in the Generation-IV International Forum (GIF). As a member of GIF, Canada is developing a pressure-tube type SCWR, which has the potential to fulfill all major GIF goals on enhanced safety, sustainability, economics, and proliferation resistance. The system thermalhydraulics code CATHENA will be used in the safety analyses for the Canadian SCWR. Based on the current conceptual design of the Canadian SCWR, a CATHENA idealization has been developed. This model includes all 336 fuel channels with a detailed model of heat transfer in the reactor core. Also modeled are the main pumps, inlet plenum, outlet plenum, turbines, and heavy water moderator. In this paper, the CATHENA idealization of the Canadian SCWR conceptual design is described. Simulation results for steady-state normal operations are also presented for the current Canadian SCWR conceptual design. (author)

  19. An overview of the evaluations of nuclear power by Canadians

    International Nuclear Information System (INIS)

    Barrados, Maria

    1980-01-01

    Limited data are available on Canadian evaluations of nuclear power. General observations are made, based on a 1976 national study by B. Greer-Wootten and a 1978 Canadian Gallup Poll survey. Little change in the knowledge Canadians have of nuclear power appears to have taken place. A sizeable proportion of the population is willing to offer an opinion about the use of nuclear power while knowing nothing about it. Increased knowledge is not associated with more positive or negative evaluations of nuclear power. In more specific evaluations of nuclear safety, increased knowledge is found to be associated with a lowered confidence in the safety of Canadian reactors. There appears to have been a drop in the proportions of Canadians somewhat in favour of nuclear power between 1976 and 1978. Since many Canadians do not know much about the use of nuclear power and the majority of opinions are not strongly committed, there is considerable potential for fluctuation in these figures. Increased emphasis appears to be put on waste management issues in 1978, while nuclear power plants are less likely to be perceived as unsafe. This may be the result of increased discussion of Canadian power reactors. (LL)

  20. Reduce, reuse and recycle: A green solution to Canada's medical isotope shortage

    International Nuclear Information System (INIS)

    Galea, R.; Ross, C.; Wells, R.G.

    2014-01-01

    Due to the unforeseen maintenance issues at the National Research Universal (NRU) reactor at Chalk River and coincidental shutdowns of other international reactors, a global shortage of medical isotopes (in particular technetium-99m, Tc-99m) occurred in 2009. The operation of these research reactors is expensive, their age creates concerns about their continued maintenance and the process results in a large amount of long-lived nuclear waste, whose storage cost has been subsidized by governments. While the NRU has since revived its operations, it is scheduled to cease isotope production in 2016. The Canadian government created the Non-reactor based medical Isotope Supply Program (NISP) to promote research into alternative methods for producing medical isotopes. The NRC was a member of a collaboration looking into the use of electron linear accelerators (LINAC) to produce molybdenum-99 (Mo-99), the parent isotope of Tc-99m. This paper outlines NRC’s involvement in every step of this process, from the production, chemical processing, recycling and preliminary animal studies to demonstrate the equivalence of LINAC Tc-99m with the existing supply. This process stems from reusing an old idea, reduces the nuclear waste to virtually zero and recycles material to create a green solution to Canada's medical isotope shortage. - Highlights: • Commercial power electron accelerators are realistic option to produce 99 Mo. • Could cover national demand of Canada. • Demonstrate LINAC- 99 Mo as environmental and economical solution to isotope crisis. • Demonstrate LINAC- 99m Tc to be clinically equivalent to current fission- 99m Tc supply

  1. Finally, nuclear engineering textbooks with a Canadian flavour!

    International Nuclear Information System (INIS)

    Bonin, H.W.

    2002-01-01

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

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

    International Nuclear Information System (INIS)

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

    2015-01-01

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

  3. Comparisons of FCC product yields and qualities between reactors using Canadian heavy feeds

    Energy Technology Data Exchange (ETDEWEB)

    Ng, Siauw H.; Fairbridge, Craig; Khulbe, Chandra [National Centre for Upgrading Technology, 1 Oil Patch Drive, Devon, Alberta (Canada); Humphries, Adrian [Akzo Nobel Catalysts LLC., 2625 Bay Area Boulevard, Suite 250, Houston, TX 77058 (United States); Zhu, Yuxia [Research Institute of Petroleum Processing, 18 Xue Yuen Road, PO Box 914, Beijing 100083 (China); Tsai, Thomas Y.R. [National Dong Hwa University, Hualien 974 (Taiwan); Ding, Fuchen [University of Petroleum, Beijing 102249 (China); Charland, Jean-Pierre [CANMET Energy Technology Centre-Ottawa, 1 Haanel Drive, Ottawa, Ontario (Canada); Yui, Sok [Syncrude, Research Centre, 9421-17 Avenue, Edmonton, Alberta (Canada)

    2005-08-25

    This study describes the effects of two catalysts, an octane-barrel and a bottoms-cracking catalyst, on the catalytic cracking of 10 oil-sands bitumen-derived feeds in fixed- and fluid-bed microactivity test (MAT) units, an Advanced Cracking Evaluation (ACE) unit, and a continuous riser pilot unit. This is part of a comprehensive study of the cracking behavior of Canadian vacuum gas oils. In general, at an equivalent catalyst/oil ratio, conversions decreased in the order ACE>fixed-bed MAT>fluid-bed MAT among the batch reactors. Between a batch reactor and the continuous riser, there existed a good correlation for a given product yield as well as for a given product quality, at a specific conversion. For the oil-sands-derived vacuum gas oils, the bottoms-cracking catalyst containing rare-earth-exchanged Y zeolite (REY) with a large-pore active matrix was more effective than the catalyst containing the rare-earth-exchanged ultrastable Y (REUSY) and ZSM-5 zeolites with an active matrix. The overall distribution of feed sulfur in cracked products, and the relationship of the sulfur content of feed with that of light cycle oil (LCO), confirmed the findings reported in the literature.

  4. Reactor core and passive safety systems descriptions of a next generation pressure tube reactor - mechanical aspects

    Energy Technology Data Exchange (ETDEWEB)

    Yetisir, M.; Gaudet, M.; Rhodes, D.; Hamilton, H.; Pencer, J. [Atomic Energy of Canada Limited, Chalk River, ON (Canada)

    2014-07-01

    Canada has been developing a channel-type supercritical water-cooled nuclear reactor concept, often called the Canadian SCWR. The objective of this reactor concept is to meet the technology goals of the Generation IV International Forum (GIF) for the next generation nuclear reactor development, which include enhanced safety features (inherent safe operation and deploying passive safety features), improved resource utilization, sustainable fuel cycle, and greater proliferation resistance than Generation III nuclear reactors. The Canadian SCWR core concept consists of a high-pressure inlet plenum, a separate low-pressure heavy water moderator contained in a calandria vessel, and 336 pressure tubes surrounded by the moderator. The reactor uses supercritical water as a coolant, and a direct steam power cycle to generate electricity. The reactor concept incorporates advanced safety features such as passive core cooling, long-term decay heat rejection to the environment and fuel melt prevention via passive moderator cooling. These features significantly reduce core damage frequency relative to existing nuclear reactors. This paper presents a description of the design concepts for the Canadian SCWR core, reactor building layout and the plant layout. Passive safety concepts are also described that address containment and core cooling following a loss-of coolant accident, as well as long term reactor heat removal at station blackout conditions. (author)

  5. Waste management in Canadian nuclear programs

    International Nuclear Information System (INIS)

    Dyne, P.J.

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

  6. Optimization of the fuel assembly for the Canadian SuperCritical Water-cooled Reactor (SCWR)

    Energy Technology Data Exchange (ETDEWEB)

    French, C., E-mail: Corey.French@cnsc-ccsn.gc.ca [Canadian Nuclear Safety Commission, Ottawa, Ontario (Canada); Bonin, H.; Chan, P.K. [Royal Military College of Ontario, Kingston, Ontario (Canada)

    2013-07-01

    An approach to develop a parametric optimization tool to support the Canadian Supercritical Water-cooled Reactor (SCWR) fuel design is presented in this work. The 2D benchmark lattices for 78-pin and 64-pin fuel assemblies are used as the initial models from which fuel performance and subsequent optimization stem from. A tandem optimization procedure is integrated which employs the steepest descent method. The physics codes WIMS-AECL, MCNP6 and SERPENT are used to calculate and verify select performance factors. The results are used as inputs to an optimization algorithm that yield optimal fresh fuel isotopic composition and lattice geometry. Preliminary results on verifications of infinite lattice reactivity are demonstrated in this paper. (author)

  7. Description of the blowdown test facility COG program on in-reactor fission product release, transport, and deposition under severe accident conditions

    International Nuclear Information System (INIS)

    Fehrenbach, P.J.; Wood, J.C.

    1987-06-01

    Loss-of-coolant accidents with additional impairment of emergency cooling would probably result in high fuel temperatures leading to severe fuel damage (SFD) and significant fission product activity would then be transported along the PHTS to the break where a fraction of it would be released and transport under such conditions, there are many interacting and sometimes competing phenomena to consider. Laboratory simulations are being used to provide data on these individual phenomena, such as UO 2 oxidation and Zr-UO 2 interaction, from which mathematical models can be constructed. These are then combined into computer codes to include the interaction effects and assess the overall releases. In addition, in-reactor tests are the only source of data on release and transport of short-lived fission product nuclides, which are important in the consequence analysis of CANDU reactor accidents. Post-test decontamination of an in-reactor test facility also provides a unique opportunity to demonstrate techniques and obtain decontamination data relevant to post-accident rehabilitation of CANDU power reactors. Specialized facilities are required for in-reactor testing because of the extensive release of radioactive fission products and the high temperatures involved (up to 2500 degrees Celsius). To meet this need for the Canadian program, the Blowdown Test Facility (BTF) has been built in the NRU reactor at Chalk River. Between completion of construction in mid-1987 and the first Zircaloy-sheathed fuel test in fiscal year 1987/88, several commissioning tests are being performed. Similarly, extensive development work has been completed to permit application of instrumentation to irradiated fuel elements, and in support of post-test fuel assembly examination. A program of decontamination studies has also been developed to generate information relevant to post-accident decontamination of power reactors. The BTF shared cost test program funded by the COG High Temperature

  8. A novel approach to the production of medical radioisotopes: the homogeneous SLOWPOKE reactor

    International Nuclear Information System (INIS)

    Bonin, H.W.; Hilborn, J.W.; Carlin, G.E.; Gagnon, R.; Busatta, P.

    2015-01-01

    In 2009, the unexpected 15-month outage of the Canadian NRU nuclear reactor resulted in a sudden 30% world shortage, with higher shortages experienced in North America than in Europe. Commercial radioisotope production is from just eight nuclear reactors, most being aging systems near the end of their service life. This paper proposes a more efficient production and distribution model. Tc-99m unit doses would be distributed to regional hospitals from ten integrated 'industrial radiopharmacies', located at existing licensed nuclear reactor sites in North America. At each site, one or more 20 kW Homogeneous SLOWPOKE nuclear reactors would deliver 15 litres of irradiated aqueous uranyl sulfate fuel solution daily to industrial-scale hot cells, for extraction of Mo-99; and the low-enriched uranium would be recycled. Purified Mo-99 would be incorporated in large Mo-99/Tc-99m generators for extraction of Tc-99m five days a week; and each automated hot-cell facility would be designed to load up to 7,000 Tc-99m syringes daily for road delivery to all of the nuclear medicine hospitals within a 3-hour range. At the current price of $20 per unit dose, the annual gross income from 10 sites would be approximately $360 million. The Homogeneous SLOWPOKE reactor evolved from the inherently safe SLOWPOKE-2 research reactor, with a double goal: replacing the heterogeneous SLOWPOKE-2 reactors at the end-of-core life, enabling them to continue their primary missions of research and education, together with full time commercial radioisotope production. The Homogeneous SLOWPOKE reactor was modelled using both deterministic and probabilistic reactor simulation codes. The homogeneous fuel mixture is a dilute aqueous solution of low-enriched uranyl sulfate containing approximately 1 kg of U-235. The reactor is controlled by mechanical absorber rods in the beryllium reflector. Safety analysis was carried out for both normal operation and transient conditions. The most severe

  9. A novel approach to the production of medical radioisotopes: the homogeneous SLOWPOKE reactor

    Energy Technology Data Exchange (ETDEWEB)

    Bonin, H.W., E-mail: bonin-h@rmc.ca [Royal Military College of Canada, Kingston, Ontario (Canada); Hilborn, J.W. [retired, Atomic Energy of Canada Limited, Chalk River, Ontario (Canada); Carlin, G.E. [Ontario Power Generation, Toronto, Ontario (Canada); Gagnon, R.; Busatta, P. [Royal Canadian Navy, Ottawa, Ontario (Canada)

    2015-03-15

    In 2009, the unexpected 15-month outage of the Canadian NRU nuclear reactor resulted in a sudden 30% world shortage, with higher shortages experienced in North America than in Europe. Commercial radioisotope production is from just eight nuclear reactors, most being aging systems near the end of their service life. This paper proposes a more efficient production and distribution model. Tc-99m unit doses would be distributed to regional hospitals from ten integrated 'industrial radiopharmacies', located at existing licensed nuclear reactor sites in North America. At each site, one or more 20 kW Homogeneous SLOWPOKE nuclear reactors would deliver 15 litres of irradiated aqueous uranyl sulfate fuel solution daily to industrial-scale hot cells, for extraction of Mo-99; and the low-enriched uranium would be recycled. Purified Mo-99 would be incorporated in large Mo-99/Tc-99m generators for extraction of Tc-99m five days a week; and each automated hot-cell facility would be designed to load up to 7,000 Tc-99m syringes daily for road delivery to all of the nuclear medicine hospitals within a 3-hour range. At the current price of $20 per unit dose, the annual gross income from 10 sites would be approximately $360 million. The Homogeneous SLOWPOKE reactor evolved from the inherently safe SLOWPOKE-2 research reactor, with a double goal: replacing the heterogeneous SLOWPOKE-2 reactors at the end-of-core life, enabling them to continue their primary missions of research and education, together with full time commercial radioisotope production. The Homogeneous SLOWPOKE reactor was modelled using both deterministic and probabilistic reactor simulation codes. The homogeneous fuel mixture is a dilute aqueous solution of low-enriched uranyl sulfate containing approximately 1 kg of U-235. The reactor is controlled by mechanical absorber rods in the beryllium reflector. Safety analysis was carried out for both normal operation and transient conditions. The most severe

  10. 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

  11. Fabrication of CANFLEX bundle kit for irradiation test in NRU

    International Nuclear Information System (INIS)

    Cho, Moon Sung; Kwon, Hyuk Il; Ji, Chul Goo; Chang, Ho Il; Sim, Ki Seob; Suk, Ho Chun.

    1997-10-01

    CANFLEX bundle kit was prepared at KAERI for the fabrication of complete bundle at AECL. Completed bundle will be used for irradiation test in NRU. Provisions in the 'Quality Assurance Manual for HWR Fuel Projects,' 'Manufacturing Plan' and 'Quality Verification, Inspection and Test Plan' were implemented as appropriately for the preparation of CANFLEX kit. A set of CANFLEX kit consist of 43 fuel sheath of two different sizes with spacers, bearing pads and buttons attached, 2 pieces of end plates and 86 pieces of end caps with two different sizes. All the documents utilized as references for the fabrication such as drawings, specifications, operating instructions, QC instructions and supplier's certificates are specified in this report. Especially, suppliers' certificates and inspection reports for the purchased material as well as KAERI's inspection report are integrated as attachments to this report. Attached to this report are supplier's certificates and KAERI inspection reports for the procured materials and KAERI QC inspection reports for tubes, pads, spacers, buttons, end caps, end plates and fuel sheath. (author). 37 refs

  12. Nuclear energy: a world of service to humanity. 27th annual conference of the Canadian Nuclear Society and 30th Canadian Nuclear Society/Canadian Nuclear Association student conference

    International Nuclear Information System (INIS)

    2006-01-01

    The 27th Annual conference of the Canadian Nuclear Society was held on June 11-14, 2006 in Toronto, Ontario, Canada. The conference gathered close to 400 scientists, engineers, technologists and students interested in all aspects and applications of energy from the atom. The central objective of this conference was to provide a forum for exchange of views on how this technical enterprise can best serve the needs of humanity, now and in the future. The plenary sessions addressed broad industrial and commercial developments in the field. Over eighty papers were presented in 15 technical sessions on the following topics: safety analysis; plant refurbishment; control room operation; nuclear chemistry and materials; advanced reactor design; plant operation; reactor physics; safety analysis; nuclear instrumentation; and, nuclear general topics. Embedded in the conference was the 30th student conference, sponsored by the Canadian Nuclear Society and the Canadian Nuclear Association. Over thirty-five papers were presented in five sessions on the following topics: corrosion processes; control systems / physics / modelling; and, chemistry / chemical engineering

  13. Status of LEU conversion program at CRNL

    International Nuclear Information System (INIS)

    Kennedy, I.C.

    1991-01-01

    After briefly reviewing the salient features of the NRU Reactor at Chalk River Nuclear Laboratories (CRNL), the progress of our LEU fuel development and testing program is described. The results (to date) of full-size prototype fuel-rod irradiations are reviewed, and the status of the new fuel-fabrication facility on the site is updated. Although development work is proceeding on U 3 Si 2 dispersions, all indications so far are that CRNL's U 3 Si fuel is fully acceptable for reactor operation. Fuel rods from the new fabrication shop will be installed in NRU in 1990, and the complete core conversion of NRU to LEU driver fuel is expected by 1991. (orig.)

  14. An update on the LEU target development and conversion program for the MAPLE reactors and new processing facility

    International Nuclear Information System (INIS)

    Malkoske, G.R.; Eng, B.Sc; Eng, P.

    2002-01-01

    Historically, the production of molybdenum-99 in the NRU research reactors at Chalk River, Canada, has been extracted from reactor targets employing highly enriched uranium (HEU). A reliable supply of HEU metal from the United States used in the manufacture of targets for the NRU research reactor has been a key factor to enable MDS Nordion to develop a secure supply of medical isotopes for the international nuclear medicine community. The molybdenum extraction process from HEU targets provides predictable, consistent yields for our high-volume molybdenum production process. Each link of the isotope supply chain, from isotope production to ultimate use by the physician, has been established using this proven and established method of HEU target irradiation and processing to extract molybdenum-99. To ensure a continued reliable and timely supply of medical isotopes, MDS Nordion is completing the construction of two MAPLE reactors and a New Processing Facility. The design of the MAPLE facilities was based on an established process developed by Atomic Energy of Canada Ltd. (AECL)-extraction of isotopes from HEU target material. However, in concert with the global trend to utilize low enriched uranium (LEU) in research reactors, MDS Nordion has launched a three phase LEU Target Development and Conversion Program for the MAPLE facilities. Phase 1, the Initial Feasibility Study, which identified the technical issues to convert the MAPLE reactor targets from HEU to LEU for large scale commercial production was reported on at the RERTR-2000 conference. The second phase of the LEU Target Development and Conversion Program was developed with extensive consultation and involvement of experts knowledgeable in target development, process system design, enriched uranium conversion chemistry and commercial scale reactor operations and molybdenum production. This paper will provide an overview of the Phase 2 Conversion Development Program, report on progress to date, and further

  15. Distributed control and instrumentation systems for future nuclear power plants

    International Nuclear Information System (INIS)

    Yan, G.; L'Archeveque, J.V.R.

    1976-01-01

    The centralized dual computer system philosophy has evolved as the key concept underlying the highly successful application of direct digital control in CANDU power reactors. After more than a decade, this basis philosophy bears re-examination in the light of advances in system concepts--notably distributed architectures. A number of related experimental programs, all aimed at exploring the prospects of applying distributed systems in Canadian nuclear power plants are discussed. It was realized from the outset that the successful application of distributed systems depends on the availability of a highly reliable, high capacity, low cost communications medium. Accordingly, an experimental facility has been established and experiments have been defined to address such problem areas as interprocess communications, distributed data base design and man/machine interfaces. The design of a first application to be installed at the NRU/NRX research reactors is progressing well

  16. Transfer of Canadian nuclear regulatory technology

    International Nuclear Information System (INIS)

    Harvie, J.D.

    1985-10-01

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

  17. The LEU target development and conversion program for the MAPLE reactors and new processing facility

    International Nuclear Information System (INIS)

    Malkoske, G.R.

    2002-01-01

    Historically, the production of molybdenum-99 in the NRU research reactors at Chalk River, Canada has been extracted from reactor targets employing highly enriched uranium (HEU). A reliable supply of HEU metal from the United States used in the manufacture of targets for the NRU research reactor has been a key factor to enable MDS Nordion to develop a secure supply of medical isotopes for the international nuclear medicine community. The molybdenum extraction process from HEU targets provides predictable, consistent yields for our high-volume molybdenum production process. Each link of the isotope supply chain, from isotope production to ultimate use by the physician, has been established using this proven and established method of HEU target irradiation and processing to extract molybdenum-99. To ensure a continued reliable and timely supply of medical isotopes, MDS Nordion is completing the construction of two MAPLE reactors and a New Processing Facility. The design of the MAPLE facilities was based on an established process developed by Atomic Energy of Canada Ltd. (AECL) - extraction of isotopes from HEU target material. However, in concert with the global trend to utilize low enriched uranium (LEU) in research reactors, MDS Nordion has launched a three phase LEU Target Development and Conversion Program for the MAPLE facilities. Phase 1, the Initial Feasibility Study, which identified the technical issues to convert the MAPLE reactor targets from HEU to LEU for large scale commercial production was reported on at the RERTR- 2000 conference. The second phase of the LEU Target Development and Conversion Program was developed with extensive consultation and involvement of experts knowledgeable in target development, process system design, enriched uranium conversion chemistry and commercial scale reactor operations and molybdenum production. This paper will provide an overview of the Phase 2 Conversion Development Program, report on progress to date, and further

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2002-07-01

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

  19. The Canadian research reactor spent fuel situation

    International Nuclear Information System (INIS)

    Ernst, P.C.

    1996-01-01

    This paper summarizes the present research reactor spent fuel situation in Canada. The research reactors currently operating are listed along with the types of fuel that they utilize. Other shut down research reactors contributing to the storage volume are included for completeness. The spent fuel storage facilities associated with these reactors and the methods used to determine criticality safety are described. Finally the current inventory of spent fuel and where it is stored is presented along with concerns for future storage. (author). 3 figs

  20. Performance of Canadian commercial nuclear units and heavy water plants

    International Nuclear Information System (INIS)

    Woodhead, L.W.; Ingolfsrud, L.J.

    The operating history of Canadian commercial CANDU type reactors, i.e. Pickering generating station-A, is described. Capacity factors and unit energy costs are analyzed in detail. Equipment performance highlights are given. The performance of the two Canadian heavy water plants is described and five more are under construction or planned. (E.C.B.)

  1. The Benefits of the 3T3 NRU Test in the Safety Assessment of Cosmetics: Long-Term Experience from Pre-Marketing Testing in the Czech Republic.

    Czech Academy of Sciences Publication Activity Database

    Jírová, D.; Kejlová, K.; Brabec, Marek; Bendová, H.; Kolářová, H.

    2003-01-01

    Roč. 174, č. 5-6 (2003), s. 791-796 ISSN 0887-2333 Source of funding: V - iné verejné zdroje Keywords : cytotoxicity * 3T3 NRU assay * irritation * nonparametric statistical model Subject RIV: BB - Applied Statistics, Operational Research Impact factor: 1.642, year: 2003

  2. The task ahead: a Canadian federal regulator's perspective

    International Nuclear Information System (INIS)

    Brooks, F.F.

    1983-06-01

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

  3. Proceedings of the Canadian Nuclear Society sixth annual conference

    International Nuclear Information System (INIS)

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

    1985-01-01

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

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

    International Nuclear Information System (INIS)

    MacKenzie, B.

    2010-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-07-01

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

  6. Canadian approach to nuclear power safety

    International Nuclear Information System (INIS)

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

    1983-01-01

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

  7. Canadian fusion program

    International Nuclear Information System (INIS)

    Brown, T.S.

    1982-06-01

    The National Research Council of Canada is establishing a coordinated national program of fusion research and development that is planned to grow to a total annual operating level of about $20 million in 1985. The long-term objective of the program is to put Canadian industry in a position to manufacture sub-systems and components of fusion power reactors. In the near term the program is designed to establish a minimum base of scientific and technical expertise sufficient to make recognized contributions and thereby gain access to the international effort. The Canadian program must be narrowly focussed on a few specializations where Canada has special indigenous skills or technologies. The programs being funded are the Tokamak de Varennes, the Fusion Fuels Technology Project centered on tritium management, and high-power gas laser technology and associated diagnostic instrumentation

  8. Organizing the Canadian nuclear industry to meet the challenge

    International Nuclear Information System (INIS)

    Lortie, Pierre.

    1983-06-01

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

  9. The prospects for Canadian uranium

    International Nuclear Information System (INIS)

    Salaff, S.

    1983-07-01

    The 1980s have seen a decline in markets for uranium concentrate, largely as a result of falling estimates for reactor fuel requirements and rising inventories. Spot market prices fell to $44 in September 1982, but have since risen back to $60. World production also fell in 1982 and is not expected to increase significantly before 1990. Some opportunities exist for Canadian producers with new low-cost deposits to replace high-cost producers in Canada and other countries, particularly the United States. There will be strong competition between Canadian producers as well as from Australia. Australia's reserves are somewhat larger than Canada's, although the reported ore grades tend to be lower than those of Saskatchewan

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

    International Nuclear Information System (INIS)

    1992-01-01

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

  11. Detection of gaseous fission products in water - a method of monitoring fuel sheathing failures

    Energy Technology Data Exchange (ETDEWEB)

    Tunnicliffe, P. R.; Whittier, A. C.

    1959-05-15

    The gaseous activities stripped from samples of effluent coolant from the NRU fuel elements tested in the central thimble of the NRX reactor (NRU loop) and from the NRX main effluent have been investigated. The activities obtained from the NRU loop can be attributed to gaseous fission products only. Design data have been obtained for a 'Gaseous Fission Product Monitor' to be installed for use with the NRU reactor. It is expected that this monitor will have high sensitivity to activity indicative of an incipient fuel element sheath failure. No qualitative determination of the various gaseous activities obtained from the NRX effluent has been made. A strong component of 25 {+-}1 seconds half-life is not consistent with O-19. Limited information concerning sheath failures in NRX was obtained. Of six failures observed in parallel with the installed delayed neutron monitors, three of these gave pre-warnings and in each case the gaseous fission product monitor showed a substantially greater sensitivity. An experiment in which small samples of uranium, inserted into the NRX reactor, could be exposed at will to a stream of water showed the behaviour of the two types of monitors to be similar. However, a number of signals were detected only by the gaseous fission product monitor. These can be attributed to its sensitivity to relatively long lived fission products. (author)

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

    International Nuclear Information System (INIS)

    Horgan, J.

    1984-01-01

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

  13. REDNET: a distributed data acquisition system for a nuclear research reactor

    International Nuclear Information System (INIS)

    Shah, R.R.; Pensom, C.F.

    1984-05-01

    Experimental facilities such as those in the NRU nuclear research reactor at the Chalk River Nuclear Laboratories (CRNL) need a data acquisition system that combines high performance with flexibility. The REactor Data NETwork (REDNET) is a system being developed at CRNL that used distributed computer technology to meet demanding requirements. This paper describes the distributed architecture of REDNET, comprising 7 minicomputers, and presents an overview of the software configuration and data structures which have been designed to produce a versatile and interactive system that must gather and store data at rates ranging from 20 times a second to once every 30 minutes. Each experimenter is provided with a unique set of points that are referred to collectively, and manipulated together as a group. Facilities are provided to modify operating parameters for and view data values in a group without affecting other groups. Facilities incorporated for graceful degradation of REDNET and automatic recovery from failures are also described

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

    International Nuclear Information System (INIS)

    Rouben, B.

    1990-01-01

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

  15. Fully integrated analysis of reactor kinetics, thermalhydraulics and the reactor control system in the MAPLE-X10 research reactor

    International Nuclear Information System (INIS)

    Shim, S.Y.; Carlson, P.A.; Baxter, D.K.

    1992-01-01

    A prototype research reactor, designated MAPLE-X10 (Multipurpose Applied Physics Lattice Experimental - X 10MW), is currently being built at AECL's Chalk River Laboratories. The CATHENA (Canadian Algorithm for Thermalhydraulic Network Analysis) two-fluid code was used in the safety analysis of the reactor to determine the adequacy of core cooling during postulated reactivity and loss-of-forced-flow transients. The system responses to a postulated transient are predicted including the feedback between reactor kinetics, thermalhydrauilcs and the reactor control systems. This paper describes the MAPLE-X10 reactor and the modelling methodology used. Sample simulations of postulated loss-of-heat-sink and loss-of-regulation transients are presented. (author)

  16. The Canadian approach to nuclear power safety

    International Nuclear Information System (INIS)

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

    1983-07-01

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

  17. Reactor core simulations in Canada

    International Nuclear Information System (INIS)

    Roy, R.; Koclas, J.; Shen, W.; Jenkins, D. A.; Altiparmakov, D.; Rouben, B.

    2004-01-01

    This review will address the current simulation flow-chart currently used for reactor-physics simulations in the Canadian industry. The neutron behaviour in heavy-water moderated power reactors is quite different from that in other power reactors, thus the core physics approximations are somewhat different Some codes used are particular to the context of heavy-water reactors, and the paper focuses on this aspect. The paper also shows simulations involving new design features of the Advanced Candu Reactor TM (ACR TM), and provides insight into future development, expected in the coming years. (authors)

  18. Fuels for Canadian research reactors

    International Nuclear Information System (INIS)

    Feraday, M.A.

    1993-01-01

    For a period of about 10 years AECL had a significant program looking into the possibility of developing U 3 Si as a high density replacement for the UO 2 pellet fuel in use in CANDU power reactors. The element design consisted of a Zircaloy-clad U 3 Si rod containing suitable voidage to accommodate swelling. We found that the binary U 3 Si could not meet the defect criterion for our power reactors, i.e., one month in 300 degree C water with a defect in the sheath and no significant damage to the element. Since U 3 Si could not do the job, a new corrosion resistant ternary U-Si-Al alloy was developed and patented. Fuel elements containing this alloy came close to meeting the defect criterion and showed slightly better irradiation stability than U 3 Si. Shortly after this, the program was terminated for other reasons. We have made much of this experience available to the Low Enrichment Fuel Development Program and will be glad to supply further data to assist this program

  19. Coupled 3D neutron kinetics and thermalhydraulic characteristics of the Canadian supercritical water reactor

    Energy Technology Data Exchange (ETDEWEB)

    Hummel, David William, E-mail: hummeld@mcmaster.ca; Novog, David Raymond

    2016-03-15

    Highlights: • A coupled spatial kinetics and thermalhydraulics model of the PT-SCWR was created. • Positive power excursions were demonstrated during accident-like transients. • The reactor will inherently self-shutdown in such transients with some delay. • A fast-acting shutdown system would limit the consequences of the power pulse. - Abstract: The Canadian Supercritical Water-cooled Reactor concept, as an evolution of the CANada Deuterium Uranium (CANDU) reactor, includes both pressure tubes and a low temperature heavy water moderator. The current Pressure Tube type SCWR (PT-SCWR) concept features 64-element fuel assemblies placed within High Efficiency Re-entrant Channels (HERCs) that connect to core inlet and outlet plena. Among current SCWR concepts the PT-SCWR is unique in that the HERC separates multiple coolant and moderator regions, giving rise to coupled neutronic-thermalhydraulic feedbacks beyond those present in CANDU or contemporary Light Water Reactors. The objective of this work was thus to model the coupled neutronic-thermal hydraulic properties of the PT-SCWR to establish the impact of these multiple regions on the core's transient behavior. To that end, the features of the PT-SCWR were first modeled with the neutron transport code DRAGON to create a database of homogenized and condensed cross-sections and thermalhydraulic feedback coefficients. These were used as input to a core-level neutron diffusion model created with the code DONJON. The behavior of the primary heat transport system was modeled with the thermalhydraulic system code CATHENA. A procedure was developed to couple the outputs of DONJON and CATHENA, facilitating three-dimensional spatial neutron kinetics and coupled thermalhydraulic analysis of the PT-SCWR core. Several postulated transients were initiated within the coupled model by changing the core inlet and outlet boundary conditions. Decreasing coolant density around the fuel was demonstrated to produce positive

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

    Energy Technology Data Exchange (ETDEWEB)

    1993-12-31

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

  1. Terrestrial Energy bets on molten salt reactors

    International Nuclear Information System (INIS)

    Anon.

    2015-01-01

    Terrestrial Energy is a Canadian enterprise, founded in 2013, for marketing the integral molten salt reactor (IMSR). A first prototype (called MSRE and with an energy output of 8 MW) was designed and operated between 1965 and 1969 by the Oak Ridge National Laboratory. IMSR is a small, modular reactor with a thermal energy output of 400 MW. According to Terrestrial Energy the technology of conventional power reactors is too complicated and too expensive. On the contrary IMSR's technology appears to be simple, easy to operate and affordable. With a staff of 30 people Terrestrial Energy appears to be a start-up in the nuclear sector. A process of pre-licensing will be launched in 2016 with the Canadian nuclear safety authority. (A.C.)

  2. Government intervention in the Canadian nuclear industry

    Energy Technology Data Exchange (ETDEWEB)

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

    1980-01-01

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

  3. Cobalt-60 production in CANDU power reactors

    International Nuclear Information System (INIS)

    Slack, J.; Norton, J.L.; Malkoske, G.R.

    2003-01-01

    therapy machines. Today the majority of the cancer therapy cobalt-60 sources used in the world are manufactured using material from the NRU reactor in Chalk River. The same technology that was used for producing cobalt-60 in a research reactor was then adapted and transferred for use in a CANDU power reactor. In the early 1970s, in co-operation with Ontario Power Generation (formerly Ontario Hydro), bulk cobalt-60 production was initiated in the four Pickering A CANDU reactors located east of Toronto. This was the first full scale production of millions of curies of cobalt-60 per year. As the demand and acceptance of sterilization of medical products grew, MDS Nordion expanded its bulk supply by installing the proprietary Canadian technology in additional CANDUs. Over the years MDS Nordion has partnered with CANDU reactor owners to produce cobalt-60 at various sites. CANDU reactors that have, or are still producing cobalt-60, include Pickering A, Pickering B, Gentilly 2, Embalse in Argentina, and Bruce B. In conclusion, the technology for cobalt-60 production in CANDU reactors, designed and developed by MDS Nordion and Atomic Energy of Canada, has been safely, economically and successfully employed in CANDU reactors with over 195 reactor years of production. Today over forty percent of the world's disposable medical supplies are made safer through sterilization using cobalt-60 sources from MDS Nordion. Over the past 40 years, MDS Nordion with its CANDU reactor owner partners, has safely and reliably shipped more than 500 million curies of cobalt-60 sources to customers around the world. MDS Nordion is presently adding three more CANDU power reactors to its supply chain. These three additional cobalt producing CANDU's will help supplement the ability of the health care industry to provide safe, sterile, medical disposable products to people around the world. As new applications for cobalt-60 are identified, and the demand for bulk cobalt-60 increases, MDS Nordion and AECL

  4. 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.

  5. 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

  6. The NRU blowdown test facility commissioning program

    Energy Technology Data Exchange (ETDEWEB)

    Walsworth, J A; Zanatta, R J; Yamazaki, A R; Semeniuk, D D; Wong, W; Dickson, L W; Ferris, C E; Burton, D H [Atomic Energy of Canada Ltd., Chalk River, ON (Canada). Chalk River Nuclear Labs.

    1990-12-31

    A major experimental program has been established at the Chalk River Nuclear Laboratories (CRL) that will provide essential data on the thermal and mechanical behaviour of nuclear fuel under abnormal reactor operating conditions and on the transient release, transport and deposition of fission product activity from severely degraded fuel. A number of severe fuel damage (SFD) experiments will be conducted within the Blowdown Test Facility (BTF) at CRL. A series of experiments are being conducted to commission this new facility prior to the SFD program. This paper describes the features and the commissioning program for the BTF. A development and testing program is described for critical components used on the reactor test section. In-reactor commissioning with a fuel assembly simulator commenced in 1989 June and preliminary results are given. The paper also outlines plans for future all-effects, in-reactor tests of CANDU-designed fuel. (author). 11 refs., 3 tabs., 7 figs.

  7. Assessment of the thorium fuel cycle in power reactors

    International Nuclear Information System (INIS)

    Kasten, P.R.; Homan, F.J.; Allen, E.J.

    1977-01-01

    A study was conducted at Oak Ridge National Laboratory to evaluate the role of thorium fuel cycles in power reactors. Three thermal reactor systems were considered: Light Water Reactors (LWRs); High-Temperature Gas-Cooled Reactors (HTGRs); and Heavy Water Reactors (HWRs) of the Canadian Deuterium Uranium Reactor (CANDU) type; most of the effort was on these systems. A summary comparing thorium and uranium fuel cycles in Fast Breeder Reactors (FBRs) was also compiled

  8. A floating desalination/co-generation system using the KLT-40 reactor and Canadian RO desalination technology

    International Nuclear Information System (INIS)

    Humphries, J.R.; Davies, K.

    2000-01-01

    indicated that under these conditions approximately 100,000 m 3 /d of potable water can be produced The use of preheated feedwater results in an improvement in water production efficiency of up to about 15% relative to a system operating at the ambient seawater temperature. This preliminary design study has shown that significant improvements in the cost of water production can be achieved through this 'marriage' of Russian small reactor technology and Canadian RO technology. The potential benefits warrant further detailed evaluation followed by a demonstration project. (author)

  9. The Canadian Fusion Fuels Technology Project

    International Nuclear Information System (INIS)

    Dautovich, D.P.; Gierszewski, P.J.; Wong, K.Y.; Stasko, R.R.; Burnham, C.D.

    1987-04-01

    The Canadian Fusion Fuels Technology Project (CFFTP) is a national project whose aim is to develop capability in tritium and robotics technologies for application to international fusion development programs. Activities over the first five years have brought substantial interaction with the world's leading projects such as Tokamak Fusion Test Reactor (TFTR), the Joint European Torus (JET), and the Next European Torus (NET), Canadian R and D and engineering services, and hardware are in demand as these major projects prepare for tritium operation leading to the demonstration of energy breakeven around 1990. Global planning is underway for the next generation ignition experiment. It is anticipated this will provide increased opportunity for CFFTP and its contractors among industry, universities and governmental laboratories

  10. Canadian CANDU fuel development program and recent fuel operating experience

    International Nuclear Information System (INIS)

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

    1999-01-01

    This paper reviews the performance of the CANDU fuel in the Canadian CANDU reactors in 1997 and 1998. The operating experience demonstrates that the CANDU fuel has performed very well. Over the 2-year period, the fuel-bundle defect rate for all bundles irradiated in the Canadian CANDU reactors has remained very low, at between 0.006% to 0.016%. On a fuel element basis, this represents an element defect rate of less than about 0.0005%. One of the reasons for the good fuel performance is the support provided by the Canadian fuel research and development programs. These programs address operational issues and provide evolutionary improvements to the fuel products. The programs consist of the Fuel Technology Program, funded by the CANDU Owners Group, and the Advanced Fuel and Fuel Cycles Technology Program, funded by Atomic Energy of Canada Ltd. These 2 programs, which have been in place for many years, complement each other by sharing expert resources and experimental facilities. This paper describes the programs in 1999/2000, to provide an overview of the scope of the programs and the issues that these programs address. (author)

  11. Technology transfer. Its contribution to the Canadian nuclear industry

    International Nuclear Information System (INIS)

    Perryman, E.C.W.

    1977-01-01

    Technology transfer from the Laboratories of Atomic Energy of Canada Limited is discussed in relation to the birth and growth of the Canadian Nuclear Industry. The evolution of the laboratories and their changing emphasis during the commercialization of the CANDU reactor system is described

  12. Research reactor status for future nuclear research in Europe

    Energy Technology Data Exchange (ETDEWEB)

    Raymond, Patrick; Bignan, Gilles; Guidez, Joel [Commissariat a l' Energie Atomique - CEA (France)

    2010-07-01

    Scandinavia). The nuclear renaissance is effective worldwide, with 33 power plants today under construction in the world and a lot of projects in discussion or in preparation in various countries (England, Italy, South Africa, USA...). In Europe, some countries, who phase-out the development nuclear energy, are also coming back in nuclear perspectives as Sweden, Italy, England, Poland,.. All these facts begin to give more work to the MTR (material testing reactors) for testing new materials and new fuels to improve their capacities and their performances. For the ZPR (Zero Power Reactors) test with new fuels allowing additives to suppress Bore utilisation, or allowing to reduce uranium consumption, will be necessary in the near future. For the safety dedicated reactors, test for compliance to last safety requirements are necessary. In this field the refurbishment of the CABRI reactor for Reactivity Insertion Accident studies, is now almost finished for test that should begin in 2010. For the radio isotope production the world demand is increasing year after year, especially for {sup 99}Mo, used in about 70 millions of medicine procedures each year in the world. Today 95% of this world production is assumed by five reactors: HFR (Netherlands), OSIRIS (France), SAFARI (South Africa), BRII (Belgium), and NRU (Canada). The youngest is OSIRIS (41 years) and should be close in 2015. Due to ageing problems NRU and HFR were shut down in 2009 for necessary repair. These points have conduced to some radio isotopes crisis in 2009. This paper explains some projects in line for the future to avoid this type of problems (FRMII initiative, RJH utilisation and PALLAS project). For training activities, needs are huge with nuclear renaissance, especially for the new countries coming back in nuclear field. It will also give a lot of opportunities to low power reactors and to the universities reactors. This paper also provides information on the status of the new projects such as the JHR ongoing

  13. Research reactor status for future nuclear research in Europe

    International Nuclear Information System (INIS)

    Raymond, Patrick; Bignan, Gilles; Guidez, Joel

    2010-01-01

    renaissance is effective worldwide, with 33 power plants today under construction in the world and a lot of projects in discussion or in preparation in various countries (England, Italy, South Africa, USA...). In Europe, some countries, who phase-out the development nuclear energy, are also coming back in nuclear perspectives as Sweden, Italy, England, Poland,.. All these facts begin to give more work to the MTR (material testing reactors) for testing new materials and new fuels to improve their capacities and their performances. For the ZPR (Zero Power Reactors) test with new fuels allowing additives to suppress Bore utilisation, or allowing to reduce uranium consumption, will be necessary in the near future. For the safety dedicated reactors, test for compliance to last safety requirements are necessary. In this field the refurbishment of the CABRI reactor for Reactivity Insertion Accident studies, is now almost finished for test that should begin in 2010. For the radio isotope production the world demand is increasing year after year, especially for 99 Mo, used in about 70 millions of medicine procedures each year in the world. Today 95% of this world production is assumed by five reactors: HFR (Netherlands), OSIRIS (France), SAFARI (South Africa), BRII (Belgium), and NRU (Canada). The youngest is OSIRIS (41 years) and should be close in 2015. Due to ageing problems NRU and HFR were shut down in 2009 for necessary repair. These points have conduced to some radio isotopes crisis in 2009. This paper explains some projects in line for the future to avoid this type of problems (FRMII initiative, RJH utilisation and PALLAS project). For training activities, needs are huge with nuclear renaissance, especially for the new countries coming back in nuclear field. It will also give a lot of opportunities to low power reactors and to the universities reactors. This paper also provides information on the status of the new projects such as the JHR ongoing construction on the Cadarache

  14. The 25 MW Super Near Boiling nuclear reactor (SNB25) for supplying co-generation energy to an Arctic Canadian Forces Base

    Energy Technology Data Exchange (ETDEWEB)

    Bonin, H.W.; Paquette, S.; Boucher, P.J. [Royal Military College of Canada, Dept. of Chemistry and Chemical Engineering, Kingston, Ontario (Canada)

    2014-12-15

    Nuclear energy represents a better alternative for the supply of heat and electricity to the Canadian Forces bases in the Arctic (CFS Alert and CFB Nanisivik). In this context, the Super Near-Boiling 25-MWth reactor (SNB25) has been designed as a small unpressurized LWR that displays inherent safety and is intended to run in automatic mode. The reactor employs TRISO fuel particles (20% enrichment) in zirconium-sheathed fuel rods, and is light water cooled and moderated with a normal output temperature is 95 {sup o} C at atmospheric pressure. Control is via 133 control rods and six adjustable radial reflector plates. The design work used the probabilistic simulation code MCNP 5 and the deterministic code WIMS-AECL Version 3.1, permitting a code-to-code comparison of the results. Inherent safety was confirmed and is mostly due to the large negative void reactivity coefficient of -5.17 mk per % void. A kinetic model that includes thermal-hydraulics calculations was developed to determine the reactor's behaviour in transient states, and the results further confirm the inherent safety. Large power excursions temperatures that could compromise structural integrity cannot be produced. If the coolant/moderator temperature exceeds the saturation temperature of 100 {sup o} C, the coolant begins to boil and the large negative void coefficient causes the reactor to become subcritical in 0.84 seconds. The SNB25 reactor's core life exceeds 12 years between refuellings. A group of 4 SNB25 reactors meets both the heating and electricity requirements of a base like CFB Nanisivik via a hot water network and through an organic Rankine cycle conversion plant. (author)

  15. The risk of shortage of radioelements at medical use must not lead to overlook the reactors safety that produce them

    International Nuclear Information System (INIS)

    2009-01-01

    As the reactors supplying the world production of radioelements for medical use have over 40 years of operation, the nuclear safety authority alerts the stake holders on the necessity to prevent the conflicts between public health and nuclear safety in the production of these elements; Asn estimates that the solution is not to extend the lifetime of the reactors but goes for a new international concerted approach. The most of the present production comes from five old reactors: N.R.U. at Chalk river (Canada, 40%), H.F.R. at Petten (Netherlands, 30%), Safari at Pelindaba (South Africa, 10%) B.R.2 at Mol (Belgium, 9%) and Osiris at Saclay (France, 5%). In this context, Asn organised in january 2009 a seminar on the safety-availability of facilities of radio-isotopes production with safety authorities of the concerned countries. Nea organised a seminar on the radiopharmaceuticals supply at the end of january 2009. (N.C.)

  16. Government intervention in the Canadian nuclear industry

    International Nuclear Information System (INIS)

    Doern, G.B.

    1980-01-01

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

  17. Experience in the application of NUSS and Canadian quality assurance standards for overseas CANDU projects

    International Nuclear Information System (INIS)

    Simmons, R.B.V.; Thomas, R.A.

    1984-10-01

    The Canadian QA standards - the CSA Z299 series for manufacture, which first appeared in 1975, and the CSA N286 series for all other phases of plant life which appeared in 1979, have been based on experience with the CANDU reactor program. The CSA Technical Committee responsible for issue and for updating the two series have a direct liaison with the IAEA Technical Review Committee for Quality Assurance. Ontario Hydro, which has a substantial commitment to nuclear power using CANDU reactors, has played a large part in the Canadian QA standards program. Atomic Energy of Canada Limited has also taken a major part in the development of CSA QA standards. As a main contractor the Company has supplied CANDU plants in Canada and to Argentina, South Korea and Romania. Because of the compatibility of the Canadian QA standards used, the Embalse plant in Argentina and the Wolsung 1 plant in Korea, are essentially in compliance with NUSS QA standards. The plant under construction at Cernavoda in Romania similarly follows Canadian QA standards

  18. A high-speed data acquisition system to measure low-level current from self-powered flux detectors in CANDU nuclear reactors

    International Nuclear Information System (INIS)

    Lawrence, C.B.; Hall, D.S.

    1982-05-01

    Self-powered flux detectors are used in CANDU nuclear power reactors to determine the spatial neutron flux distribution in the reactor core for use by both the reactor control and safety systems. To establish the dynamic response of different types of flux detectors, the Chalk River Nuclear Laboratories have an ongoing experimental irradiation program in the NRU research reactor for which a data acquistion system has been developed. The system described in this paper is used to measure the currents from the detectors both at a slow, regular logging interval, and at a rapid, adaptive rate following a reactor shutdown. Currents that range from 100 pA to 1 mA full scale can be measured from up to 38 detectors and stored at sampling rates of up to 20 samples per second. The dynamic characteristics of the detectors can be computed from the stored records. The data acquisition system comprises a DEC LSI-11/23 microcomputer, dual cartridge disks, floppy disks, a hard copy and a video display terminal. The RT-11 operating system is used and all application programs are written in FORTRAN

  19. The Canadian CANDU fuel development program and recent fuel operating experience

    International Nuclear Information System (INIS)

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

    1999-01-01

    This paper reviews the performance of the CANDU fuel in the Canadian CANDU reactors in 1997 and 1998. The operating experience demonstrates that the CANDU fuel has performed very well. Over the two-year period, the fuel-bundle defect rate for all bundles irradiated in the Canadian CANDU reactors has remained very low, at between 0.006% to 0.016%. On a fuel element basis, this represents an element defect rate of less than about 0.0005%. One of the reasons for the good fuel performance is the support provided by the Canadian fuel research and development programs. These programs address operational issues and provide evolutionary improvements to the fuel products. The programs consist of the Fuel Technology Program, funded by the CANDU Owners Group, and the Advanced Fuel and Fuel Cycles Technology Program, funded by Atomic Energy of Canada Ltd. These two programs, which have been in place for many years, complement each other by sharing expert resources and experimental facilities. This paper describes the programs in 1999/2000, to provide an overview of the scope of the programs and the issues that these programs address. (author)

  20. Canadian and United States regulatory models compared: doses from atmospheric pathways

    International Nuclear Information System (INIS)

    Peterson, S-R.

    1997-01-01

    CANDU reactors sold offshore are licensed primarily to satisfy Canadian Regulations. For radioactive emissions during normal operation, the Canadian Standards Association's CAN/CSA-N288.1-M87 is used. This standard provides guidelines and methodologies for calculating a rate of radionuclide release that exposes a member of the public to the annual dose limit. To calculate doses from air concentrations, either CSA-N288.1 or the Regulatory Guide 1.109 of the United States Nuclear Regulatory Commission, which has already been used to license light-water reactors in these countries, may be used. When dose predictions from CSA-N288.1 are compared with those from the U.S. Regulatory Guides, the differences in projected doses raise questions about the predictions. This report explains differences between the two models for ingestion, inhalation, external and immersion doses

  1. Proceedings of the seventeenth annual Canadian Nuclear Society conference

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-31

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

  2. Proceedings of the seventeenth annual Canadian Nuclear Society conference

    International Nuclear Information System (INIS)

    1996-01-01

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

  3. Safety requirements in the design of research reactors: A Canadian perspective

    International Nuclear Information System (INIS)

    Lee, A.G.; Langman, V.J.

    2000-01-01

    In Canada, the formal development of safety requirements for the design of research reactors in general began under an inter-organizational Small Reactor Criteria Committee. This committee developed safety and licensing criteria for use by several small reactor projects in their licensing discussions with the Atomic Energy Control Board. The small reactor projects or facilities represented included the MAPLE-X10 reactor, the proposed SES-10 heating reactor and its prototype, the SDR reactor at the Whiteshell Laboratories, the Korea Multipurpose Research Reactor (a.k.a., HANARO) in Korea, the SCORE project, and the McMaster University Nuclear Reactor. The top level set of criteria which form a safety philosophy and serve as a framework for more detailed developments was presented at an IAEA Conference in 1989. AECL continued this work to develop safety principles and design criteria for new small reactors. The first major application of this work has been to the design, safety analysis and licensing of the MAPLE 1 and 2 reactors for the MDS Nordion Medical Isotope Reactor Project. This paper provides an overview of the safety principles and design criteria. Examples of an implementation of these safety principles and design criteria are drawn from the work to design the MAPLE 1 and 2 reactors. (author)

  4. The 25 MW super near boiling nuclear reactor (SNB25) for supplying co-generation energy to an Arctic Canadian Forces base

    Energy Technology Data Exchange (ETDEWEB)

    Bonin, H.W.; Paquette, S.; Boucher, P.J., E-mail: bonin-h@rmc.ca [Royal Military College of Canada, Dept. of Chemistry and Chemical Engineering, Kingston, Ontario (Canada)

    2014-07-01

    Nuclear energy represents a better alternative for the supply of heat and electricity to the Canadian Forces bases in the Arctic (CFS Alert and CFB Nanisivik). In this context, the Super Near-Boiling 25-MWth reactor (SNB25) has been designed as a small unpressurized LWR that displays inherent safety and is intended to run in automatic mode. The reactor employs TRISO fuel particles (20% enrichment) in zirconium-sheathed fuel rods, and is light water cooled and moderated with a normal output temperature is 95{sup o}C at atmospheric pressure. Control is via 133 control rods and six adjustable radial reflector plates. The design work used the probabilistic simulation code MCNP 5 and the deterministic code WIMS-AECL Version 3.1, permitting a code-to-code comparison of the results. Inherent safety was confirmed and is mostly due to the large negative void reactivity coefficient of -5.17 mk per % void. A kinetic model that includes thermal-hydraulics calculations was developed to determine the reactor's behaviour in transient states, and the results further confirm the inherent safety. Large power excursions temperatures that could compromise structural integrity cannot be produced. If the coolant/moderator temperature exceeds the saturation temperature of 100{sup o}C, the coolant begins to boil and the large negative void coefficient causes the reactor to become subcritical in 0.84 seconds. The SNB25 reactor’s core life exceeds 12 years between refuellings. A group of 4 SNB25 reactors meets both the heating and electricity requirements of a base like CFB Nanisivik via a hot water network and through an organic Rankine cycle conversion plant. (author)

  5. The 25 MW super near boiling nuclear reactor (SNB25) for supplying co-generation energy to an Arctic Canadian Forces base

    International Nuclear Information System (INIS)

    Bonin, H.W.; Paquette, S.; Boucher, P.J.

    2014-01-01

    Nuclear energy represents a better alternative for the supply of heat and electricity to the Canadian Forces bases in the Arctic (CFS Alert and CFB Nanisivik). In this context, the Super Near-Boiling 25-MWth reactor (SNB25) has been designed as a small unpressurized LWR that displays inherent safety and is intended to run in automatic mode. The reactor employs TRISO fuel particles (20% enrichment) in zirconium-sheathed fuel rods, and is light water cooled and moderated with a normal output temperature is 95 o C at atmospheric pressure. Control is via 133 control rods and six adjustable radial reflector plates. The design work used the probabilistic simulation code MCNP 5 and the deterministic code WIMS-AECL Version 3.1, permitting a code-to-code comparison of the results. Inherent safety was confirmed and is mostly due to the large negative void reactivity coefficient of -5.17 mk per % void. A kinetic model that includes thermal-hydraulics calculations was developed to determine the reactor's behaviour in transient states, and the results further confirm the inherent safety. Large power excursions temperatures that could compromise structural integrity cannot be produced. If the coolant/moderator temperature exceeds the saturation temperature of 100 o C, the coolant begins to boil and the large negative void coefficient causes the reactor to become subcritical in 0.84 seconds. The SNB25 reactor’s core life exceeds 12 years between refuellings. A group of 4 SNB25 reactors meets both the heating and electricity requirements of a base like CFB Nanisivik via a hot water network and through an organic Rankine cycle conversion plant. (author)

  6. Linear parameter-varying modeling and control of the steam temperature in a Canadian SCWR

    Energy Technology Data Exchange (ETDEWEB)

    Sun, Peiwei, E-mail: sunpeiwei@mail.xjtu.edu.cn; Zhang, Jianmin; Su, Guanghui

    2017-03-15

    Highlights: • Nonlinearity of Canadian SCWR is analyzed based on step responses and Nyquist plots. • LPV model is derived through Jacobian linearization and curve fitting. • An output feedback H{sub ∞} controller is synthesized for the steam temperature. • The control performance is evaluated by step disturbances and wide range operation. • The controller can stabilize the system and reject the reactor power disturbance. - Abstract: The Canadian direct-cycle Supercritical Water-cooled Reactor (SCWR) is a pressure-tube type SCWR under development in Canada. The dynamics of the steam temperature have a high degree of nonlinearity and are highly sensitive to reactor power disturbances. Traditional gain scheduling control cannot theoretically guarantee stability for all operating regions. The control performance can also be deteriorated when the controllers are switched. In this paper, a linear parameter-varying (LPV) strategy is proposed to solve such problems. Jacobian linearization and curve fitting are applied to derive the LPV model, which is verified using a nonlinear dynamic model and determined to be sufficiently accurate for control studies. An output feedback H{sub ∞} controller is synthesized to stabilize the steam temperature system and reject reactor power disturbances. The LPV steam temperature controller is implemented using a nonlinear dynamic model, and step changes in the setpoints and typical load patterns are carried out in the testing process. It is demonstrated through numerical simulation that the LPV controller not only stabilizes the steam temperature under different disturbances but also efficiently rejects reactor power disturbances and suppresses the steam temperature variation at different power levels. The LPV approach is effective in solving control problems of the steam temperature in the Canadian SCWR.

  7. Key observations from a comprehensive FCC study on Canadian heavy gas oils from various origins: 1. Yield profiles in batch reactors

    Energy Technology Data Exchange (ETDEWEB)

    Ng, Siauw H.; Nakajima, Nobumasa [National Centre for Upgrading Technology, 1 Oil Patch Drive, Suite A202, Devon, Alberta (Canada T9G 1A8); Zhu, Yuxia [Research Institute of Petroleum Processing, 18 Xue Yuen Road, P.O. Box 914, Beijing 100083 (China); Humphries, Adrian [Albemarle Catalysts Company LP, 2625 Bay Area Blvd., Suite 250, Houston, TX 77058 (United States); Tsai, Thomas Y.R. [National Dong Hwa University, Hualien 974, Taiwan (ROC); Ding, Fuchen [Beijing Institute of Petrochemical Technology, Daxing, Beijing 102600 (China); Ling, Hao [East China University of Science and Technology, Shanghai 200237 (China); Yui, Sok [Syncrude Research Centre, 9421-17 Avenue, Edmonton, Alberta (Canada T6N 1H4)

    2006-06-15

    A series of cracking tests in a comprehensive study were conducted on separate occasions involving all or parts of 10 Canadian vacuum gas oil (VGO) feeds and a catalyst. VGOs were cracked in fixed- and fluid-bed microactivity test (MAT) units, the Advanced Cracking Evaluation (ACE) unit, and a modified ARCO riser reactor. Several important observations from this study were reported, including the effects of gasoline precursors on the maximum gasoline yields and aromatics in feeds on the conversion levels at which the maximum gasoline yields occurred. Yield profiles were found to be similar in shapes and relative positions between H{sub 2}S-free dry gas and catalytic coke for all but one of the feeds. Conversion and yield data obtained from the three batch reactors were compared and discussed. At a given conversion, correlations existed among the fixed- and fluid-bed MAT units, and the ACE for each product yield. A method to check the qualities of MAT and riser data was demonstrated by plotting the coke or total gas selectivity versus the gasoline selectivity. (author)

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

    International Nuclear Information System (INIS)

    1988-01-01

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

  9. Assessment of the National Research Universal Reactor Proposed New Stack Sampling Probe Location for Compliance with ANSI/HPS N13.1-1999

    Energy Technology Data Exchange (ETDEWEB)

    Glissmeyer, John A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Antonio, Ernest J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Flaherty, Julia E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2016-02-29

    This document reports on a series of tests conducted to assess the proposed air sampling location for the National Research Universal reactor (NRU) complex exhaust stack, located in Chalk River, Ontario, Canada, with respect to the applicable criteria regarding the placement of an air sampling probe. Due to the age of the equipment in the existing monitoring system, and the increasing difficulty in acquiring replacement parts to maintain this equipment, a more up-to-date system is planned to replace the current effluent monitoring system, and a new monitoring location has been proposed. The new sampling probe should be located within the exhaust stack according to the criteria established by the American National Standards Institute/Health Physics Society (ANSI/HPS) N13.1-1999, Sampling and Monitoring Releases of Airborne Radioactive Substances from the Stack and Ducts of Nuclear Facilities. These criteria address the capability of the sampling probe to extract a sample that represents the effluent stream. The internal Pacific Northwest National Laboratory (PNNL) project for this task was 65167, Atomic Energy Canada Ltd. Chalk River Effluent Duct Flow Qualification. The testing described in this document was guided by the Test Plan: Testing of the NRU Stack Air Sampling Position (TP-STMON-032).

  10. ZEEP: Canada's first nuclear reactor

    Energy Technology Data Exchange (ETDEWEB)

    Green, R.E.; Okazaki, A. [retired, Atomic Energy of Canada Limited, Chalk River, Ontario (Canada)

    2015-09-15

    In 1905 Albert Einstein published his historic paper on special relativity, which contained the equation E=mc 2. The significance of this mass-energy relationship became evident with the discovery of nuclear fission in 1939, when it was realized that large amounts of energy would be released in a fission chain reaction. Canadian scientists were involved in this field from the beginning and their efforts resulted in the startup in September 1945 of the ZEEP reactor at Chalk River, the first reactor to go critical outside the USA. In this paper we recall some of the events that led to the construction of ZEEP, and describe the role it played in the development of the Canadian nuclear energy program. (author)

  11. Annual report on activities 1986-1987

    International Nuclear Information System (INIS)

    1987-01-01

    More than 60 contracts valued at $2.3 million were committed in 1986-87. This brought the program for the period 1982-87 to an end on budget at a total expenditure of $16.5 million. Agreements was reached between AECL and Ontario Hydro for the continuation of Canadian Fusion Fuels Technology Project (CFFTP) for the period 1987-1992 with a total budget of $22 million. Irradiation tests of candidate solid breeder materials have commenced at the Nuclear Reactor Universal (NRU) research reactor at Chalk River Nuclear Laboratories (CRNL). CFFTP intends to develop the low-risk aqueous lithium salt blanket approach for application in the Engineering Test Reactor (ETR) class of next-step machines. An innovative concept for the detection of low energy beta particles could prove to be the heart of a compact, rugged yet sensitive alarming portable personal tritium dosimeter. The gas chromatography isotope separation process, which was successfully tested last year in the laboratory, continued to be one of the program's more exciting developments. CFFTP staff participated in design studies such as the Tokamak Ignition/Burn Experimental Reactor-USA (TIBER-II) and international fusion projects such as the Joint European Torus (JET), the Joint Research Commission (JRC) Ispra, The Next European Torus (NET), the Fusion Engineering Design Centre (FEDC), the Idaho National Engineering Laboratory (INEL) and the Tokamak Fusion Test Reactor (TFTR)

  12. Small reactors in the Canadian context: opportunities and challenges

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-07-01

    This presentation discusses the opportunities and challenges for small reactors in Canada. It concludes by suggesting that the success of small reactors in Canada will depend on a number of factors including private sector investment, access to international markets, stable, equitable and adaptable regulatory regime, public trust and technology.

  13. Canadian safeguards research and development in support of the IAEA

    International Nuclear Information System (INIS)

    1980-03-01

    Canada has established a safeguards research and development program whose purpose is to supplement the resources of the IAEA. The program of support is a coordinated effort for the development and application of safeguards techniques and instruments to reactors of Canadian design. This document sets forth those tasks that make up the program

  14. Assessment of terrorist threats to the Canadian energy sector

    Energy Technology Data Exchange (ETDEWEB)

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

    2006-03-15

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

  15. Assessment of terrorist threats to the Canadian energy sector

    International Nuclear Information System (INIS)

    Shull, A.

    2006-01-01

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

  16. Progress report, Physics and Health Sciences: Physics Section

    International Nuclear Information System (INIS)

    1990-01-01

    This report reviews the research and operational activities of the TASCC Division, the Physics Division, and the Fusion Office of Atomic Energy of Canada Ltd. TASCC, the 8π spectrometer, the on-line isotope separator, and the large scattering chamber completed their first year of operation with results including the discovery of the first nucleus, 153 Dy, to exhibit more than one superdeformed band. DUALSPEC, the double neutron spectrometer at the NRU reactor, should be commissioned in 1990. Investigations were carried out into the cold fusion phenomenon with negative results. Studies on food irradiation showed that the induced radioactivity is less than 0.25 percent of that already present. Substantial funding commitments have been made to the Sudbury Neutrino Observatory. Theoretical work on multiple scattering of heavy ions appears to be expandable to relativistic energies. Canadian contributions to the NET project have been endorsed and continue to grow

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

    International Nuclear Information System (INIS)

    Rzentkowski, G.; Khouaja, H.

    2014-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-07-01

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

  19. Safety features of the MAPLE-X10 reactor design

    International Nuclear Information System (INIS)

    Lee, A.G.; Bishop, W.E.; Heeds, W.

    1990-09-01

    The MAPLE-X10 reactor is a D 2 0-reflected, H 2 0-cooled and -moderated pool-type reactor under construction at the Chalk River Nuclear Laboratories. This 10-MW reactor will produce key medical and industrial radio-isotopes such as 99 Mo, 125 I, and 192 Ir. As the prototype for the MAPLE research reactor concept, the reactor incorporates diverse safety features both inherent in the design and in the added engineered systems. The safety requirements are analogous to those of the Canadian CANDU power reactor since standards for the licensing of new research reactors have not been developed yet by the licensing authority in Canada

  20. Canadian fuel development program

    International Nuclear Information System (INIS)

    Gacesa, M.; Young, E.G.

    1992-11-01

    CANDU power reactor fuel has demonstrated an enviable operational record. More than 99.9% of the bundles irradiated have provided defect-free service. Defect excursions are responsible for the majority of reported defects. In some cases research and development effort is necessary to resolve these problems. In addition, development initiatives are also directed at improvements of the current design or reduction of fueling cost. The majority of the funding for this effort has been provided by COG (CANDU Owners' Group) over the past 10 to 15 years. This paper contains an overview of some key fuel technology programs within COG. The CANDU reactor is unique among the world's power reactors in its flexibility and its ability to use a number of different fuel cycles. An active program of analysis and development, to demonstrate the viability of different fuel cycles in CANDU, has been funded by AECL in parallel with the work on the natural uranium cycle. Market forces and advances in technology have obliged us to reassess and refocus some parts of our effort in this area, and significant success has been achieved in integrating all the Canadian efforts in this area. This paper contains a brief summary of some key components of the advanced fuel cycle program. (Author) 4 figs., tab., 18 refs

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

    International Nuclear Information System (INIS)

    1985-03-01

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

  2. Certification of Canadian nuclear power plant personnel

    International Nuclear Information System (INIS)

    Newbury, F.

    2014-01-01

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

  3. Safety features of the MAPLE-X10 reactor design

    International Nuclear Information System (INIS)

    Lee, A.G.; Bishop, W.E.; Heeds, W.

    1990-01-01

    This paper reports on the MAPLE-X10 reactor D 2 O-reflected, H 2 O-cooled and -moderated pool- type reactor, under construction at the Chalk River Nuclear Laboratories. This 10-MW will produce key medical and industrial radioisotopes such as 99 Mo, 125 I, and 192 Ir. The prototype for the MAPLE research reactor concept, the reactor incorporates diverse safety features both inherent in the design and in the added engineered systems. The safety requirements are analogous to those of the Canadian CANDU power reactor as standards for the licensing of new research reactors have not been developed by the licensing authority in Canada

  4. Intervention of the Canadian Nuclear Association to the National Energy Board

    International Nuclear Information System (INIS)

    1982-01-01

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

  5. Canadian fuel development program in 1997/98

    International Nuclear Information System (INIS)

    Lau, J.H.; Kohn, E.; Sejnoha, R.; Cox, D.S.; Macici, N.N.; Steed, R.G.

    1997-01-01

    This paper describes the CANDU fuel development activities in Canada during 1997 through 1998. The activities include those of the Fuel Technology Program sponsored by the CANDU Owners Group. The goal of the Fuel Technology Program is to maintain and improve the reliability, economics and safety of CANDU fuel in operating reactors. These activities, therefore, concentrate on the present designs of 28-element and 37-element fuel bundles. The Canadian fuel development activities also include those of the Advanced Fuel and Fuel Cycle Technology Program at AECL. These activities concentrate on the development of advanced fuel designs and advanced fuel cycles, which among other advantages, can reduce the capital and fuelling costs, maintain operating margins in aging reactors, improve natural-uranium utilization, and reduce the amount of spent fuel. (author)

  6. Molten salt small modular reactors (MSSMRs): from DMSR to SmAHTR

    International Nuclear Information System (INIS)

    LeBlanc, D.

    2013-01-01

    Molten salt reactors were developed extensively from the 1950s to 1970s as a thermal breeder alternative on the Thorium-U233 cycle. Simplified designs running as fluid fuel convertors without salt processing as well as TRISO fueled, salt cooled reactors both hold much promise as potential small modular reactors. A background will be presented along with the most likely routes forward for a Canadian development program. (author)

  7. FISS: a computer program for reactor systems studies

    International Nuclear Information System (INIS)

    Tamm, H.; Sherman, G.R.; Wright, J.H.; Nieman, R.E.

    1979-08-01

    ΣFISSΣ is a computer code for use in investigating alternative fuel cycle strategies for Canadian and world nuclear programs. The code performs a system simulation accounting for dynamic effects of growing nuclear systems. Facilities in the model include storage for irradiated fuel, mines, plants for enrichment, fuel fabrication, fuel reprocessing and heavy water, and reactors. FISS is particularly useful for comparing various reactor strategies and studying sensitivities of resource consumption, capital investment and energy costs with changes in fuel cycle parameters, reactor parameters and financial variables. (author)

  8. State of the art of nuclear facilities with organic cooled reactors

    International Nuclear Information System (INIS)

    Brede, O.

    1984-01-01

    USA, Canadian, and USSR activities aimed at developing nuclear facilities with organic cooled reactors are summarized. The facilities OMRE, PNPF, WR-1, and ARBUS are described, discussing in particular the problems of the chemistry of organic coolants. Finally, problems of further development and prospects of the application of organic cooled reactors are briefly outlined. (author)

  9. Dosimetry aspects of the new Canadian MAPLE-X10 reactor

    International Nuclear Information System (INIS)

    Lidstone, R.F.; Wilkin, G.B.

    1994-01-01

    Atomic Energy of Canada Limited is building the 10-MW t MAPLE-X10 reactor facility as a dedicated producer of medical and industrial radioisotopes. Dosimetry aspects of the MAPLE-X10 nuclear design include the calculated thermal and fast neutron flux distributions throughout the reactor assembly and the rate of heat generation in reactor materials and components. Examples of the resolution of design issues are also presented, such as the use of fission counters and ion chambers to provide diverse methods of detecting neutron flux levels and the use of the difference between photon and neutron signals to guard against the effects of downgrading of the heavy-water reflector. Computer codes employed in the calculations include MCNP, ONEDANT, WIMS-AECL, and 3DDT

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

    International Nuclear Information System (INIS)

    Lepp, R.M.

    1990-01-01

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

  11. Uranium exports could match oil imports. [status and prospects of the Canadian uranium industry

    Energy Technology Data Exchange (ETDEWEB)

    McIntyre, H C

    1977-04-01

    Apart from a temporary embargo while safeguards are negotiated, the Canadian government limits uranium exports so as to guarantee fuel for every Canadian reactor built or planned for 30 years. On the basis of present known reserves of 172 Gg of 'cheap' U/sub 3/O/sub 8/ and 33 of 'dear', that would mean phasing out exports after the mid 1980's, but probably much more 'dear' uranium remains to be discovered. Provincial taxation and restrictions on foreign ownership may be limitations. Discoveries range over eleven areas, but production capacity at present is 14190 Mg/d from Ontario and 3400 from Saskatchewan, with 8800 mothballed and 4860 planned or being rehabilitated. The price has jumped to $95/kg, so that uranium exports may cover half the cost of oil imports. All producers use sulfuric acid leaching, except Eldorado, which uses carbonate leaching; a process using tertiary amine is being developed. Development of the organic-cooled Th//sup 233/U fuelled reactor may greatly extend fuel resources.

  12. Pressurized heavy-water reactor safety

    International Nuclear Information System (INIS)

    Pease, L.; Wilson, R.

    1977-09-01

    CANDU-PWR type reactors routinely release small amounts of radioactive liquids and gases and large quantities of low-grade waste heat. Radioactive emissions are usually below 1% of the derived release limits based on ICRP limits. Waste heat is common to all power plants and is not foreseen as a problem in Canadian conditions. Risk analysis shows a very low accident probability for CANDU type reactors. Multiple barriers to release of radionuclides, quality assurance, control, and inspection, containment systems, the shutdown system, the ECCS, and leak-before-break design, would all combine to mitigate the effects of an accident. (E.C.B.)

  13. Present status of irradiation tests on tritium breeding blanket for fusion reactor

    International Nuclear Information System (INIS)

    Futamura, Yoshiaki; Sagawa, Hisashi; Shimakawa, Satoshi; Tsuchiya, Kunihiko; Kuroda, Toshimasa; Kawamura, Hiroshi.

    1994-01-01

    To develop a tritium breeding blanket for a fusion reactor, irradiation tests in fission reactors are indispensable for obtaining data on irradiation effects on materials, and neutronics/thermal characteristics and tritium production/recovery performance of the blanket. Various irradiation tests have been conducted in the world, especially to investigate tritium release characteristics from tritium breeding and neutron multiplier materials, and materials integrity under irradiation. In Japan, VOM experiments at JRR-2 for ceramic breeders and experiments at JMTR for ceramic breeders and beryllium as a neutron multiplier have been performed. Several universities have also investigated ceramic breeders. In the EC, the EXOTIC experiments at HFR in the Netherlands and the SIBELIUS, the LILA, the LISA and the MOZART experiments for ceramic breeders have carried out. In Canada, NRU has been used for the CRITIC experiments. The TRIO experiments at ORR(ORNL), experiments at RTNS-II, FUBR and ATR have been conducted in the USA. The last two are experiments with high neutron fluence aiming at investigating materials integrity under irradiation. The BEATRIX-I and -II experiments have proceeded under international collaboration of Japan, Canada, the EC and the USA. This report shows the present status of these irradiation tests following a review of the blanket design in the ITER CDA(Conceptual Design Activity). (author)

  14. Formulating the Canadian regulatory position on severe accidents

    International Nuclear Information System (INIS)

    Viktorov, Alex

    2006-01-01

    In response to the increasing potential of new nuclear build in Canada, and as part of documentation harmonization effort, CNSC staff has initiated development of requirements for design of nuclear power plants. These requirements build both on the IAEA standards, most notably, NS-R-1, and the Canadian practices and experience. The three safety objectives, formulated by the IAEA, are adopted, and Safety Goals are proposed consistent with the international trend. This Canadian standard will require, for the first time, explicit consideration of severe accidents in design and safety assessments. Specific requirements are formulated for several plant systems that assure an effective fourth level of defence in depth. Available results from probabilistic safety assessments indicate that the risks posed by severe accidents are acceptably low. Nevertheless, such risks are not negligible. CNSC staff considers that severe accident management (SAM) represents the most practical way to achieve risk reduction with a moderate effort. Ultimately, SAM actions are aimed at bringing the reactor, and the plant in general, into a controlled and stable state. For the operating reactors, SAM provides an additional defense barrier against the consequences of those accidents that fall beyond the scope of events considered in the reactor design basis. The establishment of a SAM program ensures availability of the information, procedures, and resources necessary to take full advantage of existing plant capabilities to arrest core degradation, and prevent or mitigate large releases of radioactive material. To the extent practicable, a SAM program builds on the existing emergency operating procedures and makes use of the plant design capabilities. On this basis, the CNSC requested nuclear power reactor licensees to develop and implement SAM at all operating reactors. To be able to demonstrate compliance with requirements for plant design and severe accident management, it is necessary to

  15. The Canadian Safeguards Support Program - A future outlook

    International Nuclear Information System (INIS)

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

    2001-01-01

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

  16. The application of nuclear energy to the Canadian chemical process industry

    International Nuclear Information System (INIS)

    Robertson, R.F.S.

    1976-03-01

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

  17. The "Canadian" in Canadian Children's Literature.

    Science.gov (United States)

    Bainbridge, Joyce; Wolodko, Brenda

    2001-01-01

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

  18. 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)

  19. Canadian contributions to the safety and environmental aspects of fusion

    International Nuclear Information System (INIS)

    Stasko, R.; Wong, K.

    1987-05-01

    Since next-step fusion devices will be fuelled with mixtures of tritium and deuterium, the knowledge base and tritium handling experience associated with the operation of CANDU reactors is viewed as relevant to the development of safe fusion technology. Fusion safety issues will be compared with fission safety experience, after which specific Canadian activities in support of fusion safety will be overviewed. In addition, recommendations for appropriate fusion safety criteria will be summarized. 18 refs

  20. Distinctive safety aspects of the CANDU-PHW reactor design

    International Nuclear Information System (INIS)

    Kugler, G.

    1980-01-01

    Two lectures are presented in this report. They were prepared in response to a request from IAEA to provide information on the 'Special characteristics of the safety analysis of heavy water reactors' to delegates from member states attending the Interregional Training Course on Safety Analysis Review, held at Karlsruhe, November 19 to December 20, 1979. The CANDU-PHW reactor is used as a model for discussion. The first lecture describes the distinctive features of the CANDU reactor and how they impact on reactor safety. In the second lecture the Canadian safety philosophy, the safety design objective, and other selected topics on reactor safety analysis are discussed. The material in this report was selected with a view to assisting those not familiar with the CANDU heavy water reactor design in evaluating the distinctive safety aspects of these reactors. (auth)

  1. The Canadian Dollar and the Dutch and Canadian Diseases

    Directory of Open Access Journals (Sweden)

    Serge Coulombe

    2013-10-01

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

  2. Fabrication and irradiation testing of LEU [low enriched uranium] fuels at CRNL status as of 1987 September

    International Nuclear Information System (INIS)

    Sears, D.F.; Berthiaume, L.C.; Herbert, L.N.

    1987-01-01

    The current status of Chalk River Nuclear Laboratories' (CRNL) program to develop and test low-enriched uranium (LEU), proliferation-resistant fuels for use in research reactors is reviewed. CRNL's fuel manufacturing process has been qualified by the successful demonstration irradiation of 7 full-size rods in the NRU reactor. Now industrial-scale production equipment has been commissioned, and a fuel-fabrication campaign for 30 NRU rods and a MAPLE-X core is underway. Excess capacity could be used for commercial fuel fabrication. In the irradiation testing program, mini-elements with deliberately included core surface defects performed well in-reactor, swelling by only 7 to 8 vol% at 93 atomic percent burnup of the original U-235. The additional restraint provided by the aluminium cladding which flowed into the defects during extrusion contributed to this good performance. Mini-elements containing a variety of particle size distributions were also successfully irradiated to 93 at% burnup in NRU, as part of a study to establish the optimum particle size distribution. Swelling was found to be proportional to the percentage of fines (<44μm particles) contained in the cores. The mini-elements containing the composition normally used at CRNL had swollen by 5.8 vol%, and mini-elements with a much higher percentage of fines had swollen by 6.8 vol%, at 93 at% burnup. Also, a program to develop LEU targets for Mo-99 production, via the technology developed to fabricate dispersed silicide fuel, has started, and preliminary scoping studies are underway. (Author)

  3. Design requirements for new nuclear reactor facilities in Canada

    International Nuclear Information System (INIS)

    Shim, S.; Ohn, M.; Harwood, C.

    2012-01-01

    The Canadian Nuclear Safety Commission (CNSC) has been establishing the regulatory framework for the efficient and effective licensing of new nuclear reactor facilities. This regulatory framework includes the documentation of the requirements for the design and safety analysis of new nuclear reactor facilities, regardless of size. For this purpose, the CNSC has published the design and safety analysis requirements in the following two sets of regulatory documents: 1. RD-337, Design of New Nuclear Power Plants and RD-310, Safety Analysis for Nuclear Power Plants; and 2. RD-367, Design of Small Reactor Facilities and RD-308, Deterministic Safety Analysis for Small Reactor Facilities. These regulatory documents have been modernized to document past practices and experience and to be consistent with national and international standards. These regulatory documents provide the requirements for the design and safety analysis at a high level presented in a hierarchical structure. These documents were developed in a technology neutral approach so that they can be applicable for a wide variety of water cooled reactor facilities. This paper highlights two particular aspects of these regulatory documents: The use of a graded approach to make the documents applicable for a wide variety of nuclear reactor facilities including nuclear power plants (NPPs) and small reactor facilities; and, Design requirements that are new and different from past Canadian practices. Finally, this paper presents some of the proposed changes in RD-337 to implement specific details of the recommendations of the CNSC Fukushima Task Force Report. Major changes were not needed as the 2008 version of RD-337 already contained requirements to address most of the lessons learned from the Fukushima event of March 2011. (author)

  4. Management of radioactive fuel wastes: the Canadian disposal program

    International Nuclear Information System (INIS)

    Boulton, J.

    1978-10-01

    This report describes the research and development program to verify and demonstrate the concepts for the safe, permanent disposal of radioactive fuel wastes from Canadian nuclear reactors. The program is concentrating on deep underground disposal in hard-rock formations. The nature of the radioactive wastes is described, and the options for storing, processing, packaging and disposing of them are outlined. The program to verify the proposed concept, select a suitable site and to build and operate a demonstration facility is described. (author)

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

    International Nuclear Information System (INIS)

    1964-06-01

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

  6. Evolution of on-power fuelling machines on Canadian natural uranium power reactors

    International Nuclear Information System (INIS)

    Isaac, P.

    1984-10-01

    The evolution of the on-power fuel changing process and fuelling machines on CANDU heavy-water pressure tube power reactors from the first nuclear power demonstration plant, 22 MWe NPD, to the latest plants now in design and development is described. The high availability of CANDU's is largely dependent on on-power fuelling. The on-power fuelling performance record of the 16 operating CANDU reactors, covering a 22 year period since the first plant became operational, is given. This shows that on-power fuel changing with light (unshielded), highly mobile and readily maintainable fuelling machines has been a success. The fuelling machines have contributed very little to the incapabilities of the plants and have been a key factor in placing CANDUs in the top ten list of world performance. Although fuel handling technology has reached a degree of maturity, refinements are continuing. A new single-ended fuel changing concept for horizontal reactors under development is described. This has the potential for reducing capital and operating costs for small reactors and increasing the fuelling capability of possible large reactors of the future

  7. Performance indicators for power reactors

    International Nuclear Information System (INIS)

    Gillies, C.; White, M.

    1995-11-01

    A review of Canadian and worldwide performance indicator definitions and data was performed to identify a set of indicators that could be used for comparison of performance among nuclear power plants. The results of this review are to be used as input to an AECB team developing a consistent set of performance indicators for measuring Canadian power reactor safety performance. To support the identification of performance indicators, a set of criteria was developed to assess the effectiveness of each indicator for meaningful comparison of performance information. The project identified a recommended set of performance indicators that could be used by AECB staff to compare the performance of Canadian nuclear power plants among themselves, and with international performance. The basis for selection of the recommended set and exclusion of others is provided. This report provides definitions and calculation methods for each recommended performance indicator. In addition, a spreadsheet has been developed for comparison and trending for the recommended set of indicators. Example trend graphs are included to demonstrate the use of the spreadsheet. (author). 50 refs., 11 tabs., 3 figs

  8. Homogeneous SLOWPOKE reactors for Mo-99/Tc-99m production in North America

    Energy Technology Data Exchange (ETDEWEB)

    Hilborn, J.W., E-mail: hilbovanw@sympatico.ca [Deep River, Ontario (Canada); Bonin, H.W. [Royal Military College of Canada, Kingston, Ontario (Canada)

    2014-07-01

    The 15 month shutdown of NRU in 2009 - 2010 caused an overall isotope shortage of approximately 30%; and in North America, the annual Tc-99m demand decreased from an estimated 20 million unit doses to about 15 million unit doses. Mo-99/Tc-99m is produced from HEU targets, irradiated in NRU for 11 days, and after chemical removal of uranium it is shipped to Nordion in Kanata, Ontario. Nordion further purifies the material and sends it to Lantheus Medical Imaging in the USA for manufacture of Mo-99 generators, which are then distributed to hundreds of hospital radiopharmacies throughout North America. One other American company, Covidien, manufactures and distributes Mo-99 generators like Lantheus, but they import bulk Mo-99 from Europe or South Africa. At the hospitals, Tc-99m is chemically extracted daily from the Mo-99 generators and loaded into syringes for immediate clinical use. Fortuitously, the 66 hour half-life of Mo-99 allows the replenishment of Tc-99m in the generator over a growth period of about 20 hours; and a generator can be 'milked' daily for up to two weeks. A more efficient model is the direct production and distribution of Tc-99m unit doses to regional hospitals from 10 'industrial' radiopharmacies located at existing licensed reactor sites in North America. A 20 kW homogeneous SLOWPOKE reactor at each site would deliver 15 litres of irradiated uranyl sulphate fuel solution daily to industrial-scale hot cells for extraction of Mo-99, which would be incorporated in large Mo-99/Tc-99m generators for extraction of Tc-99m five days a week; and the Low Enriched Uranium (LEU) would be recycled. Each automated hot-cell facility would be designed to load up to 7,000 Tc-99m syringes daily, for courier delivery to all of the Nuclear Medicine hospitals within a 3 hour average range by road transport. Typically, the delivered doses would be in the range 10 to 30 mCi. Assuming an average unit dose of 25 mCi at the hospital and 5 x 52

  9. Simplification of coding of NRU loop experiment software with dimensional generator

    International Nuclear Information System (INIS)

    Davis, R. S.

    2006-01-01

    The following are specific topics of this paper: 1.There is much creativity in the manner in which Dimensional Generator can be applied to a specific programming task [2]. This paper tells how Dimensional Generator was applied to a reactor-physics task. 2. In this first practical use, Dimensional Generator itself proved not to need change, but a better user interface was found necessary, essentially because the relevance of Dimensional Generator to reactor physics was initially underestimated. It is briefly described. 3. The use of Dimensional Generator helps make reactor-physics source code somewhat simpler. That is explained here with brief examples from BURFEL-PC and WIMSBURF. 4. Most importantly, with the help of Dimensional Generator, all erroneous physical expressions were automatically detected. The errors are detailed here (in spite of the author's embarrassment) because they show clearly, both in theory and in practice, how Dimensional Generator offers quality enhancement of reactor-physics programming. (authors)

  10. Radiocarbon dispersion around Canadian nuclear facilities

    International Nuclear Information System (INIS)

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

    1995-01-01

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

  11. The Canadian initiative to host the international thermonuclear experimental reactor

    Energy Technology Data Exchange (ETDEWEB)

    Dautovich, D P; James, R A [Canadian Fusion Fuels Technology Project, Mississauga, ON (Canada)

    1996-12-31

    At the time of the conference, the Canadian Nuclear Fuels Technology Project was making an innovative proposal whereby Ontario Hydro would provide space at its Darlington or Bruce sites as potential sites for the ITER project. An economic impact analysis, conducted by Ernst and Young, showed the potential economic benefits to Canada; other benefits could rather be considered to be scientific and technological benefits. A stable electrical supply grid, existing waste management infrastructure, an abundance of cheap power, and a skilled workforce, made Canada an attractive prospect. ITER, whatever its location, would require all of Ontario Hydro`s tritium. Canada was attractive as a neutral siting alternative, and had gained early Russian support.

  12. The Canadian initiative to host the international thermonuclear experimental reactor

    International Nuclear Information System (INIS)

    Dautovich, D.P.; James, R.A.

    1995-01-01

    At the time of the conference, the Canadian Nuclear Fuels Technology Project was making an innovative proposal whereby Ontario Hydro would provide space at its Darlington or Bruce sites as potential sites for the ITER project. An economic impact analysis, conducted by Ernst and Young, showed the potential economic benefits to Canada; other benefits could rather be considered to be scientific and technological benefits. A stable electrical supply grid, existing waste management infrastructure, an abundance of cheap power, and a skilled workforce, made Canada an attractive prospect. ITER, whatever its location, would require all of Ontario Hydro's tritium. Canada was attractive as a neutral siting alternative, and had gained early Russian support

  13. The regional control of the canadian energy production

    International Nuclear Information System (INIS)

    Petitlaurent, S.; Sarrazin, J.

    2004-12-01

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

  14. A conversion development program to LEU targets for medical isotope production in the MAPLE Facilities

    International Nuclear Information System (INIS)

    Malkoske, G.R.

    2000-01-01

    Historically, the production of molybdenum-99 in the NRU research reactors at Chalk River, Canada has been extracted from reactor targets employing highly enriched uranium (HEU). The molybdenum extraction process from the HEU targets provided predictable, consistent yields for our high-volume molybdenum production process. A reliable supply of HEU for the NRU research reactor targets has enabled MDS Nordion to develop a secure chain of medical isotope supply for the international nuclear medicine community. Each link of the isotope supply chain, from isotope production to patient application, has been established on a proven method of HEU target irradiation and processing. To ensure a continued reliable and timely supply of medical isotopes, the design of the MAPLE facilities was based on our established process - extraction of isotopes from HEU target material. However, in concert with the global trend to utilize low enriched uranium (LEU) in research reactors, MDS Nordion has launched a program to convert the MAPLE facilities to LEU targets. An initial feasibility study was initiated to identify the technical issues to convert the MAPLE targets from HEU to LEU. This paper will present the results of the feasibility study. It will also describe future challenges and opportunities in converting the MAPLE facilities to LEU targets for large scale, commercial medical isotope production. (author)

  15. The risk of shortage of radioelements at medical use must not lead to overlook the reactors safety that produce them; Le risque de penurie de radioelements a usage medical ne doit pas conduire a faire l'impasse sur la surete des reacteurs qui les produisent

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2009-07-01

    As the reactors supplying the world production of radioelements for medical use have over 40 years of operation, the nuclear safety authority alerts the stake holders on the necessity to prevent the conflicts between public health and nuclear safety in the production of these elements; Asn estimates that the solution is not to extend the lifetime of the reactors but goes for a new international concerted approach. The most of the present production comes from five old reactors: N.R.U. at Chalk river (Canada, 40%), H.F.R. at Petten (Netherlands, 30%), Safari at Pelindaba (South Africa, 10%) B.R.2 at Mol (Belgium, 9%) and Osiris at Saclay (France, 5%). In this context, Asn organised in january 2009 a seminar on the safety-availability of facilities of radio-isotopes production with safety authorities of the concerned countries. Nea organised a seminar on the radiopharmaceuticals supply at the end of january 2009. (N.C.)

  16. ROP design for Enhanced CANDU 6 reactor

    Energy Technology Data Exchange (ETDEWEB)

    Hu, J.; Scherbakova, D; Kastanya, D.; Ovanes, M. [Candu Energy Inc., Mississauga, Ontario (Canada)

    2011-07-01

    The Enhanced CANDU 6 (EC6) nuclear power plant is a mid-sized pressurized heavy water reactor design, based on the highly successful CANDU 6 (C6) family of power plants, upgraded to meet today's Canadian and international safety requirements and to satisfy Generation III expectations. The EC6 reactor is equipped with two independent Regional Overpower Protection (ROP) systems to prevent overpowers in the reactor fuel. The ROP system design, retaining the traditional C6 methodology, is determined to cover the End-of-Life (EOL) reactor core condition since the reactor operating/thermal margin gradually decreases as plant equipment ages. Several design changes have been incorporated into the reference C6 plant to mitigate the ageing effect on the ROP trip margin. This paper outlines the basis for the EC6 ROP physics design and presents the ROP related improvements made in the EC6 design to ensure that full power operation is not limited by the ROP throughout the entire life of the reactor. (author)

  17. A prediction method of the effect of radial heat flux distribution on critical heat flux in CANDU fuel bundles

    International Nuclear Information System (INIS)

    Yuan, Lan Qin; Yang, Jun; Harrison, Noel

    2014-01-01

    Fuel irradiation experiments to study fuel behaviors have been performed in the experimental loops of the National Research Universal (NRU) Reactor at Atomic Energy of Canada Limited (AECL) Chalk River Laboratories (CRL) in support of the development of new fuel technologies. Before initiating a fuel irradiation experiment, the experimental proposal must be approved to ensure that the test fuel strings put into the NRU loops meet safety margin requirements in critical heat flux (CHF). The fuel strings in irradiation experiments can have varying degrees of fuel enrichment and burnup, resulting in large variations in radial heat flux distribution (RFD). CHF experiments performed in Freon flow at CRL for full-scale bundle strings with a number of RFDs showed a strong effect of RFD on CHF. A prediction method was derived based on experimental CHF data to account for the RFD effect on CHF. It provides good CHF predictions for various RFDs as compared to the data. However, the range of the tested RFDs in the CHF experiments is not as wide as that required in the fuel irradiation experiments. The applicability of the prediction method needs to be examined for the RFDs beyond the range tested by the CHF experiments. The Canadian subchannel code ASSERT-PV was employed to simulate the CHF behavior for RFDs that would be encountered in fuel irradiation experiments. The CHF predictions using the derived method were compared with the ASSERT simulations. It was observed that the CHF predictions agree well with the ASSERT simulations in terms of CHF, confirming the applicability of the prediction method in fuel irradiation experiments. (author)

  18. Topical papers on heavy water, fuel fabrication and reactors

    International Nuclear Information System (INIS)

    1978-01-01

    A total of four papers is presented. The first contribution of the Federal Republic of Germany reviews the market situation for reactors and the relations between reactor producers and buyers as reflected in sales agreements. The second West German contribution gives a world-wide survey of fuel element production as well as of fuel and fuel element demand up to the year 2000. The Canadian paper discusses the future prospects of heavy-water production, while the Ecuador contribution deals with small and medium-sized nuclear power plants

  19. The U.S.-Russian joint studies on using power reactors to disposition surplus weapons plutonium as spent fuel

    International Nuclear Information System (INIS)

    Chebeskov, A.; Kalashnikov, A.; Pavlovichev, A.

    1997-09-01

    In 1996, the US and the Russian Federation completed an initial joint study of the candidate options for the disposition of surplus weapons plutonium in both countries. The options included long term storage, immobilization of the plutonium in glass or ceramic for geologic disposal, and the conversion of weapons plutonium to spent fuel in power reactors. For the latter option, the US is only considering the use of existing light water reactors (LWRs) with no new reactor construction for plutonium disposition, or the use of Canadian deuterium uranium (CANDU) heavy water reactors. While Russia advocates building new reactors, the cost is high, and the continuing joint study of the Russian options is considering only the use of existing VVER-1000 LWRs in Russia and possibly Ukraine, the existing BN-60O fast neutron reactor at the Beloyarsk Nuclear Power Plant in Russia, or the use of the Canadian CANDU reactors. Six of the seven existing VVER-1000 reactors in Russia and the eleven VVER-1000 reactors in Ukraine are all of recent vintage and can be converted to use partial MOX cores. These existing VVER-1000 reactors are capable of converting almost 300 kg of surplus weapons plutonium to spent fuel each year with minimum nuclear power plant modifications. Higher core loads may be achievable in future years

  20. The relationship between natural uranium and advanced fuel cycles in CANDU reactors

    International Nuclear Information System (INIS)

    Lane, A.D.; McDonnell, F.N.; Griffiths, J.

    1988-11-01

    CANDU is the most uranium-economic type of thermal power reactor, and is the only type used in Canada. CANDU reactors consume approximately 15% of Canadian uranium production and support a fuel service industry valued at ∼$250 M/a. In addition to their once-through, natural-uranium fuel cycle, CANDU reactors are capable of operating with slightly-enriched uranium (SEU), uranium-plutonium and thorium cycles, more efficiently than other reactors. Only SEU is economically attractive in Canada now, but the other cycles are of interest to countries without indigenous fuel resources. A program is underway to establish the fuel technologies necessary for the use of SEU and the other fuel cycles in CANDU reactors. 22 refs

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

    Science.gov (United States)

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

    2015-12-01

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

  2. A review of the UKAEA interest in heavy water reactors

    International Nuclear Information System (INIS)

    Symes, R.J.

    1983-01-01

    The chapter commences with a brief account of the history of heavy water production and then begins the story of the British use of this moderator in power reactors. This is equated with the introduction and development of the tube reactor as a distinct and important form of reactor construction in contrast with the perhaps better known vessel design that has tended to dominate reactor engineering to date. The account thus includes a succession of reactor designs including the gas and steam cooled heavy water systems in addition to the steam-generating heavy water reactor. The SGHWR was demonstrated by the construction of a substantial prototype, which continues in operation as a flexible and reliable electricity-generating plant. It was also, for a time, identified as the system to be used for Britain's third reactor programme. Today the successful Canadian CANDU power reactors represent the only penetration of heavy water reactor technology into large scale electricity generation. The range of research and experimental reactors using heavy water in their cores is reviewed. (author)

  3. 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)

  4. Tritium technology. A Canadian overview

    Energy Technology Data Exchange (ETDEWEB)

    Hemmings, R.L. [Canatom NPM (Canada)

    2002-10-01

    An overview of the various tritium research and operational activities in Canada is presented. These activities encompass tritium processing and recovery, tritium interactions with materials, and tritium health and safety. Many of these on-going activities form a sound basis for the tritium use and handling aspects of the ITER project. Tritium management within the CANDU heavy water reactor, associated detritiation facilities, research and development facilities, and commercial industry and improving the understanding of tritium behaviour in humans and the environment remain the focus of a long-standing Canadian interest in tritium. While there have been changes in the application of this knowledge and experience over time, the operating experience and the supporting research and development continue to provide for improved plant and facility operations, an improved understanding of tritium safety issues, and improved products and tools that facilitate tritium management. (author)

  5. Tritium technology. A Canadian overview

    International Nuclear Information System (INIS)

    Hemmings, R.L.

    2002-01-01

    An overview of the various tritium research and operational activities in Canada is presented. These activities encompass tritium processing and recovery, tritium interactions with materials, and tritium health and safety. Many of these on-going activities form a sound basis for the tritium use and handling aspects of the ITER project. Tritium management within the CANDU heavy water reactor, associated detritiation facilities, research and development facilities, and commercial industry and improving the understanding of tritium behaviour in humans and the environment remain the focus of a long-standing Canadian interest in tritium. While there have been changes in the application of this knowledge and experience over time, the operating experience and the supporting research and development continue to provide for improved plant and facility operations, an improved understanding of tritium safety issues, and improved products and tools that facilitate tritium management. (author)

  6. 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

  7. Economics and utilization of thorium in nuclear reactors. Technical annexes 1 and 2

    International Nuclear Information System (INIS)

    1978-05-01

    An assessment of the impact of utilizing the 233 U/thorium fuel cycle in the U.S. nuclear economy is strongly dependent upon several decisions involving nuclear energy policy. These decisions include: (1) to recycle or not recycle fissile material; (2) if fissile material is recycled, to recycle plutonium, 233 U, or both; and (3) to deploy or not to deploy advanced reactor designs such as Fast Breeder Reactors (FBR's), High Temperature Gas Reactors (HTGR's), and Canadian Deuterium Uranium Reactors (CANDU's). This report examines the role of thorium in the context of the above policy decisions while focusing special attention on economics and resource utilization

  8. Luncheon address: Development of the CANDU reactor

    International Nuclear Information System (INIS)

    Bain, A.S.

    1997-01-01

    The paper is a highlight of the some of the achievements in the development of the CANDU Reactor, taken from the book C anada Enters the Nuclear Age . The CANDU reactor is one of Canada's greatest scientific/engineering achievements, that started in the 1940's and bore fruit with the reactors of the 60's, 70's, and 80's. The Government decided in the 1950's to proceed with a demonstration nuclear power reactor (NPD), AECL invited 7 Canadian corporations to bid on a contract to design and construct the NPD plant. General Electric was selected. A utility was also essential for participation and Ontario Hydro was chosen. In May 1957 it was concluded that the minimum commercial size would be about 200MWe and it should use horizontal pressure tubes to contain the fuel and pressurized heavy water coolant. The book also talks of standard out-reactor components such as pumps, valves, steam generators and piping. A major in-reactor component of interest was the fuel, fuel channels and pressure tubes. A very high level of cooperation was required for the success of the CANDU program

  9. Thermal hydraulic simulation of the CANDU nuclear reactor

    Energy Technology Data Exchange (ETDEWEB)

    Carvalho, Athos M.S.S. de; Ramos, Mario C.; Costa, Antonella L.; Fernandes, Gustavo H.N., E-mail: athos1495@yahoo.com.br [Universidade Federal de Minas Gerais (UFMG), Belo Horizonte, MG (Brazil). Departamento de Engenharia Nuclear; Instituto Nacional de Ciência e Tecnologia de Reatores Nucleares Inovadores (INCT/CNPq), Rio de janeiro, RJ (Brazil)

    2017-07-01

    The CANDU (Canada Deuterium Uranium) is a Canadian-designed power reactor of PHWR type (Pressurized Heavy Water Reactor) that uses heavy water (deuterium oxide) for moderator and coolant, and natural uranium for fuel. There are about 47 reactors of this type in operation around the world generating more than 23 GWe, highlighting the importance of this kind of device. In this way, the main purpose of this study is to develop a thermal hydraulic model for a CANDU reactor to aggregate knowledge in this line of research. In this way, a core modeling was performed using RELAP5-3D code. Results were compared with reference data to verify the model behavior in steady state operation. Thermal hydraulic parameters as temperature, pressure and mass flow rate were verified and the results are in good agreement with reference data, as it is being presented in this work. (author)

  10. 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

  11. 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)

  12. CANDU reactors, their regulation in Canada, and the identification of relevant NRC safety issues

    International Nuclear Information System (INIS)

    Charak, I.; Kier, P.H.

    1995-04-01

    Atomic Energy of Canada, Limited (AECL) and its subsidiary in the US, are considering submitting the CANDU 3 design for standard design certification under 10 CFR Part 52. CANDU reactors are pressurized heavy water power reactors. They have some substantially different safety responses and safety systems than the LWRs that the commercial power reactor licensing regulations of the US Nuclear Regulatory Commission (NRC) have been developed to deal with. In this report, the authors discuss the basic design characteristics of CANDU reactors, specifically of the CANDU 3 where possible, and some safety-related consequences of these characteristics. The authors also discuss the Canadian regulatory provisions, and the CANDU safety systems that have evolved to satisfy the Canadian regulatory requirements as of December 1992. Finally, the authors identify NRC regulations, mainly in 10 CFR Parts 50 and 100, with issues for CANDU 3 reactor designs. In all, eleven such regulatory issues are identified. They are: (1) the ATWS rule (section 50.62); (2) station blackout (section 50.63); (3) conformance with Standard Review Plan (SRP); (4) appropriateness of the source term (section 50.34(f) and section 100.11); (5) applicability of reactor coolant pressure boundary (RCPB) requirements (section 50.55a, etc); (6) ECCS acceptance criteria (section 50.46)(b); (7) combustible gas control (section 50.44, etc); (8) power coefficient of reactivity (GDC 11); (9) seismic design (Part 100); (10) environmental impacts of the fuel cycle (section 51.51); and (11) (standards section 50.55a)

  13. MINIMARS tandem mirror reactor study

    International Nuclear Information System (INIS)

    Perkins, L.J.; Logan, B.G.; Doggett, J.N.

    1986-01-01

    During 1985-1986, Lawrence Livermore National Lab., in partnership with the Fusion Engineering Design Center of Oak Ridge National Lab., the Univ. of Wisconsin, TRW, Grumman Aerospace Corporation, General Dynamics/Convair, Argonne National Lab., and the Canadian Fusion Fuels Technology Project, has conducted the conceptual design of MINIMARS, a small commercial tandem mirror reactor with novel octopole end plugs. With a net electric output of 600 MW(e), MINIMARS is expressly designed for short (∼4- to 5-yr) construction time, factory-built modules, and a passively safe blanket and thermal cycle. In this way, we intend to achieve a small reactor based on the tandem mirror principle that will minimize utility financial risk, thereby providing an attractive alternative to the more conventional large fusion plant designs encountered to date

  14. To question of NPP power reactor choice for Kazakhstan

    International Nuclear Information System (INIS)

    Batyrbekov, G.A.; Makhanov, Y.M.; Reznikova, R.A.; Sidorenco, A.V.

    2004-01-01

    Full text: The requirements to NPP power reactors that will be under construction in Kazakhstan are proved and given in the report. A comparative analysis of the most advanced projects of power reactors with light and heavy water under pressure of large, medium and low power is carried out. Different reactors have been considered as follows: 1. Reactors with high-power (700 MW(el) and up) such as EPR, French - German reactor; CANDU-9, Canadian heavy-water reactor; System 80+, developed by ABB Combustion Engineering company, USA; KNGR, Korean reactor of the next generation; APWR, Japanese advanced reactor; WWER-1000 (V-392) - development of Atomenergoproect /Gydropress, Russian Federation; EP 1000, European passive reactor. 2. Reactors with medium power (300 MW (el) - 700 MW (el): AP-600, passive PWR of the Westinghouse company; CANDU-6, Canadian heavy-water reactor; AC-600, Chinese passive PWR; WWER-640, Russian passive reactor; MS-600 Japanese reactor of Mitsubishi Company; KSNP-600, South Korean reactor. 3. Reactors with low power (a few MW(el)- 300 MW(el)): IRIS, reactor of IV generation, developed by the International Corporation of 13 organizations from 7 countries, SMART, South Korean integrated reactor; CAREM, Argentina integrated reactor; MRX, Japanese integrated reactor; 'UNITERM', Russian NPP with integrated reactor, development of NIKIET; AHEC-80, Russian NPP, developed by OKBM. A comparison of the projects of the above-mentioned power reactors was carried out with respect to 15 criteria of nuclear, radiating, ecological safety and economic competitiveness, developed especially for this case. Data on a condition and prospects of power production and power consumption, stations and networks in Kazakhstan necessary for the choice of projects of NPP reactors for Kazakhstan are given. According to the data a balance of power production and power consumption as a whole in the country was received at the level of 59 milliard kw/h. However, strong dis balance

  15. To question of NPP power reactor choice for Kazakhstan

    International Nuclear Information System (INIS)

    Batyrbekov, G.A.; Makhanov, Y.M.; Reznikova, R.A.; Sidorenco, A.V.

    2004-01-01

    The requirements to NPP power reactors that will be under construction in Kazakhstan are proved and given in the report. A comparative analysis of the most advanced projects of power reactors with light and heavy water under pressure of large, medium and low power is carried out. Different reactors have been considered as follows: 1. Reactors with high-power (700 MW(el) and up) such as EPR, French - German reactor; CANDU-9, Canadian heavy-water reactor; System 80+, developed by ABB Combustion Engineering company, USA; KNGR, Korean reactor of the next generation; APWR, Japanese advanced reactor; WWER-1000 (V-392) - development of Atomenergoproect /Gydropress, Russian Federation; EP 1000, European passive reactor. 2. Reactors with medium power (300 MW (el) - 700 MW (el): AP-600, passive PWR of the Westinghouse company; CANDU-6, Canadian heavy-water reactor; AC-600, Chinese passive PWR; WWER-640, Russian passive reactor; MS-600 Japanese reactor of Mitsubishi Company; KSNP-600, South Korean reactor. 3. Reactors with low power (a few MW(el)- 300 MW(el)): IRIS, reactor of IV generation, developed by the International Corporation of 13 organizations from 7 countries, SMART, South Korean integrated reactor; CAREM, Argentina integrated reactor; MRX, Japanese integrated reactor; 'UNITERM', Russian NPP with integrated reactor, development of NIKIET; AHEC-80, Russian NPP, developed by OKBM. A comparison of the projects of the above-mentioned power reactors was carried out with respect to 15 criteria of nuclear, radiating, ecological safety and economic competitiveness, developed especially for this case. Data on a condition and prospects of power production and power consumption, stations and networks in Kazakhstan necessary for the choice of projects of NPP reactors for Kazakhstan are given. According to the data a balance of power production and power consumption as a whole in the country was received at the level of 59 milliard kw/h. However, strong dis balance in the

  16. Aspects of the physics and chemistry of water radiolysis by fast neutrons and fast electrons in nuclear reactors

    Energy Technology Data Exchange (ETDEWEB)

    McCracken, D.R. [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada); Tsang, K.T. [Atomic Energy of Canada Limited, Mississauga, Ontario (Canada); Laughton, P.J

    1998-09-01

    Detailed radiation physics calculations of energy deposition have been done for the coolant of CANDU reactors and Pressurized Water Reactors (PWRs). The geometry of the CANDU fuel channel was modelled in detail. Fluxes and energy-deposition rates for neutrons, recoil ions, photons, and fast electrons have been calculated using MCNP4B, WIMS-AECL, and specifically derived energy-transfer factors. These factors generate the energy/flux spectra of recoil ions from fast-neutron energy/flux spectra. The energy spectrum was divided into 89 discrete ranges (energy bins).The production of oxidizing species and net coolant radiolysis can be suppressed by the addition of hydrogen to the coolant of nuclear reactors. It is argued that the net dissociation of coolant by gamma rays is suppressed by lower levels of excess hydrogen than when dissociation is by ion recoils. This has consequences for the modelling of coolant radiolysis by homogeneous kinetics. More added hydrogen is required to stop water radiolysis by recoil ions acting alone than if recoil ions and gamma rays acted concurrently in space and time. Homogeneous kinetic models and experimental data suggest that track overlap is very inefficient in providing radicals from gamma-ray tracks to recombine molecular products in ion-recoil tracks. An inhomogeneous chemical model is needed that incorporates ionizing-particle track structure and track overlap. Such a model does not yet exist, but a number of limiting cases using homogeneous kinetics are discussed. There are sufficient uncertainties and contradictions in the data relevant to the radiolysis of reactor coolant that the relatively high CHC's (critical hydrogen concentration) observed in NRU reactor experiments (compared to model predictions) may be explainable by errors in fundamental data and understanding of water radiolysis under reactor conditions. The radiation chemistry program at CRL has been focused to generate quantitative water-radiolysis data in a

  17. Protest: The Canadian pulse

    International Nuclear Information System (INIS)

    Lott, J.E.

    1979-01-01

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

  18. 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.)

  19. Canadian development program for off-gas management in nuclear facilities

    International Nuclear Information System (INIS)

    Sridhar, T.S.

    1983-01-01

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

  20. Licensing assessment of the Candu Pressurized Heavy Water Reactor. Preliminary safety information document. Volume II

    International Nuclear Information System (INIS)

    1977-06-01

    ERDA has requested United Engineers and Constructors (UE and C) to evaluate the design of the Canadian natural uranium fueled, heavy water moderated (CANDU) nuclear reactor power plant to assess its conformance with the licensing criteria and guidelines of the U.S. Nuclear Regulatory Commission (USNRC) for light water reactors. This assessment was used to identify cost significant items of nonconformance and to provide a basis for developing a detailed cost estimate for a 1140 MWe, 3-loop Pressurized Heavy Water Reactor (PHWR) located at the Middletown, USA Site

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

    Science.gov (United States)

    Morton, Heather; Gorzalka, Boris B

    2013-11-01

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

  2. Dictionaries of Canadian English | Considine | Lexikos

    African Journals Online (AJOL)

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

  3. CANDU nuclear reactor technology

    International Nuclear Information System (INIS)

    Kakaria, B. K.

    1994-01-01

    AECL has over 40 years of experience in the nuclear field. Over the past 20 years, this unique Canadian nuclear technology has made a worldwide presence, In addition to 22 CANDU reactors in Canada, there are also two in India, one in Pakistan, one in Argentina, four in Korea and five in Romania. CANDU advancements are based on evolutionary plant improvements. They consist of system performance improvements, design technology improvements and research and development in support of advanced nuclear power. Given the good performance of CANOU plants, it is important that this CANDU operating experience be incorporated into new and repeat designs

  4. Canadian attitudes to nuclear power

    International Nuclear Information System (INIS)

    Davies, J.E.O.

    1977-01-01

    In the past ten years, public interest in nuclear power and its relationship to the environment has grown. Although most Canadians have accepted nuclear power as a means of generating electricity, there is significant opposition to its use. This opposition has effectively forced the Canadian nuclear industry to modify its behaviour to the public in the face of growing concern over the safety of nuclear power and related matters. The paper reviews Canadian experience concerning public acceptance of nuclear power, with special reference to the public information activities of the Canadian nuclear industry. Experience has shown the need for scientific social data that will permit the nuclear industry to involve the public in a rational examination of its concern about nuclear power. The Canadian Nuclear Association sponsored such studies in 1976 and the findings are discussed. They consisted of a national assessment of public attitudes, two regional studies and a study of Canadian policy-makers' views on nuclear energy. The social data obtained were of a base-line nature describing Canadian perceptions of and attitudes to nuclear power at that time. This research established that Canadian levels of knowledge about nuclear power are very low and that there are marked regional differences. Only 56% of the population have the minimum knowledge required to indicate that they know that nuclear power can be used to generate electricity. Nevertheless, 21% of informed Canadians oppose nuclear power primarily on the grounds that it is not safe. Radiation and waste management are seen to be major disadvantages. In perspective, Canadians are more concerned with inflation than with the energy supply. About half of all Canadians see the question of energy supplies as a future problem (within five years), not a present one. A more important aspect of energy is seen by the majority of Canadians to be some form of energy independence. The use of data from these studies is no easy

  5. Cross-situational consistency of trait expressions and injunctive norms among Asian Canadian and European Canadian undergraduates.

    Science.gov (United States)

    Locke, Kenneth D; Sadler, Pamela; McDonald, Kelly

    2018-06-14

    In the current paper, we sought to clarify when and why Asian Americans/Canadians and European Americans/Canadians differ in self-consistency (the consistency of personality traits across situations). European Canadian (n = 220) and second-generation Asian Canadian (n = 166) undergraduates (Mage = 19 years) described the traits they expressed and the traits others wanted them to express (i.e., injunctive norms, or injunctions) in four different social situations (i.e., with parents, with friends, with siblings, and with professors). Self-consistency was greater among European Canadians than Asian Canadians, but only when comparing behavior with parents versus with peers (i.e., friends and siblings). The same pattern was found for injunctive consistency (cross-situational consistency of trait injunctions). Injunctions strongly predicted the behavior of both Asian and European Canadians, but because the injunctions from parents versus peers diverged more for Asian Canadians, so did their behaviors. Controlling for the effect of inconsistent injunctions across situations eliminated the ethnic difference in self-consistency. Finally, Asian Canadians who perceived their immigrant parents as embracing a Canadian identity were as cross-situationally consistent as European Canadians because they tended to behave-and believe their parents approved of their behaving-with parents similarly to how they behaved with peers (e.g., more carefree and outspoken). Contrary to previous theorizing, cultural influences on broad cognitive or motivational dispositions (e.g., dialecticism, collectivism) alone cannot explain the observed pattern of ethnic differences in consistency. To understand when bicultural individuals are less consistent across situations also requires an understanding of the specific situations across which they tend to encounter divergent social norms. (PsycINFO Database Record (c) 2018 APA, all rights reserved).

  6. Practical test set-up and method for determining the response characteristics of a log rate channel over 6 decades

    International Nuclear Information System (INIS)

    Kemp, J.

    1996-01-01

    A test method was developed using modern, readily available instrumentation to produce an exponentially rising signal over 6 1/2 decades. The method includes validation and calibration tests. It was used to simulate the current signal that would be produced from an ion chamber during a hypothetical loss of Regulation event for a reactor from a shutdown state. This simulation scenario was then used to test the log rate channel of the new ion chamber amplifiers for the NRU research reactor second trip system upgrade. (author)

  7. Framing Canadian federalism

    National Research Council Canada - National Science Library

    Saywell, John; Anastakis, Dimitry; Bryden, Penny E

    2009-01-01

    ... the pervasive effects that federalism has on Canadian politics, economics, culture, and history, and provide a detailed framework in which to understand contemporary federalism. Written in honour of John T. Saywell's half-century of accomplished and influential scholarly work and teaching, Framing Canadian Federalism is a timely and fitting t...

  8. Analysis of log rate noise in Ontario's CANDU reactors

    Energy Technology Data Exchange (ETDEWEB)

    Hinds, H.W. [Dynamic Simulation and Analysis Corp., Deep River, Ontario (Canada); Banica, C.; Arguner, D. [Ontario Power Generation, Ajax, Ontario (Canada); Scharfenberg, R. [Bruce Power, Tiverton, Ontario (Canada)

    2007-07-01

    In the fall of 2003, the operators noticed that in the recently-refurbished Bruce A Shutdown System no. 1 (SDS1) the noise level in Log Rate signals were much larger than before. At the request of the Canadian Nuclear Safety Commission (CNSC), all Canadian CANDU reactors took action to characterize their Log Rate noise. Staff of the Inspection and Maintenance Services division of Ontario Power Generation (OPG) has collected high-speed high-accuracy noise data from nearly all 16 Ontario reactors, either as part of routine measurements before planned outages or as a dedicated noise recording. This paper gives the results of examining a suitable subset of this data, with respect to the characteristics and possible causes of Log Rate noise. The reactor and instrumentation design is different at each station: the locations of the moderator injection nozzles, the location of the ion chambers for each system, and the design of the Log Rate amplifiers. It was found that the Log noise (source of Log Rate noise) was much larger for those ion chambers in the path of the moderator injection nozzles, compared to those which were not in the path. This 'extra' Log noise would then be either attenuated or amplified depending on the transfer function (time constants) of the Log Rate amplifier. It was also observed that most of the Log and Log Rate noise is independent of any other signal measured. Although all CANDU reactors in Ontario have Log and Log Rate noise, the Bruce A SDS1 system has the largest amount of Log Rate noise, because (a) its SDS1 (and RRS) ion chambers are at the top of the reactor in the path of the moderator injection nozzles, and (b) its SDS1 Log Rate amplifiers have the smallest time constants. (author)

  9. Conditioning and handling of tritiated wastes at Canadian nuclear power facilities

    International Nuclear Information System (INIS)

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

    1987-04-01

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

  10. Ethno-linguistic peculiarities of French Canadian and English ...

    African Journals Online (AJOL)

    When English Canadian and French Canadian phraseology is compared, the greater role of religion in the French Canadian community is evident, rather than in English Canadian; the influence of the Canadian variant of the English language on the Canadian variant of French is clearly expressed. With all the differences, ...

  11. The development and testing of reduced enrichment fuels for Canadian research reactors

    International Nuclear Information System (INIS)

    Wood, J.C.; Foo, M.T.; Berthiaume, L.C.

    1983-01-01

    Fuel rods of uranium silicide dispersed in aluminum and clad in aluminum have been developed and tested in the laboratory and in-reactor. The properties of the dispersion fuel materials proved satisfactory with regard to thermal conductivity, aqueous corrosion resistance, strength and ductility, and thermal stability below 473 K. A vacancy condensation model is proposed to account for the thermally-induced swelling that occurs above 473 K by virtue of the chemical reactions that occur between the dispersed silicide fuel particles and the aluminum matrix. The in-reactor fuel core swelling was less than % after irradiation at high powers 76-131 kW/m) to a high terminal burnup (79.2 at% of U-235 atoms). (author)

  12. 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)

  13. Thermal aspects of mixed oxide fuel in application to supercritical water-cooled nuclear reactors

    Energy Technology Data Exchange (ETDEWEB)

    Grande, L.; Peiman, W.; Rodriguez-Prado, A.; Villamere, B.; Mikhael, S.; Allison, L.; Pioro, I., E-mail: lisa.grande@mycampus.uoit.ca, E-mail: igor.pioro@uoit.ca [Univ. of Ontario Inst. of Tech., Faculty of Energy Systems and Nuclear Science, Oshawa, Ontario (Canada)

    2010-07-01

    SuperCritical Water-cooled nuclear Reactors (SCWRs) are a renewed technology being developed as one of the Generation IV reactor concepts. This reactor type uses a light water coolant at temperatures and pressures above its critical point. These elevated operating conditions will improve Nuclear Power Plant (NPP) thermal efficiencies by 10 - 15% compared to those of current NPPs. Also, SCWRs will have the ability to utilize a direct cycle, thus decreasing NPP capital and operational costs. The SCWR core has 2 configurations: 1) Pressure Vessel (PV) -type enclosing a fuel assembly and 2) Pressure Tube (PT) -type consisting of individual pressurized channels containing fuel bundles. Canada and Russia are developing PT-type SCWRs. In particular, the Canadian SCWR reactor has an output of 1200 MW{sub el} and will operate at a pressure of 25 MPa with inlet and outlet fuel-channel temperatures of 350 and 625°C, respectively. These extreme operating conditions require alternative fuels and materials to be investigated. Current CANadian Deuterium Uranium (CANDU) nuclear reactor fuel-channel design is based on the use of uranium dioxide (UO{sub 2}) fuel; zirconium alloy sheath (clad) bundle, pressure and calandria tubes. Alternative fuels should be considered to supplement depleting world uranium reserves. This paper studies general thermal aspects of using Mixed OXide (MOX) fuel in an Inconel-600 sheath in a generic PT-type SCWR. The bulk fluid, sheath and fuel centerline temperatures along with the Heat Transfer Coefficient (HTC) profiles were calculated at uniform and non-uniform Axial Heat Flux Profiles (AHFPs). (author)

  14. Full-length fuel rod behavior under severe accident conditions

    International Nuclear Information System (INIS)

    Lombardo, N.J.; Lanning, D.D.; Panisko, F.E.

    1992-12-01

    This document presents an assessment of the severe accident phenomena observed from four Full-Length High-Temperature (FLHT) tests that were performed by the Pacific Northwest Laboratory (PNL) in the National Research Universal (NRU) reactor at Chalk River, Ontario, Canada. These tests were conducted for the US Nuclear Regulatory Commission (NRC) as part of the Severe Accident Research Program. The objectives of the test were to simulate conditions and provide information on the behavior of full-length fuel rods during hypothetical, small-break, loss-of-coolant severe accidents, in commercial light water reactors

  15. Performance of small reactors at universities for teaching, research, training and service (TRTS): thirty five years' experience with the Dalhousie University SLOWPOKE-2 reactor

    Energy Technology Data Exchange (ETDEWEB)

    Chatt, A., E-mail: a.chatt@dal.ca [Dalhousie Univ., Trace Analysis Research Centre, Dept. of Chemistry, Halifax, Nova Scotia (Canada)

    2013-07-01

    The Dalhousie University SLOWPOKE-2 Reactor (DUSR) facility, operated during 1976-2011, was the only research reactor in Atlantic Canada as well as the only one associated with a chemistry department in a Canadian university. The most outstanding features of the facility included: a rapid (100 ms) cyclic pneumatic sample transfer system, a permanently installed Cd-site, and a Compton-suppression gamma-ray spectrometer. The usage encompassed fundamental as well as applied studies in various fields using neutron activation analysis (NAA). The facility was used for training undergraduate/graduate students, postdoctoral fellows, technicians, and visiting scientists, and for cooperative projects with other universities, research organizations and industries. (author)

  16. Technical specification: Mixed-oxide pellets for the light-water reactor irradiation demonstration test

    International Nuclear Information System (INIS)

    Cowell, B.S.

    1997-06-01

    This technical specification is a Level 2 Document as defined in the Fissile Materials Disposition Program Light-Water Reactor Mixed-oxide Fuel Irradiation Test Project Plan. It is patterned after the pellet specification that was prepared by Atomic Energy of Canada, Limited, for use by Los Alamos National Laboratory in fabrication of the test fuel for the Parallex Project, adjusted as necessary to reflect the differences between the Canadian uranium-deuterium reactor and light-water reactor fuels. This specification and the associated engineering drawing are to be utilized only for preparation of test fuel as outlined in the accompanying Request for Quotation and for additional testing as directed by Oak Ridge National Laboratory or the Department of Energy

  17. Canadian petroleum industry

    Energy Technology Data Exchange (ETDEWEB)

    Dagher, J.H.

    1969-12-01

    This study covers the following Canadian petroleum industry categories: (1) a brief history; (2) the demand for Alberta crude; (3) U.S. oil policies; (4) overseas exploration; (5) the national oil policy; (6) the Montreal pipeline and its targets; (7) a continental oil policy; and (8) the impact of Arctic reserves. It is noted that large potential benefits will improve from the Manhattan navigating the Northwest Passage. Without prejudging the analysis now applied to the information gathered on this voyage, the Manhattan has greatly contributed to the solution of the problem of access to the Arctic islands. The picture for natural gas is less fraught with uncertainties. Unlike oil, where domestic and international considerations may weigh in U.S. policy decision, Canadian natural gas is likely to be allowed to enjoy its full economic potential in bridging the foreseeable U.S. supply gap and, inasmuch as this potential is ultimately tied with that for crude oil markets, the anticipated U.S. needs for Canadian natural gas may be expected to enhance U.S. interest in the overall well-being of the Canadian petroleum industry.

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

    International Nuclear Information System (INIS)

    1981-01-01

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

  19. Evaluation of hydride blisters in zirconium pressure tube in CANDU reactor

    International Nuclear Information System (INIS)

    Cheong, Y. M.; Kim, Y. S.; Gong, U. S.; Kwon, S. C.; Kim, S. S.; Choo, K.N.

    2000-09-01

    When the garter springs for maintaining the gap between the pressure tube and the calandria tube are displaced in the CANDU reactor, the sagging of pressure tube results in a contact to the calandria tube. This causes a temperature difference between the inner and outer surface of the pressure tube. The hydride can be formed at the cold spot of outer surface and the volume expansion by hydride dormation causes the blistering in the zirconium alloys. An incident of pressure tube rupture due to the hydride blisters had happened in the Canadian CANDU reactor. This report describes the theoretical development and models on the formation and growth of hydride blister and some experimental results. The evaluation methodology and non-destructive testing for hydride blister in operating reactors are also described

  20. Evaluation of hydride blisters in zirconium pressure tube in CANDU reactor

    Energy Technology Data Exchange (ETDEWEB)

    Cheong, Y M; Kim, Y S; Gong, U S; Kwon, S C; Kim, S S; Choo, K N

    2000-09-01

    When the garter springs for maintaining the gap between the pressure tube and the calandria tube are displaced in the CANDU reactor, the sagging of pressure tube results in a contact to the calandria tube. This causes a temperature difference between the inner and outer surface of the pressure tube. The hydride can be formed at the cold spot of outer surface and the volume expansion by hydride dormation causes the blistering in the zirconium alloys. An incident of pressure tube rupture due to the hydride blisters had happened in the Canadian CANDU reactor. This report describes the theoretical development and models on the formation and growth of hydride blister and some experimental results. The evaluation methodology and non-destructive testing for hydride blister in operating reactors are also described.

  1. Canadian competitive advantage

    International Nuclear Information System (INIS)

    Wills, J.

    1997-01-01

    The evolution of the Canadian petrochemical industry was outlined, emphasizing the proximity to feedstocks as the principal advantage enjoyed by the industry over its international competitors. Annual sales statistics for 1995 were provided. Key players in the Canadian petrochemical industry (Nova, Dow, DuPont, Methanex, Esso, Union Carbide, Shell and Celanese), their share of the market and key products were noted. Manufacturing facilities are located primarily in Alberta, southern Ontario and Quebec. The feedstock supply infrastructure, historical and alternative ethane pricing in Canada and the US, the North American market for petrochemicals, the competitiveness of the industry, tax competitiveness among Canadian provinces and the US, the Canada - US unit labour cost ratio, ethylene facility construction costs in Canada relative to the US Gulf Coast, and projected 1997 financial requirements were reviewed. 19 figs

  2. Power auxiliaries and research reactors. Section 3 of Symposium on the peaceful uses of atomic energy in Australia, 1958, held in Sydney, in June 1958

    Energy Technology Data Exchange (ETDEWEB)

    None

    1958-10-15

    The problems of disposing of the large amounts of highly-radioactive waste resulting from a large-scale nuclear power program are reviewed. The Canadian research reactor NRX is discussed. The DIDO reactor is briefly described and operating experience for the first year at high flux is summarized. The core of the High Flux Australian Research Reactor (HIFAR) is described, and some reactivity balance data are given (T.R.H.)

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

    International Nuclear Information System (INIS)

    2006-01-01

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

  4. Inspection methods for physical protection Task III review of other agencies' physical security activities for research reactors

    International Nuclear Information System (INIS)

    In Task I of this project, the current Nuclear Regulatory Commission (NRC) position-on physical security practices and procedures at research reactors were reviewed. In the second task, a sampling of the physical security plans was presented and the three actual reactor sites described in the security plans were visited. The purpose of Task III is to review other agencies' physical security activities for research reactors. During this phase, the actions, procedures and policies of two domestic and two foreign agencies other than the NRC that relate to the research reactor community were examined. The agencies examined were: International Atomic Energy Agency; Canadian Atomic Energy Control Board; Department of Energy; and American Nuclear Insurers

  5. Fuel cycle options for light water reactors and heavy water reactors. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    1999-11-01

    In the second half of the 20th century nuclear power has evolved from the research and development environment to an industry that supplies 16% of the world's electricity. By the end of 1997, over 8500 reactor-years of operating experience had been accumulated. Global environmental change, and the continuing increase in global energy supply required to provide increasing populations with an improving standard of living, make the contribution from nuclear energy even more important for the next century. For nuclear power to achieve its full potential and make its needed contribution, it must be safe, economical, reliable and sustainable. All of these factors can be enhanced by judicious choice and development of advanced fuel cycle options. The Technical Committee Meeting (TCM) on Fuel Cycle Options for Light Water Reactors and Heavy Water Reactors was hosted by Atomic Energy of Canada Limited (AECL) on behalf of the Canadian Government and was jointly conducted within the frame of activities of the IAEA International Working Group on Advanced Technologies for Light Water Reactors (IWG-LWR) and the IAEA International Working Group on Advanced Technologies for Heavy Water Reactors (IWG-HWR). The TCM provided the opportunity to have in-depth discussions on important technical topics which were highlighted in the International Symposium on Nuclear Fuel Cycle and Reactor Strategies: Adjusting to New Realities, held in Vienna, 3-6 June 1997. The main results and conclusions of the TCM were presented as input for discussion at the first meeting of the IAEA newly formed International Working Group on Fuel Cycle Options

  6. Conference summaries. Canadian Nuclear Association 29. annual conference; Canadian Nuclear Society 10. annual conference

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1990-12-31

    Separate abstracts were prepared for 15 papers from the twenty-ninth Annual Conference of the Canadian Nuclear Association. Abstracts were also prepared for the 102 papers from the tenth Annual Conference of the Canadian Nuclear Society.

  7. Conference summaries. Canadian Nuclear Association 29. annual conference; Canadian Nuclear Society 10. annual conference

    International Nuclear Information System (INIS)

    1989-01-01

    Separate abstracts were prepared for 15 papers from the twenty-ninth Annual Conference of the Canadian Nuclear Association. Abstracts were also prepared for the 102 papers from the tenth Annual Conference of the Canadian Nuclear Society

  8. Recommended safety objectives, principles and requirements for mini-reactors

    International Nuclear Information System (INIS)

    1991-05-01

    Canadian and international publications containing objectives, principles and requirements for the safety of nuclear facilities in general and nuclear power plants in particular have been reviewed for their relevance to mini-reactors. Most of the individual recommendations, sometimes with minor wording changes, are applicable to mini-reactors. However, some prescriptive requirements for the shutdown, emergency core cooling and containment systems of power reactors are considered inappropriate for mini-reactors. The Advisory Committee on Nuclear Safety favours a generally non-prescriptive approach whereby the applicant for a mini-reactor license is free to propose any means of satisfying the fundamental objectives, but must convince the regulatory agency to that effect. To do so, a probabilistic safety assessment (PSA) would be the favoured procedure. A generic PSA for all mini-reactors of the same design would be acceptable. Notwithstanding this non-prescriptive approach, the ACNS considers that it would be prudent to require the existence of at least one independent shutdown system and two physically independent locations from which the reactor can be shut down and the shutdown condition monitored, and to require provision for an assumed loss of integrity of the primary cooling system's boundary unless convincing arguments to the contrary are presented. The ACNS endorses in general the objectives and fundamental principles proposed by the interorganizational Small Reactor Criteria working group, and intends to review and comment on the documents on specific applications to be issued by that working group

  9. Financial outlook for the Canadian gas industry

    International Nuclear Information System (INIS)

    Friedenberg, B.

    1995-01-01

    The financial outlook for the Canadian gas industry depends on the outlook for gas prices at Canadian producing basins, the cost of producing in Canada and the volume of production of Canadian natural gas. Price, cost and volume determine the health of the Canadian industry. Industry's costs are the basis of the supply (volume) offered on the market and price is determined by the interaction of supply and demand. (author)

  10. The Canadian National Retirement Risk Index: employing statistics Canada's LifePaths to measure the financial security of future Canadian seniors.

    Science.gov (United States)

    MacDonald, Bonnie-Jeanne; Moore, Kevin D; Chen, He; Brown, Robert L

    2011-01-01

    This article measures a Canadian National Retirement Risk Index (NRRI). Originally developed by the Center for Retirement Research at Boston College, the NRRI is a forward-looking measure that evaluates the proportion of working-aged individuals who are at risk of not maintaining their standard of living in retirement. The Canadian retirement income system has been very effective in reducing elderly poverty, but our results suggest that it has been much less successful in maintaining the living standards of Canadians after retirement. Since the earlier years of the new millennium, we find that approximately one-third of retiring Canadians have been unable to maintain their working-age consumption after retirement—a trend that is projected to worsen significantly for future Canadian retirees. The release of the Canadian NRRI is timely given the widespread concern that the current Canadian retirement income system is inadequate. Many proposals have recently emerged to extend and/or enhance Canadian public pensions, and the NRRI is a tool to test their merit. The methodology underlying the Canadian NRRI is uniquely sophisticated and comprehensive on account of our employment of Statistics Canada’s LifePaths, a state-of-the-art stochastic microsimulation model of the Canadian population. For instance, the Canadian NRRI is novel in that it models all of the relevant sources of consumption before and after retirement, while accounting for important features that are typically neglected in retirement adequacy studies such as family size, the variation of consumption over a person’s lifetime, and the heterogeneity among the life courses of individuals.

  11. The Canadian long-term experimental used fuel storage program

    International Nuclear Information System (INIS)

    Wasywich, K.M.; Taylor, P.

    1993-01-01

    The Canadian experimental fuel storage program consists of four components: (1) storage of used CANDU (CANadian Deuterium Uranium, registered trademark of AECL) fuel under water, with periodic examination; (2) storage of used CANDU fuel in dry air at seasonally varying temperatures, and in both dry and moisture-saturated air at 150 C, also with periodic examination; (3) underlying research on the oxidation of unused and used UO 2 in dry and moist air at temperatures up to 300 C; and (4) modeling of UO 2 oxidation in dry air. The primary objective of the fuel-storage experiments is to investigate the stability of used CANDU fuel during long-term storage. Burnup of the fuel in these experiments ranges from ∼43 to 582 MW h/kg U, while the outer-element linear power ratings range from 22 to 79 kW/m. The storage behavior of intact and intentionally defected fuel, and fuel that defected in-reactor, is being investigated in the above experiments. Since differences in UO 2 oxidation behavior were observed between dry-air, moisture-saturated air and wet storage of intentionally defected used CANDU fuel, underlying research was initiated on oxidation of unused and used fuel to develop a better understanding of the different mechanisms. Modeling of UO 2 oxidation based on the results of the dry-storage experiments is also under way

  12. Committing Canadian sociology: developing a Canadian sociology and a sociology of Canada.

    Science.gov (United States)

    Matthews, Ralph

    2014-05-01

    This paper is a slightly revised version of the author's "Outstanding Career Award Lecture" presented at the Annual Meeting of the Canadian Sociological Association in Victoria, British Columbia on June 6, 2013. The paper distinguishes between Canadian Sociology and the Sociology of Canada. The former involves the explanatory stance that one takes to understanding Canada. The latter addresses the significant social dimensions that underlie Canadian social organization, culture, and behavior. I make a case for a Canadian Sociology that focuses on the unique features of Canadian society rather than adopting a comparative perspective. I also argue that there is a continuing need within the Sociology of Canada to address the issues of staples development. However, I argue that "new" staples analysis must have a directional change from that of the past, in that social processes now largely determine the pattern of staples development. Moreover, new staples analysis must include issues that were never part of earlier staples analysis, such as issues of environmental impacts and of staples depletion under conditions, such as climate change. The paper concludes by analyzing four factors that provide the dominant social contexts for analyzing modern staples development: (1) the rise of neoliberal government, (2) the implementation of globalization and its social consequences, (3) the assumption of aboriginal rights and entitlement, and (4) the rise of environmentalism. These factors were generally not considered in earlier staples approaches. They are critical to understanding the role of staples development and its impact on Canada in the present time.

  13. Modelling the long-term corrosion behaviour of candidate alloys for Canadian SCWR

    Energy Technology Data Exchange (ETDEWEB)

    Steeves, G.; Cook, W., E-mail: wcook@unb.ca, E-mail: graham.steeves@unb.ca [University of New Brunswick, Department of Chemical Engineering, Fredericton, NB (Canada)

    2015-07-01

    Corrosion behaviour of Inconel 625 and Incoloy 800H, two of the candidate fuel cladding materials for Canadian supercritical water (SCW) reactor designs, were evaluated by exposing the metals to SCW in UNB's SCW flow loop. Individual experiments were conducted over a range of 370{sup o}C and 600{sup o}C. Exposure times were typically intervals of 100, 250, and 500 hours. Experimental data was used to create an empirical kinetic equation for each material. Activation energies for the alloys were determined, and showed a distinct difference between low-temperature electrochemical corrosion mechanism and direct high-temperature chemical oxidation. (author)

  14. Health practices of Canadian physicians.

    Science.gov (United States)

    Frank, Erica; Segura, Carolina

    2009-08-01

    To study the health and health practices of Canadian physicians, which can often influence patient health. Mailed survey. Canada. A random sample of 8100 Canadian physicians; 7934 were found to be eligible and 3213 responded (40.5% response rate). Factors that influence health, such as consumption of fruits and vegetables, amount of exercise and alcohol consumption, smoking status, body mass idex, and participation in preventive health screening measures, as well as work-life balance and emotional stability. Canadian physicians are healthy. More than 90% reported being in good to excellent health, and only 5% reported that poor physical or mental health made it difficult to handle their workload more than half the time in the previous month (although a quarter had reduced work activity because of long-term health conditions). Eight percent were obese, 3% currently smoked cigarettes, and 1% typically consumed 5 drinks or more on days when they drank alcohol. Physicians averaged 4.7 hours of exercise per week and ate fruits and vegetables 4.8 times a day. Their personal screening practices were largely compliant with Canadian Task Force on Preventive Health Care recommendations. They averaged 38 hours per week on patient care and 11 hours on other professional activities. Fifty-seven percent agreed that they had a good work-life balance, and 11% disagreed with the statement "If I can, I work when I am ill." Compared with self-reports from the general Canadian population, Canadian physicians, like American physicians, seem to be healthy and to have generally healthy behaviour. There is, however, room for improvement in physicians' personal and professional well-being, and improving their personal health practices could be an efficient and beneficent way to improve the health of all Canadians.

  15. Program for analyzing power boost tests

    International Nuclear Information System (INIS)

    Wills, C.A.

    1982-03-01

    A rapid increase of power in a reactor produces a failure in the fuel. Experiments to study the conditions in the NRU reactor after such failures have been planned and carried out. Given the concentrations of specified isotopes at a number of times over the length of an experiment as produced for example, from the program SARGS and the power history of the reactor, this program calculates the release rates, escape rate coefficients, and fractional releases for the isotopes. These values may be optionally printed and plotted. Decay schemes for a limited number of mass numbers are implemented. The program is written in FORTRAN and runs on the CDC 6600 - CYBER 170 system

  16. Canadian gas supply : an update

    International Nuclear Information System (INIS)

    Rochefort, T.

    1998-01-01

    An overview of the daily production from the Western Canada Sedimentary Basin (WCSB) from 1986 to 1997 was presented. This presentation also outlined Canadian production trends, Canadian reserves and resources, and supply challenges. Ultimate conventional marketable gas from the WCSB, the Scotian Shelf, the Beaufort Sea and Canada's Arctic region was estimated at 591 TCF. Issues regarding supply and demand of natural gas such as the impact of electricity restructuring on pricing, generation fuel mix, the capacity of the U.S. market to absorb Canadian heavy oil production, and the influence of the rate of technological advances on supply and demand were outlined. The overall conclusion confirmed the health and competitiveness of the Canadian upstream sector and expressed confidence that the WCSB can support rising levels of production to meet the expected continued market growth. tabs., figs

  17. An intercomparison of Canadian external dosimetry processors for radiation protection

    International Nuclear Information System (INIS)

    1989-10-01

    The five Canadian external dosimetry processors have participated in a two-stage intercomparison. The first stage involved dosimeters to known radiation fields under controlled laboratory conditions. The second stage involved exposing dosimeters to radiation fields in power reactor working environments. The results for each stage indicated the dose reported by each processor relative to an independently determined dose and relative to the others. The results of the intercomparisons confirm the original supposition: namely that the average differences in reported dose among five processors are much less than the uncertainty limits recommended by the ICRP. This report provides a description of the experimental methods as well as a discussion of the results for each stage. The report also includes a set of recommendations

  18. Microstructural examination of fuel rods subjected to a simulated large-break loss of coolant accident in reactor

    International Nuclear Information System (INIS)

    Garlick, A.

    1985-01-01

    A series of tests has been conducted in the National Research Universal (NRU) reactor, Chalk River, Canada, to investigate the behaviour of full-length 32-rod PWR fuel bundles during a simulated large-break loss of coolant accident (LOCA). In one of these tests (MT-3), 12 central rods were pre-pressurized in order to evaluate the ballooning and rupture of cladding in the Zircaloy high-α/α+β temperature region. All 12 rods ruptured after experiencing < 90% diametral strain but there was no suggestion of coplanar blockage. Post-irradiation examination was carried out on cross-sections of cladding from selected rods to determine the aximuthal distribution of wall thinning along the ballooned regions. These data are assessed to check whether they are consistent with a mechanism in which fuel stack eccentricity generates temperature gradients around the ballooning cladding and leads to premature rupture during a LOCA. After anodizing, the cladding microstructures were examined for the presence of prior-beta phase that would indicate the α/α+β transformation temperature (1078K) had been exceeded. These results were compared with isothermal annealing test data on unirradiated cladding from the same manufacturing batch

  19. SCW Pressure-Channel Nuclear Reactor Some Design Features

    Science.gov (United States)

    Pioro, Igor L.; Khan, Mosin; Hopps, Victory; Jacobs, Chris; Patkunam, Ruban; Gopaul, Sandeep; Bakan, Kurtulus

    Concepts of nuclear reactors cooled with water at supercritical pressures were studied as early as the 1950s and 1960s in the USA and Russia. After a 30-year break, the idea of developing nuclear reactors cooled with SuperCritical Water (SCW) became attractive again as the ultimate development path for water cooling. The main objectives of using SCW in nuclear reactors are: 1) to increase the thermal efficiency of modern Nuclear Power Plants (NPPs) from 30-35% to about 45-48%, and 2) to decrease capital and operational costs and hence decrease electrical energy costs (˜1000 US/kW or even less). SCW NPPs will have much higher operating parameters compared to modern NPPs (pressure about 25 MPa and outlet temperature up to 625°C), and a simplified flow circuit, in which steam generators, steam dryers, steam separators, etc., can be eliminated. Also, higher SCW temperatures allow direct thermo-chemical production of hydrogen at low cost, due to increased reaction rates. Pressure-tube or pressure-channel SCW nuclear reactor concepts are being developed in Canada and Russia for some time. Some design features of the Canadian concept related to fuel channels are discussed in this paper. The main conclusion is that the development of SCW pressure-tube nuclear reactors is feasible and significant benefits can be expected over other thermal-energy systems.

  20. Market potential for Canadian crude oil

    International Nuclear Information System (INIS)

    Heath, M.; Fisher, L.; Golosinski, D.; Luthin, A.; Gill, L.; Raggett, C.

    1997-01-01

    Future key markets for Canadian crude were evaluated, and probable flow volumes and prices were identified. Key concerns of market participants such as pricing, alternative crude sources, pipeline tariffs and crude quality, were examined. An overview of the competition faced by Canadian crude supply in global markets was presented. World crude oil supply and demand was discussed. US and Canadian crude oil supply (2000 to 2010), refinery demand for light and heavy crudes, existing future crude oil and refined product pipeline infrastructure, and pricing implications of changing crude oil flows were analyzed. The general conclusion was that the US market will continue to provide growing markets for Canadian crude oil, and that the Canadian supply to fulfill increased export requirements will be available due to the combined effects of increasing heavy crude supply, growing production from the east coast offshore, and recent and ongoing pipeline expansions and additions. 20 refs., 64 tabs., 42 figs

  1. Canadian hydrogen safety program

    International Nuclear Information System (INIS)

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

    2007-01-01

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

  2. The amazing vanishing Canadian dermatologist: results from the 2006 Canadian Dermatology Association member survey.

    Science.gov (United States)

    Chow, Eunice Y; Searles, Gordon E

    2010-01-01

    The 2006 Canadian Dermatology Association (CDA) member survey tracked the Canadian dermatology workforce. Information on use of nondermatologist extenders, impact of financial burden on practice style, and wait times was collected in the survey. To survey Canadian dermatologists for specialty-specific physician resource information including demographics, workload, and future career plans and compare it to results from the 2001 survey. In addition, to explore three other areas not covered in the previous survey: patient access to dermatologic care through wait times, the use of nondermatologist extenders, and potential impact of educational financial debt on practice styles. CDA members in 2006 were surveyed by mail. Follow-up mailings were done for nonresponders. Survey results were compared to those of the 2001 survey. Thirty-six percent (216 of 602) of Canadian dermatologists responded (70% in 2001). The national distribution was identical between surveys. The median age increased to 55 years; two-thirds of dermatologists are male. The median retirement age remained at 65 years. There was a shift from rural to urban practice locations; 78% practice in private offices. Three-fifths of dermatologists do mainly medical dermatology, a decrease between surveys. Pediatric dermatology decreased 10%, whereas surgical dermatology increased 52% between surveys. Fewer practitioners perform noninsured services, and half as many perform research or hospital consultations or teach medical students. Financial debt burden had no impact on selection of practice style. Median wait times for nonurgent consultations doubled from 5 to 10 weeks; follow-up visits increased from 4 to 5 weeks; noninsured consultations increased from 4 to 5 weeks. The national median wait time for a third available consultation appointment was 42 days (range 7-161 days). Seventeen percent of dermatologists reported using nondermatologist extenders. Training programs produce only 60% of new practitioners

  3. Nuclear waste management, reactor decommisioning, nuclear liability and public attitudes

    International Nuclear Information System (INIS)

    Green, R.E.

    1982-01-01

    This paper deals with several issues that are frequently raised by the public in any discussion of nuclear energy, and explores some aspects of public attitudes towards nuclear-related activities. The characteristics of the three types of waste associated with the nuclear fuel cycle, i.e. mine/mill tailings, reactor wastes and nuclear fuel wastes, are defined, and the methods currently being proposed for their safe handling and disposal are outlined. The activities associated with reactor decommissioning are also described, as well as the Canadian approach to nuclear liability. The costs associated with nuclear waste management, reactor decommissioning and nuclear liability are also discussed. Finally, the issue of public attitudes towards nuclear energy is addressed. It is concluded that a simple and comprehensive information program is needed to overcome many of the misconceptions that exist about nuclear energy and to provide the public with a more balanced information base on which to make decisions

  4. Canadian International Food Security Research Fund (CIFSRF ...

    International Development Research Centre (IDRC) Digital Library (Canada)

    Canadian International Food Security Research Fund (CIFSRF). The Canadian International Food Security Research Fund (CIFS-RF) is a collaborative program of the Canadian International Development Agency (CIDA) and IDRC valued at CA $61 654 707 (CIDA: CA $50 000 000; IDRC: CA $11 654 707). The program ...

  5. The accident at Chernobyl and its implications for the safety of CANDU reactors

    International Nuclear Information System (INIS)

    1987-05-01

    In August 1986, a delegation of Canadians, including two members of the staff of the AECB (Atomic Energy Control Board), attended a post-accident review meeting in Vienna, at which Soviet representatives described the accident and its causes and consequences. On the basis of the information presented at that meeting, AECB staff conducted a study of the accident to ascertain its implications for the safety of CANDU nuclear reactors and for the regulatory process in Canada. The conclusion of this review is that the accident at Chernobyl has not revealed any important new information which would have an effect on the safety requirements for CANDU reactors as presently applied by the AECB. All important aspects of the accident and its causes have been considered by the AECB in the licensing process for currently licensed reactors. However a number of recommendations are made with respect to aspects of reactor safety which should be re-examined in order to reinforce this conclusion

  6. The Supply of Medical Radioisotopes. Medical Isotope Supply in the Future: Production Capacity and Demand. Forecast for the 99Mo/99mTc Market, 2015-2020

    International Nuclear Information System (INIS)

    Peykov, Pavel; Cameron, Ron

    2014-04-01

    This document presents a forecast of 99 Mo/ 99m Tc production capacity and demand in 2015-2020, when two major irradiators - the OSIRIS and NRU reactors in France and Canada - are expected to exit the global supply chain and new alternative technology projects may be commissioned. The forecast does not attempt to predict shortages, but identify periods when there is an increased risk of disrupted supply, to inform policy makers and other stakeholders. (authors)

  7. Reactor construction programme in Japan

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1959-04-15

    In September last year, the Japanese Government requested the International Atomic Energy Agency to supply three tons of natural uranium for a research reactor, and the Agency has now arranged for its sale to Japan. The metal will be supplied in ingot form and after fabrication it will be used as fuel in a reactor of the natural uranium, heavy water type. The uranium will be obtained from Canada and sold to Japan by IAEA. The Agency had invited tenders for its supply, and after considering the tenders received, the Agency's Board of Governors decided that the Canadian offer to the Agency of three tons of natural uranium free of charge should be accepted and that the selling price to Japan should be US $35. 50 per kilogramme. The price takes into account Article XIV/E of the Agency's Statute which says that the Agency shall establish a scale of charges (including those for storage and handling) for materials furnished to Member States, and that the scale shall be designed to produce revenues to meet expenses in connexion with materials acquired by the Agency and costs of materials and services provided by it under agreements with one or more members. This is the first operation of its kind to be undertaken by the Agency, and the reactor for which the supply is being made will be the first in Japan to be constructed by Japanese scientists and technicians. IAEA's Board of Governors has given the necessary approval to the reactor project for which the Agency is providing assistance

  8. 2007 Canadian vehicle survey : summary report

    Energy Technology Data Exchange (ETDEWEB)

    Garcha, A.; Norup, S.; Kormylo, A.

    2009-09-15

    The Canadian vehicle survey is a quarterly survey of vehicle transportation activities in Canada that began in 1999. This report presented the results of the Canadian vehicle survey for 2007. The purpose of the survey is to encourage Canadians to make energy-efficient choices regarding their driving habits. The study shed light on Canadian fuel consumption behaviour, modes of transportation and consumer trends. This report examined the composition of Canada's vehicle fleet, the main characteristics of this fleet, and the patterns of vehicle use. Some behavioural characteristics of Canadian drivers were also discussed. Specific topics that were presented included Canada's on-road vehicle fleet; geographic analysis; light vehicles; heavy vehicles such as medium and heavy trucks; and trip analysis such as road types used by vehicles, rush hour and fuel consumption, and driver's age and gender. It was concluded that vehicles in Canada consumed 31 billion litres of gasoline and 11 billion litres of diesel. In addition, fuel efficiency for heavy trucks increased 21 percent between 2000 and 2007. 15 tabs., 39 figs., 4 appendices.

  9. Political Socialization Research and Canadian Studies

    Science.gov (United States)

    Tomkins, George S.

    1977-01-01

    Presents a review of the burgeoning field of Canadian political socialization research as it applies to children and youth, and considers some implications of recent findings for the Canadian studies curriculum. (Editor)

  10. Canadian gas resource

    International Nuclear Information System (INIS)

    Anon.

    1989-01-01

    Canadian exports of gas to the United States are a critical component of EMF-9 (North American Gas Supplies). However, it has been noted that there are differences between US expectations for imports and Canadian forecasts of export supply capacity. Recent studies by the National Petroleum Council (NPC) and the US Department of Energy (DOE) indicate that 1.8 to 2.4 Tcf of imports may be required in the mid to late 1990's; A recent study by Canada's National Energy Board (NEB) indicates that the conventional resource base may not be able to provide continued gas exports to the US after the mid 1990's and that frontier sources would need to be developed to meet US expectations. The discrepancies between US expectations and Canadian estimates of capacity are of great concern to US policymakers because they call into question the availability of secure supplies of natural gas and suggest that the cost of imports (if available) will be high. By implication, if shortages are to be averted, massive investment may be required to bring these higher cost sources to market. Since the long-term supply picture will be determined by the underlying resource base, EMF-9 participants have been asked to provide estimates of critical components of the Canadian resource base. This paper provides a summary of ICF-Lewin's recent investigation of both the Conventional and Tight Gas resource in Canada's Western Sedimentary Basin, which includes both quantitative estimates and a brief sketch of the analysis methodology

  11. CANDU - Canadian experience and expectations with the heavy-water reactor

    International Nuclear Information System (INIS)

    Foster, J.S.; Russell, S.H.

    1977-05-01

    The paper describes the evolution of the CANDU nuclear-power plants with particular reference to the objectives of safety, reliability and economy; the development of industrial capacity for the supply of fuel, components and heavy water; and the prospective development of advanced fuel cycles and the projected results. It provides data on radiation, releases, and exposures, internal and external to the power plants; plant availability, capacity factors and other performance data; heavy water production data with reference to safety, reliability, and economics; projections of the performance of CANDU reactors operating on a thorium-U-233 cycle and the development required to establish this cycle; and intent with respct to spent-fuel management and radioactive-waste storage. (author)

  12. Computation of a Canadian SCWR unit cell with deterministic and Monte Carlo codes

    International Nuclear Information System (INIS)

    Harrisson, G.; Marleau, G.

    2012-01-01

    The Canadian SCWR has the potential to achieve the goals that the generation IV nuclear reactors must meet. As part of the optimization process for this design concept, lattice cell calculations are routinely performed using deterministic codes. In this study, the first step (self-shielding treatment) of the computation scheme developed with the deterministic code DRAGON for the Canadian SCWR has been validated. Some options available in the module responsible for the resonance self-shielding calculation in DRAGON 3.06 and different microscopic cross section libraries based on the ENDF/B-VII.0 evaluated nuclear data file have been tested and compared to a reference calculation performed with the Monte Carlo code SERPENT under the same conditions. Compared to SERPENT, DRAGON underestimates the infinite multiplication factor in all cases. In general, the original Stammler model with the Livolant-Jeanpierre approximations are the most appropriate self-shielding options to use in this case of study. In addition, the 89 groups WIMS-AECL library for slight enriched uranium and the 172 groups WLUP library for a mixture of plutonium and thorium give the most consistent results with those of SERPENT. (authors)

  13. Canadian Irradiation Centre

    International Nuclear Information System (INIS)

    1987-05-01

    The Canadian Irradiation Centre is a non-profit cooperative project between Atomic Energy of Canada Limited, Radiochemical Company and Universite du Quebec, Institut Armand-Frappier, Centre for Applied Research in Food Science. The Centre's objectives are to develop, demonstrate and promote Canada's radiation processing technology and its applications by conducting applied research; training technical, professional and scientific personnel; educating industry and government; demonstrating operational and scientific procedures; developing processing procedures and standards, and performing product and market acceptance trials. This pamphlet outlines the history of radoation technology and the services offered by the Canadian Irradiation Centre

  14. Microscopy investigation on the corrosion of Canadian generation IV SCWR materials

    Energy Technology Data Exchange (ETDEWEB)

    Li, J. [CanmetMATERIALS, Hamilton, ON (Canada); Huang, X. [Carleton Univ., Ottawa, ON (Canada); Zeng, Y.; Zheng, W. [CanmetMATERIALS, Hamilton, ON (Canada); Woo, O.T.; Guzonas, D. [Atomic Energy Canada Limited, Chalk River, ON (Canada)

    2014-07-01

    Selection of fuel cladding materials for the Canadian Generation-IV Supercritical Water-cooled Reactor (SCWR) concept faces major challenges due to the severe operating conditions (650 {sup o}C and 25 MPa). High temperature microstructure stability and excellent resistance to general corrosion and stress corrosion cracking are key criteria. While corrosion resistance are generally assessed using weight change measurements and surface oxide examinations by optical and Scanning Electron Microscope (SEM) techniques, for materials exposed to SCW conditions, advanced analytical techniques that involve the use of Focused Ion Beam (FIB) and Transmission Electron Microscopy (TEM) techniques are required. This paper provides examples of such work conducted at CanmetMATERIALS and AECL to provide an in-depth understanding of the corrosion mechanisms of alloys exposed under SCW conditions. (author)

  15. "Canadianizing" an American Communication Textbook.

    Science.gov (United States)

    Maclennan, Jennifer M.

    2000-01-01

    Presents a study on the process involved in the "Canadianization" of U.S. textbooks for the domestic market. Explores whether disciplinary values have been shaped by the United States in the field of communication. Focuses on the experience of developing the Canadian edition of the book "Public Speaking: Strategies for Success"…

  16. Engendering migrant health: Canadian perspectives

    National Research Council Canada - National Science Library

    Spitzer, Denise L

    2011-01-01

    ... these and other issues at the intersections of gender, immigration, and health in the lives of new Canadians. Situating their work within the context of Canadian policy and society, the contributors illuminate migrants' testimonies of struggle, resistance, and solidarity as they negotiate a place for themselves in a new country. Topics range fr...

  17. The Canadian Dermatology Workforce Survey: implications for the future of Canadian dermatology--who will be your skin expert?

    Science.gov (United States)

    Maguiness, Sheilagh; Searles, Gordon E; From, Lynn; Swiggum, Susan

    2004-01-01

    To survey Canadian dermatologists for specialty-specific physician resource information including demographics, workload and future career plans. In 2001, the Canadian Dermatology Association (CDA) surveyed 555 dermatologists in Canada to gain specialty-specific physician resource information. Three hundred and seventy-one dermatologists (69%) provided information about themselves, their workloads and their future career goals. The average Canadian dermatologist is 52 years old and 35% of practicing dermatologists are over the age of 55. Eighty-nine percent of dermatologists practice in an urban setting, 19% include practice in a rural setting while less than 0.5% practice in remote areas. Canadian dermatologists spend 61% of their clinical time providing services in Medical Dermatology. Within 5 years, 50% of dermatologists reported that they plan to reduce their practices or retire. The Canadian Dermatology Workforce Survey provides a snapshot of the current practice of dermatology in Canada. It also serves to highlight the critical shortage of dermatologists, which will continue to worsen without immediate, innovative planning for the future.

  18. 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

  19. The 2 × 2 model of perfectionism: a comparison across Asian Canadians and European Canadians.

    Science.gov (United States)

    Franche, Véronique; Gaudreau, Patrick; Miranda, Dave

    2012-10-01

    The 2 × 2 model of perfectionism posits that the 4 within-person combinations of self-oriented and socially prescribed perfectionism (i.e., pure SOP, mixed perfectionism, pure SPP, and nonperfectionism) can be distinctively associated with psychological adjustment. This study examined whether the relationship between the 4 subtypes of perfectionism proposed in the 2 × 2 model (Gaudreau & Thompson, 2010) and academic outcomes (i.e., academic satisfaction and grade-point average [GPA]) differed across 2 sociocultural groups: Asian Canadians and European Canadians. A sample of 697 undergraduate students (23% Asian Canadians) completed self-report measures of dispositional perfectionism, academic satisfaction, and GPA. Results replicated most of the 2 × 2 model's hypotheses on ratings of GPA, thus supporting that nonperfectionism was associated with lower GPA than pure SOP (Hypothesis 1a) but with higher GPA than pure SPP (Hypothesis 2). Results also showed that mixed perfectionism was related to higher GPA than pure SPP (Hypothesis 3) but to similar levels as pure SOP, thus disproving Hypothesis 4. Furthermore, results provided evidence for cross-cultural differences in academic satisfaction. While all 4 hypotheses were supported among European Canadians, only Hypotheses 1a and 3 were supported among Asian Canadians. Future lines of research are discussed in light of the importance of acknowledging the role of culture when studying the influence of dispositional perfectionism on academic outcomes. (c) 2012 APA, all rights reserved.

  20. Western University (No. 10 Canadian Stationary Hospital and No. 14 Canadian General Hospital): a study of medical volunteerism in the First World War.

    Science.gov (United States)

    Istl, Alexandra C; McAlister, Vivian C

    2016-12-01

    The Canadian government depended on chaotic civilian volunteerism to staff a huge medical commitment during the First World War. Offers from Canadian universities to raise, staff and equip hospitals for deployment, initially rejected, were incrementally accepted as casualties mounted. When its offer was accepted in 1916, Western University Hospital quickly adopted military decorum and equipped itself using Canadian Red Cross Commission guidelines. Staff of the No. 10 Canadian Stationary Hospital and the No. 14 Canadian General Hospital retained excellent morale throughout the war despite heavy medical demand, poor conditions, aerial bombardment and external medical politics. The overwhelming majority of volunteers were Canadian-born and educated. The story of the hospital's commanding officer, Edwin Seaborn, is examined to understand the background upon which the urge to volunteer in the First World War was based. Although many Western volunteers came from British stock, they promoted Canadian independence. A classical education and a broad range of interests outside of medicine, including biology, history and native Canadian culture, were features that Seaborn shared with other leaders in Canadian medicine, such as William Osler, who also volunteered quickly in the First World War.

  1. Canadian environmental sustainability indicators: highlights 2005

    International Nuclear Information System (INIS)

    2005-12-01

    Canadians' health and their social and economic well-being are fundamentally linked to the quality of their environment. Recognizing this, in 2004 the Government of Canada committed to establishing national indicators of freshwater quality, air quality and greenhouse gas emissions. The goal of these new indicators is to provide Canadians with more regular and reliable information on the state of their environment and how it is linked with human activity. Canadians need clearly defined environmental indicators - measuring sticks that can track the results that have been achieved through the efforts of governments, industries and individuals to protect and improve the environment. Environment Canada, Statistics Canada and Health Canada are working together to further develop and communicate these indicators. Reflecting the joint responsibility for environmental management in Canada, this effort has benefited from the cooperation and input of the provinces and territories. The indicators are: air quality; greenhouse gas emissions; and, freshwater quality. Air quality tracks Canadians' exposure to ground-level ozone - a key component of smog. The indicator measures one of the most common, harmful air pollutants to which people are exposed. The use of the seasonal average of ozone concentrations reflects the potential for long-term health effects. Greenhouse gas emissions tracks the annual releases of the six greenhouse gases that are the major contributors to climate change. The indicator comes directly from the greenhouse gas inventory report prepared by Environment Canada for the United Nations Framework Convention on Climate Change (UNFCCC) and the Kyoto Protocol. The data are widely used to report on progress toward Canada's Kyoto target for reduced emissions. Freshwater quality reports the status of surface water quality at selected monitoring sites across the country. For this first report, the focus of the indicator is on the protection of aquatic life, such as

  2. Outlook for Canadian refining

    International Nuclear Information System (INIS)

    Boje, G.

    1998-01-01

    The petroleum supply and demand balance was discussed and a comparison between Canadian and U.S. refineries was provided. The impact of changing product specifications on the petroleum industry was also discussed. The major changes include sulphur reductions in gasoline, benzene and MMT additives. These changes have been made in an effort to satisfy environmental needs. Geographic margin variations in refineries between east and west were reviewed. An overview of findings from the Solomon Refining Study of Canadian and American refineries, which has been very complimentary of the Canadian refining industry, was provided. From this writer's point of view refinery utilization has improved but there is a threat from increasing efficiency of US competitors. Environmental issues will continue to impact upon the industry and while the chances for making economic returns on investment are good for the years ahead, it will be a challenge to maintain profitability

  3. Canadian guidelines for acute bacterial rhinosinusitis

    Science.gov (United States)

    Kaplan, Alan

    2014-01-01

    Objective To provide a clinical summary of the Canadian clinical practice guidelines for acute bacterial rhinosinusitis (ABRS) that includes relevant considerations for family physicians. Quality of evidence Guideline authors performed a systematic literature search and drafted recommendations. Recommendations received both strength of evidence and strength of recommendation ratings. Input from external content experts was sought, as was endorsement from Canadian medical societies (Association of Medical Microbiology and Infectious Disease Canada, Canadian Society of Allergy and Clinical Immunology, Canadian Society of Otolaryngology—Head and Neck Surgery, Canadian Association of Emergency Physicians, and the Family Physicians Airways Group of Canada). Main message Diagnosis of ABRS is based on the presence of specific symptoms and their duration; imaging or culture are not needed in uncomplicated cases. Treatment is dependent on symptom severity, with intranasal corticosteroids (INCSs) recommended as monotherapy for mild and moderate cases, although the benefit might be modest. Use of INCSs plus antibiotics is reserved for patients who fail to respond to INCSs after 72 hours, and for initial treatment of patients with severe symptoms. Antibiotic selection must account for the suspected pathogen, the risk of resistance, comorbid conditions, and local antimicrobial resistance trends. Adjunct therapies such as nasal saline irrigation are recommended. Failure to respond to treatment, recurrent episodes, and signs of complications should prompt referral to an otolaryngologist. The guidelines address situations unique to the Canadian health care environment, including actions to take during prolonged wait periods for specialist referral or imaging. Conclusion The Canadian guidelines provide up-to-date recommendations for diagnosis and treatment of ABRS that reflect an evolving understanding of the disease. In addition, the guidelines offer useful tools to help

  4. On Realities of Canadian Multiculturalism

    Institute of Scientific and Technical Information of China (English)

    李梦辰

    2013-01-01

    Canada is a multicultural country which was mainly established by immigrants. Just because of that, Canadian govern⁃ment has carried out the policy of multiculturalism since1970s. However, it has encountered many problems such as policy con⁃flicts, national identity, democracy-inquiry and racial discrimination, etc. Hence the Canadian multiculturalism has been in a di⁃lemma.

  5. Canadian perspectives on food irradiation

    International Nuclear Information System (INIS)

    Kunstadt, P.

    1988-01-01

    Canada has been in the forefront of irradiation technology for some 30 years. Nearly 90 of the 140 irradiators used worldwide are Canadian-built, yet Canadian food processors have been very slow to use the technology. The food irradiation regulatory situation in Canada, the factors that influence it, and some significant non-regulatory developments are reviewed. (author)

  6. SEALER: a very small lead cooled fast reactor for commercial energy production in off-grid communities

    Energy Technology Data Exchange (ETDEWEB)

    Wallenius, J., E-mail: janne@leadcold.com [LeadCold Reactors, Dalgatan 3C, Marsta (Sweden); Bortot, S., E-mail: sara.bortot@psi.ch [Paul Scherrer Inst., Villigen (Switzerland)

    2014-07-01

    SEALER (Swedish Advanced Lead Reactor) is a small lead cooled fast reactor operating on 20% enriched UO{sub 2} fuel. It is designed for commercial production of electricity and heat in the Canadian arctic. In this paper, we present an updated set of reactivity coefficients for the SEALER core, used in simulations of un-protected transients such as control-rod withdrawal, and loss of flow. The analysis is carried out using the SAS4A/SASSYS-1 (SAS) system code developed by ANL and the BELLA multi-point dynamics code developed by KTH and PSI. (author)

  7. Canadian national nuclear forensics capability project

    International Nuclear Information System (INIS)

    Ball, J.; Dimayuga, I.; Summerell, I.; Totland, M.; Jonkmans, G.; Whitlock, J.; El-jaby, A.; Inrig, E.

    2015-01-01

    Following the 2010 Nuclear Security Summit, Canada expanded its existing capability for nuclear forensics by establishing a national nuclear forensics laboratory network, which would include a capability to perform forensic analysis on nuclear and other radioactive material, as well as on traditional evidence contaminated with radioactive material. At the same time, the need for a national nuclear forensics library of signatures of nuclear and radioactive materials under Canadian regulatory control was recognized. The Canadian Safety and Security Program, administered by Defence Research and Development Canada's Centre for Security Science (DRDC CSS), funds science and technology initiatives to enhance Canada's preparedness for prevention of and response to potential threats. DRDC CSS, with assistance from Canadian Nuclear Laboratories, formerly Atomic Energy of Canada Limited, is leading the Canadian National Nuclear Forensics Capability Project to develop a coordinated, comprehensive, and timely national nuclear forensics capability. (author)

  8. Canadian perspectives in evaluating transparency

    International Nuclear Information System (INIS)

    Herwig, L.

    2007-01-01

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

  9. Fording Canadian Coal Trust

    Energy Technology Data Exchange (ETDEWEB)

    Popowich, J.; Millos, R. [Elk Valley Coal Corporation, Calgary, AB (Canada)

    2004-07-01

    This is the first of five slide/overhead presentations presented at the Fording Canadian Coal Trust and Tech Cominco Ltd. investor day and mine tour. The Fording Canadian Coal Trust is described. The Trust's assets comprise six Elk Valley metallurgical coal mines and six wollastonite operations (in the NYCO Group). Trust structure, corporate responsibility, organizational structure, reserves and resources, management philosophy, operating strategies, steel market dynamics, coal market, production expansion, sales and distribution are outlined. 15 figs., 5 tabs.

  10. The LEU target development and conversion program for the MAPLE reactors and new processing facility

    International Nuclear Information System (INIS)

    Malkoske, G.R.

    2003-01-01

    The availability of isotope grade, Highly Enriched Uranium (HEU), from the United States for use in the manufacture of targets for molybdenum-99 production in AECL's NRU research reactor has been a key factor to enable MDS Nordion to develop a reliable, secure supply of medical isotopes for the international nuclear medicine community. The molybdenum extraction process from HEU targets is a proven and established method that has reliably produced medical isotopes for several decades. The HEU process provides predictable, consistent yields for our high-volume, molybdenum-99 production. Other medical isotopes such as I-131 and Xe-133, which play an important role in nuclear medicine applications, are also produced from irradiated HEU targets as a by-product of the molybdenum-99 process. To ensure a continued reliable and timely supply of medical isotopes, MDS Nordion is completing the commissioning of two MAPLE reactors and an associated isotope processing facility (the New Processing Facility). The new MAPLE facilities, which will be dedicated exclusively to medical isotope production, will provide an essential contribution to a secure, robust global healthcare system. Design and construction of these facilities has been based on a life cycle management philosophy for the isotope production process. This includes target irradiation, isotope extraction and waste management. The MAPLE reactors will operate with Low Enriched Uranium (LEU) fuel, a significant contribution to the objectives of the RERTR program. The design of the isotope production process in the MAPLE facilities is based on an established process - extraction of isotopes from HEU target material. This is a proven technology that has been demonstrated over more than three decades of operation. However, in support of the RERTR program and in compliance with U.S. legislation, MDS Nordion has undertaken a LEU Target Development and Conversion Program for the MAPLE facilities. This paper will provide an

  11. Thermodynamic analysis of a supercritical water reactor

    International Nuclear Information System (INIS)

    Edwards, M.

    2007-01-01

    A thermodynamic model has been developed for a hypothetical design of a Supercritical Water Reactor, with emphasis on Canadian design criteria. The model solves for cycle efficiency, mass flows and physical conditions throughout the plant based on input parameters of operating pressures and efficiencies of components. The model includes eight feedwater heaters, three feedwater pumps, a deaerator, a condenser, the core, three turbines and two reheaters. To perform the calculations, Microsoft Excel was used in conjunction with FLUIDCAL-IAPWS95 and VBA code. The calculations show that a thermal efficiency of 47.5% can be achieved with a core outlet temperature of 625 o C. (author)

  12. Canadian national nuclear forensics capability project

    Energy Technology Data Exchange (ETDEWEB)

    Ball, J.; Dimayuga, I., E-mail: joanne.ball@cnl.ca [Canadian Nuclear Laboratories, Chalk River, Ontario (Canada); Summerell, I. [Royal Canadian Mounted Police, Ottawa, Ontario (Canada); Totland, M. [Canadian Nuclear Laboratories, Chalk River, Ontario (Canada); Jonkmans, G. [Defence Research and Development Canada, Ottawa, Ontario (Canada); Whitlock, J. [Canadian Nuclear Laboratories, Chalk River, Ontario (Canada); El-jaby, A. [Canadian Nuclear Safety Commission, Ottawa, Ontario (Canada); Inrig, E. [Defence Research and Development Canada, Ottawa, Ontario (Canada)

    2015-06-15

    Following the 2010 Nuclear Security Summit, Canada expanded its existing capability for nuclear forensics by establishing a national nuclear forensics laboratory network, which would include a capability to perform forensic analysis on nuclear and other radioactive material, as well as on traditional evidence contaminated with radioactive material. At the same time, the need for a national nuclear forensics library of signatures of nuclear and radioactive materials under Canadian regulatory control was recognized. The Canadian Safety and Security Program, administered by Defence Research and Development Canada's Centre for Security Science (DRDC CSS), funds science and technology initiatives to enhance Canada's preparedness for prevention of and response to potential threats. DRDC CSS, with assistance from Canadian Nuclear Laboratories, formerly Atomic Energy of Canada Limited, is leading the Canadian National Nuclear Forensics Capability Project to develop a coordinated, comprehensive, and timely national nuclear forensics capability. (author)

  13. Plutonium Consumption Program, CANDU Reactor Project final report

    Energy Technology Data Exchange (ETDEWEB)

    1994-07-31

    DOE is investigating methods for long term dispositioning of weapons grade plutonium. One such method would be to utilize the plutonium in Mixed OXide (MOX) fuel assemblies in existing CANDU reactors. CANDU (Canadian Deuterium Uranium) reactors are designed, licensed, built, and supported by Atomic Energy of Canada Limited (AECL), and currently use natural uranium oxide as fuel. The MOX spent fuel assemblies removed from the reactor would be similar to the spent fuel currently produced using natural uranium fuel, thus rendering the plutonium as unattractive as that in the stockpiles of commercial spent fuel. This report presents the results of a study sponsored by the DOE for dispositioning the plutonium using CANDU technology. Ontario Hydro`s Bruce A was used as reference. The fuel design study defined the optimum parameters to disposition 50 tons of Pu in 25 years (or 100 tons). Two alternate fuel designs were studied. Safeguards, security, environment, safety, health, economics, etc. were considered. Options for complete destruction of the Pu were also studied briefly; CANDU has a superior ability for this. Alternative deployment options were explored and the potential impact on Pu dispositioning in the former Soviet Union was studied. An integrated system can be ready to begin Pu consumption in 4 years, with no changes required to the reactors other than for safe, secure storage of new fuel.

  14. Plutonium Consumption Program, CANDU Reactor Project final report

    International Nuclear Information System (INIS)

    1994-01-01

    DOE is investigating methods for long term dispositioning of weapons grade plutonium. One such method would be to utilize the plutonium in Mixed OXide (MOX) fuel assemblies in existing CANDU reactors. CANDU (Canadian Deuterium Uranium) reactors are designed, licensed, built, and supported by Atomic Energy of Canada Limited (AECL), and currently use natural uranium oxide as fuel. The MOX spent fuel assemblies removed from the reactor would be similar to the spent fuel currently produced using natural uranium fuel, thus rendering the plutonium as unattractive as that in the stockpiles of commercial spent fuel. This report presents the results of a study sponsored by the DOE for dispositioning the plutonium using CANDU technology. Ontario Hydro's Bruce A was used as reference. The fuel design study defined the optimum parameters to disposition 50 tons of Pu in 25 years (or 100 tons). Two alternate fuel designs were studied. Safeguards, security, environment, safety, health, economics, etc. were considered. Options for complete destruction of the Pu were also studied briefly; CANDU has a superior ability for this. Alternative deployment options were explored and the potential impact on Pu dispositioning in the former Soviet Union was studied. An integrated system can be ready to begin Pu consumption in 4 years, with no changes required to the reactors other than for safe, secure storage of new fuel

  15. The Liberalization of Canadian Immigration Policy (1945-1976

    Directory of Open Access Journals (Sweden)

    Mariia Burtseva

    2017-07-01

    Full Text Available Immigration policy has played a key role in Canadian history since the second half of 19th century. Certainly, immigration legislation was a major element of it. Some of the most important reforms in Canadian immigration policy took place in the first decades after the Second World War. This was a time of multiple legislative reforms conducted by the Canadian government, but in general, the immigration regulations introduced during that period started the process of liberalization in this area. The Immigration Act of 1976 played a key role in building up the new liberal strategy of Canadian immigration. The pre-reform period is also important because it helps to understand the evolution process from discrimi¬native legislation to liberal policy. Therefore, the focus of this study is on the development of Canadian immigration policy from 1945 to 1976. The present research examines the main preconditions for the adoption of the 1976 Immigration Act. It analyses legislation regulations, which paved the ground for post-war Canadian immigration policy, with a particular emphasis on regula-tions enacted from 1945 to 1976. This article provides an overview of Canadian immigration policy in post-war period. It also identifies successive documents that proved particularly influential for Canadian immigration policy at the time. The findings of this research point to a variety of causes for the legislation changes, from foreign and domestic policy to economy policy.

  16. A perspective on Canadian shale gas

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, Mike; Davidson, Jim; Mortensen, Paul

    2010-09-15

    In a relatively new development over just the past few years, shale formations are being targeted for natural gas production. Based on initial results, there may be significant potential for shale gas in various regions of Canada, not only in traditional areas of conventional production but also non-traditional areas. However, there is much uncertainty because most Canadian shale gas production is currently in experimental or early developmental stages. Thus, its full potential will not be known for some time. If exploitation proves to be successful, Canadian shale gas may partially offset projected long-term declines in Canadian conventional natural gas production.

  17. SCC-induced failure of a 304 stainless steel pipe

    International Nuclear Information System (INIS)

    Tapping, R.L.; Disney, D.J.; Szostak, F.J.

    1993-01-01

    On 1991 January 12, a 304 Stainless Steel (SS) suction line in the AECL-Research NRU reactor failed, shutting down the reactor for approximately 12 months. The pipe, a 32 mm schedule 40 304 stainless steel line exposed to D 2 O at temperatures ≤35 degrees C had been in service for approximately 20 years, although no manufacturing data or composition specifications were available. The failure and resultant leak resulted in a small loss of D 2 O moderator from the reactor vessel. The pipe cracked approximately 180 degrees C around the circumference of a weld. This failure was unexpected and hense a thorough metallographic examination was carried out on the failed section, on the rest of the line (Line 1212), and on representative samples from the rest of the reactor in order to assess the integrity of the remaining piping

  18. 2010 Canadian Cardiovascular Society/Canadian Heart Rhythm Society Training Standards and Maintenance of Competency in Adult Clinical Cardiac Electrophysiology.

    Science.gov (United States)

    Green, Martin S; Guerra, Peter G; Krahn, Andrew D

    2011-01-01

    The last guidelines on training for adult cardiac electrophysiology (EP) were published by the Canadian Cardiovascular Society in 1996. Since then, substantial changes in the knowledge and practice of EP have mandated a review of the previous guidelines by the Canadian Heart Rhythm Society, an affiliate of the Canadian Cardiovascular Society. Novel tools and techniques also now allow electrophysiologists to map and ablate increasingly complex arrhythmias previously managed with pharmacologic or device therapy. Furthermore, no formal attempt had previously been made to standardize EP training across the country. The 2010 Canadian Cardiovascular Society/Canadian Heart Rhythm Society Training Standards and Maintenance of Competency in Adult Clinical Cardiac Electrophysiology represent a consensus arrived at by panel members from both societies, as well as EP program directors across Canada and other select contributors. In describing program requirements, the technical and cognitive skills that must be acquired to meet training standards, as well as the minimum number of procedures needed in order to acquire these skills, the new guidelines provide EP program directors and committee members with a template to develop an appropriate curriculum for EP training for cardiology fellows here in Canada. Copyright © 2011 Canadian Cardiovascular Society. Published by Elsevier Inc. All rights reserved.

  19. Field experience in use of radiation instruments in Cirus reactor

    International Nuclear Information System (INIS)

    Ramesh, N.; Sharma, R.C.; Agarwal, S.K.; Sawant, D.K.; Yadav, R.K.B.; Prasad, S.K.

    2005-01-01

    Cirus, located at Bhabha Atomic Research Centre, is a 40 MW (Th) research reactor fuelled by natural uranium, moderated by heavy water and cooled by de-mineralized light water. Graphite is used as reflector in this reactor. The reactor, commissioned in the year 1960, was in operation with availability factor of about 70% till early nineties. There after signs of ageing started surfacing up. After ageing studies, refurbishment plan was finalized and executed during the period from 1997-2002. after successful refurbishment, the reactor is in operation at full power. A wide range of radiation instruments have been used at Cirus for online monitoring of the radiological status of various process systems and environmental releases. Also, variety of survey meters, counting systems and monitors have been used by the health physics unit of the reactor for radiation hazard control. Many of these instruments, which were originally of Canadian design, have undergone changes due to obsolescence or as part of upgradation. This paper describes the experience with the radiation instruments of Cirus, bringing out their effectiveness in meeting the design intent, difficulties faced in their field use, and modifications carried out based on the performance feed back. Also, this paper highlights the areas where further efforts are needed to develop nuclear instrumentation to further strengthen monitoring and surveillance. (author)

  20. Canadian perspectives on food irradiation

    International Nuclear Information System (INIS)

    Kunstadt, P.

    1990-01-01

    Canada has been in the forefront of irradiation technology for over 30 years. Some 83 of the 147 irradiators used worldwide are Canadian-built, yet Canadian food processors have been very slow to use the technology. This paper is an update on the food irradiation regulatory situation in Canada and the factors that influence it. It also reviews some significant non-regulatory developments. (author)

  1. The regional control of the canadian energy production; Le contraste provincial de la production energetique canadienne

    Energy Technology Data Exchange (ETDEWEB)

    Petitlaurent, S.; Sarrazin, J

    2004-12-01

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

  2. Implications of globalization on pricing for Canadian crudes

    Energy Technology Data Exchange (ETDEWEB)

    Black, R. [Canadian Occidental Petroleum Ltd., Calgary, AB (Canada)

    1998-05-01

    The effects of globalization on Canadian crude oil prices was discussed. Since deregulation in October 1985, Canadian crude oil has competed directly against international crude oil through the use of the NYMEX contract price for light sweet crude oil as the base for establishing the price for Canadian crudes. Prior to that date, Alberta crude was marketed by the Alberta Petroleum Marketing Commission using the old block matrix which was loosely tied to the world market price. In addition to world crude oil prices other factors that affect the price of Canadian crude oil include technology impacts and global integration. Also, when the Sarnia to Montreal pipeline (Line 9) is reversed to bring offshore crude oil into the Ontario refining community, Canadian producers can expect some adverse effects on the price they are paid for their products leading up to the reversal as refiners start to swing over to their alternate suppliers. The offshore supply is expected to be about 140,000 barrels/day of light sweet crude oil, but all grades of Canadian crude oil will be affected.

  3. The flow of radionuclides through the Canadian archipelago

    International Nuclear Information System (INIS)

    Ellis, K.; Smith, J.N.

    1999-01-01

    The transport of contaminants to the Canadian Arctic by air and in water and their concentration through the marine food web has lead to enhanced levels of contaminants in several foods of Canadian northern inhabitants. Artificial radionuclides in the marine water can be used to determine water circulation and to trace contaminant transport through the Canadian Archipelago

  4. A Solution-Based Approach for Mo-99 Production: Considerations for Nitrate versus Sulfate Media

    Directory of Open Access Journals (Sweden)

    Amanda J. Youker

    2013-01-01

    Full Text Available Molybdenum-99 is the parent of Technetium-99m, which is used in nearly 80% of all nuclear medicine procedures. The medical community has been plagued by Mo-99 shortages due to aging reactors, such as the NRU (National Research Universal reactor in Canada. There are currently no US producers of Mo-99, and NRU is scheduled for shutdown in 2016, which means that another Mo-99 shortage is imminent unless a potential domestic Mo-99 producer fills the void. Argonne National Laboratory is assisting two potential domestic suppliers of Mo-99 by examining the effects of a uranyl nitrate versus a uranyl sulfate target solution configuration on Mo-99 production. Uranyl nitrate solutions are easier to prepare and do not generate detectable amounts of peroxide upon irradiation, but a high radiation field can lead to a large increase in pH, which can lead to the precipitation of fission products and uranyl hydroxides. Uranyl sulfate solutions are more difficult to prepare, and enough peroxide is generated during irradiation to cause precipitation of uranyl peroxide, but this can be prevented by adding a catalyst to the solution. A titania sorbent can be used to recover Mo-99 from a highly concentrated uranyl nitrate or uranyl sulfate solution; however, different approaches must be taken to prevent precipitation during Mo-99 production.

  5. Recent Books on Canadian Business History.

    Science.gov (United States)

    Armstrong, Christopher

    1979-01-01

    Reviews Canadian business history books published since 1972 as well as reprints of useful older works. Topics dealt with are the fish, timber, and wheat industry, transportation, entrepreneurs and entrepreneurship, Canadian economy during World War I, the development of natural resources, and the lives of the rich and the powerful. (KC)

  6. Canadian advanced life support capacities and future directions

    Science.gov (United States)

    Bamsey, M.; Graham, T.; Stasiak, M.; Berinstain, A.; Scott, A.; Vuk, T. Rondeau; Dixon, M.

    2009-07-01

    Canada began research on space-relevant biological life support systems in the early 1990s. Since that time Canadian capabilities have grown tremendously, placing Canada among the emerging leaders in biological life support systems. The rapid growth of Canadian expertise has been the result of several factors including a large and technically sophisticated greenhouse sector which successfully operates under challenging climatic conditions, well planned technology transfer strategies between the academic and industrial sectors, and a strong emphasis on international research collaborations. Recent activities such as Canada's contribution of the Higher Plant Compartment of the European Space Agency's MELiSSA Pilot Plant and the remote operation of the Arthur Clarke Mars Greenhouse in the Canadian High Arctic continue to demonstrate Canadian capabilities with direct applicability to advanced life support systems. There is also a significant latent potential within Canadian institutions and organizations with respect to directly applicable advanced life support technologies. These directly applicable research interests include such areas as horticultural management strategies (for candidate crops), growth media, food processing, water management, atmosphere management, energy management, waste management, imaging, environment sensors, thermal control, lighting systems, robotics, command and data handling, communications systems, structures, in-situ resource utilization, space analogues and mission operations. With this background and in collaboration with the Canadian aerospace industry sector, a roadmap for future life support contributions is presented here. This roadmap targets an objective of at least 50% food closure by 2050 (providing greater closure in oxygen, water recycling and carbon dioxide uptake). The Canadian advanced life support community has chosen to focus on lunar surface infrastructure and not low Earth orbit or transit systems (i.e. microgravity

  7. Liquid fuels from Canadian coals

    Energy Technology Data Exchange (ETDEWEB)

    Taylor, G. W.

    1979-06-15

    In Canadian energy planning, the central issue of security of supply must be addressed by developing flexible energy systems that make the best possible use of available resources. For liquid fuel production, oil sands and heavy oil currently appear more attractive than coal or biomass as alternatives to conventional crude oil, but the magnitude of their economic advantage is uncertain. The existence of large resources of oil sands, heavy oils, natural gas and low-sulfur coals in Western Canada creates a unique opportunity for Canadians to optimize the yield from these resources and develop new technology. Many variations on the three basic liquefaction routes - hydroliquefaction, pyrolysis and synthesis - are under investigation around the world, and the technology is advancing rapidly. Each process has merit under certain circumstances. Surface-mineable subbituminous and lignite coals of Alberta and Saskatchewan appear to offer the best combination of favorable properties, deposit size and mining cost, but other deposits in Alberta, Nova Scotia and British Columbia should not be ruled out. The research effort in Canada is small by world standards, but it is unlikely that technology could be imported that is ideally suited to Canadian conditions. Importing technology is undesirable: innovation or process modification to suit Canadian coals and markets is preferred; coprocessing of coal liquids with bitumen or heavy oils would be a uniquely Canadian, exportable technology. The cost of synthetic crude from coal in Canada is uncertain, estimates ranging from $113 to $220/m/sup 3/ ($18 to $35/bbl). Existing economic evaluations vary widely depending on assumptions, and can be misleading. Product quality is an important consideration.

  8. Tuberculosis in Aboriginal Canadians

    Directory of Open Access Journals (Sweden)

    Vernon H Hoeppner

    2000-01-01

    Full Text Available Endemic tuberculosis (TB was almost certainly present in Canadian aboriginal people (aboriginal Canadians denotes status Indians, Inuit, nonstatus Indians and metis as reported by Statistics Canada before the Old World traders arrived. However, the social changes that resulted from contact with these traders created the conditions that converted endemic TB into epidemic TB. The incidence of TB varied inversely with the time interval from this cultural collision, which began on the east coast in the 16th century and ended in the Northern Territories in the 20th century. This relatively recent epidemic explains why the disease is more frequent in aboriginal children than in Canadian-born nonaboriginal people. Treatment plans must account for the socioeconomic conditions and cultural characteristics of the aboriginal people, especially healing models and language. Prevention includes bacillus Calmette-Guerin vaccination and chemoprophylaxis, and must account for community conditions, such as rates of suicide, which have exceeded the rate of TB. The control of TB requires a centralized program with specifically directed funding. It must include a program that works in partnership with aboriginal communities.

  9. Research Awards: Canadian Partnerships Program Deadline: 12 ...

    International Development Research Centre (IDRC) Digital Library (Canada)

    Jean-Claude Dumais

    2012-09-12

    Sep 12, 2012 ... IDRC's Canadian Partnerships (CP) Program offers a Research ... For this, they may consider quantitative and qualitative methods, case studies, ... What types of processes do Canadian organizations use to learn about their ...

  10. Installation of a second trip system

    International Nuclear Information System (INIS)

    Bessada, E.

    1997-01-01

    Since its first criticality in 1957, the NRU reactor has been operating safely and efficiently supporting the CANDU reactor's research and development programs and producing radioisotopes for medical use. To ensure that the reactor continues to operate safely and effectively, Atomic Energy of Canada Limited (AECL) commissioned a team in 1989 to conduct a systematic review and assessment of the reactor condition. The outcome of the study indicated that the overall condition of the reactor is good and that it is being operated safely. The study also produced recommendations as to where safety can be improved. These recommendations are the basis of the upgrade program currently being implemented in the reactor. The Second Trip System (STS) is part of the upgrade program. It is a stand alone seismically qualified trip system that operates independently from the existing first trip system (FST) to shutdown the reactor. This paper discusses the design, installation and the inactive commissioning of the system, and the process used to ensure that the system can be retrofitted to the reactor without affecting its safety or its operational requirements. (author)

  11. There be dragons: Canadian explorers in international fields

    Energy Technology Data Exchange (ETDEWEB)

    O' Meara, D

    1999-11-01

    International hotspots of Canadian exploration and production companies are described. Examples of mid-sized Canadian companies competing successfully in many parts of the world are recounted. Being Canadian and having access to countries that Americans do not because of trade sanctions, allows Canadian companies to bring to these countries all the North American technology without the associated politics. Successes by Canadian Occidental Petroleum in Yemen, in Africa, the former Soviet Union and South America, or Alberta Energy Company International's recent commitment to explore in Azerbaijan with estimated reserves of 5.9 billion barrels of oil-equivalent, are only some of the examples where Canadian explorers have been very successful. Some of the problems faced by international operators such as scarcity of indigenous trained personnel, lack of infrastructure, unstable governments, and/or unfriendly government policies, tribal wars, unfavourable public reaction 'back home' to repressive regimes in parts of the world ( e.g. Talisman Energy in Sudan) are some of the dangers faced by companies venturing into the global arena, driven by dreams of untold riches, but also by the prospects of diminishing reserves on home turf.

  12. There be dragons: Canadian explorers in international fields

    Energy Technology Data Exchange (ETDEWEB)

    O' Meara, D.

    1999-11-01

    International hotspots of Canadian exploration and production companies are described. Examples of mid-sized Canadian companies competing successfully in many parts of the world are recounted. Being Canadian and having access to countries that Americans do not because of trade sanctions, allows Canadian companies to bring to these countries all the North American technology without the associated politics. Successes by Canadian Occidental Petroleum in Yemen, in Africa, the former Soviet Union and South America, or Alberta Energy Company International's recent commitment to explore in Azerbaijan with estimated reserves of 5.9 billion barrels of oil-equivalent, are only some of the examples where Canadian explorers have been very successful. Some of the problems faced by international operators such as scarcity of indigenous trained personnel, lack of infrastructure, unstable governments, and/or unfriendly government policies, tribal wars, unfavourable public reaction 'back home' to repressive regimes in parts of the world ( e.g. Talisman Energy in Sudan) are some of the dangers faced by companies venturing into the global arena, driven by dreams of untold riches, but also by the prospects of diminishing reserves on home turf.

  13. Canadian petroleum industry review

    International Nuclear Information System (INIS)

    Feick, R. M.

    1997-01-01

    A wide ranging discussion about the factors that have influenced oil and natural gas prices, the differences of the Canadian market from international markets, the differences between eastern and western Canadian markets, and shareholders' perspectives on recent commodity price developments was presented. Developments in the OPEC countries were reviewed, noting that current OPEC production of 25 mmbbls is about 60 per cent higher than it was in 1985. It is expected that OPEC countries will continue to expand capacity to meet expected demand growth and the continuing need created by the UN embargo on Iraqi oil sales. Demand for natural gas is also likely to continue to rise especially in view of the deregulation of the electricity industry where natural gas may well become the favored fuel for incremental thermal generation capacity. Prices of both crude oil and natural gas are expected to hold owing to unusually low storage levels of both fuels. The inadequacy of infrastructure, particularly pipeline capacity as a key factor in the Canadian market was noted, along with the dynamic that will emerge in the next several years that may have potential consequences for Canadian production - namely the reversal of the Sarnia to Montreal pipeline. With regard to shareholders' expectations the main issues are (1) whether international markets reach back to the wellhead, hence the producer's positioning with respect to transportation capacity and contract portfolios, and (2) whether the proceeds from increased prices are invested in projects that are yielding more than the cost of capital. 28 figs

  14. Social Workers' Role in the Canadian Mental Health Care System

    Science.gov (United States)

    Towns, Ashley M.; Schwartz, Karen

    2012-01-01

    Objective: Using Canadian survey data this research provides social workers in Canada with a better understanding of their role in the Canadian mental health care system. Methods: By analyzing data from the Canadian Community Health Survey, Cycle 1.2 Mental Health and Well-being, the role of social workers in the Canadian mental health system was…

  15. The safety of Ontario's nuclear power reactors. A scientific and technical review. A submission to the Ontario Nuclear Safety Review by Atomic Energy Canada Limited

    International Nuclear Information System (INIS)

    1987-01-01

    This submission comments on the evolution of the Canadian nuclear program, the management of safety, and the reactor design, analysis, operation and research programs that contribute to the safety of the CANDU reactor and provide assurance of safety to the regulatory agency and to the public. The CANDU reactor system has been designed and developed with close cooperation between Atomic Energy of Canada Ltd. (AECL), utilities, manufacturers, and the Atomic Energy Control Board (AECB). The AECB has the responsibility, on behalf of the public, for establishing acceptable standards with respect to public risk and for establishing through independent review that these standards are satisfied. The plant designer has responsibility for defining how those standards will be met. The plant operator has responsibility for operating within the framework of those standards. The Canadian approach to safety design is based on the philosophy of defence in depth. Defence in depth is achieved through a high level of equipment quality, system redundancy and fail-safe design; regulating and process systems designed to maintain all process systems within acceptable operating parameters; and, independent safety systems to shut down the reactor, provide long-term cooling, and contain potential release of radioactivity in the event of an accident. The resulting design meets regulatory requirements not only in Canada but also in other countries. Probabilistic safety and risk evaluations show that the CANDU design offers a level of safety and least as good as other commercially available reactor designs

  16. The Canadian elder standard - pricing the cost of basic needs for the Canadian elderly.

    Science.gov (United States)

    MacDonald, Bonnie-Jeanne; Andrews, Doug; Brown, Robert L

    2010-03-01

    We determined the after-tax income required to finance basic needs for Canadian elders living with different circumstances in terms of age, gender, city of residence, household size, homeowner or renter status, means of transportation, and health status. Using 2001 as our base year, we priced the typical expenses for food, shelter, medical, transportation, miscellaneous basic living items and home-based long-term care for elders living in five Canadian cities. This is the first Canadian study of basic living expenses tailored to elders instead of adults in general, prepared on an absolute rather than a relative basis. We also accounted for an individual's unique life circumstances and established the varying effect that they have on the cost of basic expenses, particularly for home care. We found that the maximum Guaranteed Income Supplement and Old Age Security benefit did not meet the cost of basic needs for an elder living in poor circumstances.

  17. The low power miniature neutron source reactors: Design, safety and applications

    International Nuclear Information System (INIS)

    Ahmed, Y.A.; Ewa, I.O.B.; Umar, M.; Bezboruah, T.; Johri, M.; Akaho, E.H.K.

    2006-04-01

    The Chinese Miniature Neutron Source Reactor (MNSR) is a low power research reactor with maximum thermal neutron flux of 1 x 10 12 n.cm -2 .s -1 in one of its inner irradiation channels and thermal power of approximately 30kW. The MNSR is designed based on the Canadian SLOWPOKE reactor and is one of the smallest commercial research reactors presently available in the world. Its commercial versions currently in operation in China, Ghana, Iran, Nigeria, Pakistan and Syria, is considered as an excellent tool for Neutron Activation Analysis (NAA), training of Scientist, and Engineers in nuclear science and technology and small scale radioisotope production. The paper highlights the basic design and theory of the commercial MNSR, its safety features, applications and advantages over the Chinese Prototype. The experimental flux characteristics determined in this work and in similar studies by other authors reveal that the commercial MNSR has more flux stability, longer life span, higher negative temperature coefficient of reactivity and low under-moderation compared to its prototype in China. The result shows that the facility is safe for reactor physics experiments, teaching and training of students and also ideal for application of NAA for the determination of elemental composition of biological and environmental samples. It can also be a useful tool for geochemical and soil fertility mapping. (author)

  18. Cyber security for remote monitoring and control of small reactors

    Energy Technology Data Exchange (ETDEWEB)

    Trask, D., E-mail: dave.trask@cnl.ca [Atomic Energy of Canada Limited, Chalk River, ON (Canada); Jung, C. [Canadian Nuclear Safety Commission, Ottawa, ON (Canada); MacDonald, M., E-mail: marienna.macdonald@cnl.ca [Atomic Energy of Canada Limited, Chalk River, ON (Canada)

    2014-07-01

    There is growing international interest and activity in the development of small nuclear reactor technology with a number of vendors interested in building small reactors in Canada to serve remote locations. A common theme of small reactor designs proposed for remote Canadian locations is the concept of a centrally located main control centre operating several remotely located reactors via satellite communications. This theme was echoed at a recent IAEA conference where a recommendation was made to study I&C for remotely controlled small modular reactors, including satellite links and cyber security. This paper summarizes the results of an AECL-CNSC research project to analyze satellite communication technologies used for remote monitoring and control functions in order to provide cyber security regulatory considerations. The scope of this research included a basic survey of existing satellite communications technology and its use in industrial control applications, a brief history of satellite vulnerabilities and a broad review of over 50 standards, guidelines, and regulations from recognized institutions covering safety, cyber security, and industrial communication networks including wireless communications in general. This paper concludes that satellite communications should not be arbitrarily excluded by standards or regulation from use for the remote control and monitoring of small nuclear reactors. Instead, reliance should be placed on processes that are independent of any particular technology, such as reducing risks by applying control measures and demonstrating required reliability through good design practices and testing. Ultimately, it is compliance to well-developed standards that yields the evidence to conclude whether a particular application that uses satellite communications is safe and secure. (author)

  19. Cyber security for remote monitoring and control of small reactors

    International Nuclear Information System (INIS)

    Trask, D.; Jung, C.; MacDonald, M.

    2014-01-01

    There is growing international interest and activity in the development of small nuclear reactor technology with a number of vendors interested in building small reactors in Canada to serve remote locations. A common theme of small reactor designs proposed for remote Canadian locations is the concept of a centrally located main control centre operating several remotely located reactors via satellite communications. This theme was echoed at a recent IAEA conference where a recommendation was made to study I&C for remotely controlled small modular reactors, including satellite links and cyber security. This paper summarizes the results of an AECL-CNSC research project to analyze satellite communication technologies used for remote monitoring and control functions in order to provide cyber security regulatory considerations. The scope of this research included a basic survey of existing satellite communications technology and its use in industrial control applications, a brief history of satellite vulnerabilities and a broad review of over 50 standards, guidelines, and regulations from recognized institutions covering safety, cyber security, and industrial communication networks including wireless communications in general. This paper concludes that satellite communications should not be arbitrarily excluded by standards or regulation from use for the remote control and monitoring of small nuclear reactors. Instead, reliance should be placed on processes that are independent of any particular technology, such as reducing risks by applying control measures and demonstrating required reliability through good design practices and testing. Ultimately, it is compliance to well-developed standards that yields the evidence to conclude whether a particular application that uses satellite communications is safe and secure. (author)

  20. Physical activity of Canadian children and youth: accelerometer results from the 2007 to 2009 Canadian Health Measures Survey.

    Science.gov (United States)

    Colley, Rachel C; Garriguet, Didier; Janssen, Ian; Craig, Cora L; Clarke, Janine; Tremblay, Mark S

    2011-03-01

    Physical activity is an important determinant of health and fitness. This study provides contemporary estimates of the physical activity levels of Canadians aged 6 to 19 years. Data are from the 2007 to 2009 Canadian Health Measures Survey. The physical activity of a nationally representative sample was measured using accelerometers. Data are presented as time spent in sedentary, light, moderate and vigorous intensity movement, and in steps accumulated per day. An estimated 9% of boys and 4% of girls accumulate 60 minutes of moderate-to-vigorous physical activity on at least 6 days a week. Regardless of age group, boys are more active than girls. Canadian children and youth spend 8.6 hours per day-62% of their waking hours-in sedentary pursuits. Daily step counts average 12,100 for boys and 10,300 for girls. Based on objective and robust measures, physical activity levels of Canadian children and youth are low.

  1. 2009 Canadian Radiation Oncology Resident Survey

    International Nuclear Information System (INIS)

    Debenham, Brock; Banerjee, Robyn; Fairchild, Alysa; Dundas, George; Trotter, Theresa; Yee, Don

    2012-01-01

    Purpose: Statistics from the Canadian post-MD education registry show that numbers of Canadian radiation oncology (RO) trainees have risen from 62 in 1999 to approximately 150 per year between 2003 and 2009, contributing to the current perceived downturn in employment opportunities for radiation oncologists in Canada. When last surveyed in 2003, Canadian RO residents identified job availability as their main concern. Our objective was to survey current Canadian RO residents on their training and career plans. Methods and Materials: Trainees from the 13 Canadian residency programs using the national matching service were sought. Potential respondents were identified through individual program directors or chief resident and were e-mailed a secure link to an online survey. Descriptive statistics were used to report responses. Results: The eligible response rate was 53% (83/156). Similar to the 2003 survey, respondents generally expressed high satisfaction with their programs and specialty. The most frequently expressed perceived weakness in their training differed from 2003, with 46.5% of current respondents feeling unprepared to enter the job market. 72% plan on pursuing a postresidency fellowship. Most respondents intend to practice in Canada. Fewer than 20% of respondents believe that there is a strong demand for radiation oncologists in Canada. Conclusions: Respondents to the current survey expressed significant satisfaction with their career choice and training program. However, differences exist compared with the 2003 survey, including the current perceived lack of demand for radiation oncologists in Canada.

  2. 2009 Canadian Radiation Oncology Resident Survey

    Energy Technology Data Exchange (ETDEWEB)

    Debenham, Brock, E-mail: debenham@ualberta.net [Department of Radiation Oncology, Cross Cancer Institute, University of Alberta, Edmonton, Alberta (Canada); Banerjee, Robyn [Department of Radiation Oncology, Tom Baker Cancer Centre, University of Calgary, Calgary, Alberta (Canada); Fairchild, Alysa; Dundas, George [Department of Radiation Oncology, Cross Cancer Institute, University of Alberta, Edmonton, Alberta (Canada); Trotter, Theresa [Department of Radiation Oncology, Tom Baker Cancer Centre, University of Calgary, Calgary, Alberta (Canada); Yee, Don [Department of Radiation Oncology, Cross Cancer Institute, University of Alberta, Edmonton, Alberta (Canada)

    2012-03-15

    Purpose: Statistics from the Canadian post-MD education registry show that numbers of Canadian radiation oncology (RO) trainees have risen from 62 in 1999 to approximately 150 per year between 2003 and 2009, contributing to the current perceived downturn in employment opportunities for radiation oncologists in Canada. When last surveyed in 2003, Canadian RO residents identified job availability as their main concern. Our objective was to survey current Canadian RO residents on their training and career plans. Methods and Materials: Trainees from the 13 Canadian residency programs using the national matching service were sought. Potential respondents were identified through individual program directors or chief resident and were e-mailed a secure link to an online survey. Descriptive statistics were used to report responses. Results: The eligible response rate was 53% (83/156). Similar to the 2003 survey, respondents generally expressed high satisfaction with their programs and specialty. The most frequently expressed perceived weakness in their training differed from 2003, with 46.5% of current respondents feeling unprepared to enter the job market. 72% plan on pursuing a postresidency fellowship. Most respondents intend to practice in Canada. Fewer than 20% of respondents believe that there is a strong demand for radiation oncologists in Canada. Conclusions: Respondents to the current survey expressed significant satisfaction with their career choice and training program. However, differences exist compared with the 2003 survey, including the current perceived lack of demand for radiation oncologists in Canada.

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-07-01

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

  4. Tearing the Fabric of Canada: The Broadcast Media and Canadian Identity.

    Science.gov (United States)

    Weiss, Elaine F.

    This paper explores the perceived threat of American cultural "imperialism" in Canada, the effect of constant exposure to American broadcasting on the Canadian national identity, the role broadcasting plays in shaping Canadian identity, and the efforts by the Canadian government to "Canadianize" its broadcasting. A brief…

  5. Guide to Canadian Aerospace Related Industries,

    Science.gov (United States)

    1983-01-01

    Research and Development (US). Digital Radar - Contract with Fundacao Educacional Data Processing de Bauru, Brazil. Satellite/Radar - Contract with Canadian... especially suitable for cartography and thematic mapping. The principal applications to date have been to Vehicle Mobility mapping for the Canadian Forces...This latter capability is especially applied to the repair and rebuilding of sawmill and pulpmill machinery, and mining equipment. Ebco is

  6. Canadian ethane market overview

    Energy Technology Data Exchange (ETDEWEB)

    Stauft, T. [TransCanada Midstream, Calgary, AB (Canada)

    1999-07-01

    A review of the Canadian petrochemical industry, the supply and demand for ethane, and the longer-term outlook for ethane are presented. Recent projections of natural gas production by the National Energy Board are examined, along with the impact on ethane supply and demand by Alliance. It is suggested that reduced gas will flow past Cochrane and Empress, Alberta ethane and gas prices will increase relative to US Gulf Coast prices, and since expansion is based on ethane demand, the combined influence of these factors will be to delay the construction of new extraction capacity. Present capacity is considered sufficient to produce ethane for the current round of petrochemical plant expansions. Excess supplies will exist for the next few years, and Alberta ethane prices are likely to strengthen due to the tight supply/demand balance. The combination of the impact of the Alliance Pipeline project and the ultimate potential of the Western Canadian Sedimentary Basin are the major uncertainties. On the plus side, both the US and Canadian regulatory agencies appear to be moving away from regulating ethane, and towards allowing a competitive market to develop.

  7. Canadian ethane market overview

    International Nuclear Information System (INIS)

    Stauft, T.

    1999-01-01

    A review of the Canadian petrochemical industry, the supply and demand for ethane, and the longer-term outlook for ethane are presented. Recent projections of natural gas production by the National Energy Board are examined, along with the impact on ethane supply and demand by Alliance. It is suggested that reduced gas will flow past Cochrane and Empress, Alberta ethane and gas prices will increase relative to US Gulf Coast prices, and since expansion is based on ethane demand, the combined influence of these factors will be to delay the construction of new extraction capacity. Present capacity is considered sufficient to produce ethane for the current round of petrochemical plant expansions. Excess supplies will exist for the next few years, and Alberta ethane prices are likely to strengthen due to the tight supply/demand balance. The combination of the impact of the Alliance Pipeline project and the ultimate potential of the Western Canadian Sedimentary Basin are the major uncertainties. On the plus side, both the US and Canadian regulatory agencies appear to be moving away from regulating ethane, and towards allowing a competitive market to develop

  8. Cobalt-60 production in CANDU power reactors

    International Nuclear Information System (INIS)

    Malkoske, G.R.; Norton, J.L.; Slack, J.

    2002-01-01

    MDS Nordion has been supplying cobalt-60 sources to industry for industrial and medical purposes since 1946. These cobalt-60 sources are used in many market and product segments, but are primarily used to sterilize single-use medical products including; surgical kits, gloves, gowns, drapes, and cotton swabs. Other applications include sanitization of cosmetics, microbial reduction of pharmaceutical raw materials, and food irradiation. The technology for producing the cobalt-60 isotope was developed by MDS Nordion and Atomic Energy of Canada Limited (AECL) almost 55 years ago using research reactors at the AECL Chalk River Laboratories in Ontario, Canada. The first cobalt-60 source produced for medical applications was manufactured by MDS Nordion and used in cancer therapy. The benefits of cobalt-60 as applied to medical product manufacturing, were quickly realized and the demand for this radioisotope quickly grew. The same technology for producing cobalt-60 in research reactors was then designed and packaged such that it could be conveniently transferred to a utility/power reactor. In the early 1970's, in co-operation with Ontario Power Generation (formerly Ontario Hydro), bulk cobalt-60 production for industrial irradiation applications was initiated in the four Pickering A CANDU reactors. As the demand and acceptance of sterilization of medical products grew, MDS Nordion expanded its bulk supply by installing the proprietary Canadian technology for producing cobalt-60 in additional CANDU reactors. CANDU is unique among the power reactors of the world, being heavy water moderated and fuelled with natural uranium. They are also designed and supplied with stainless steel adjusters, the primary function of which is to shape the neutron flux to optimize reactor power and fuel bum-up, and to provide excess reactivity needed to overcome xenon-135 poisoning following a reduction of power. The reactor is designed to develop full power output with all of the adjuster

  9. Literature on the periphery of capitalism: Brazilian theory, Canadian culture Literature on the periphery of capitalism: Brazilian theory, Canadian culture

    Directory of Open Access Journals (Sweden)

    Imre Szeman

    2008-04-01

    Full Text Available In order to get past the blind spots that have developed in contemporary postcolonial theory, it is essential to seek out complementarities and solidarities in different national situations and in different modernities. This essay undertakes this task by exploring the homologous situations faced in Brazil and Canada in their respective attempts to create genuine national cultures. As in many postcolonial situations, the problem of creating an authentic culture is directly related to the sense that postcolonial culture is necessarily imitative and belated. In Misplaced Ideas, Roberto Schwarz exposes the hidden class character of the problem of cultural authenticity in Brazil, and in so doing, shows that the trauma of national-cultural identity merely reflects the contradictory structural position of Brazil’s postcolonial elite. Using Schwarz’s insights to explore the Canadian situation, the author shows that the same forces are at work in Canada. Though the crisis of a lack of an authentic Canadian culture has recently been surmounted as a result of the apparent international success of Canadian culture (especially literary fiction, that author cautions that this “success” story hides the class basis of Canadian culture in both its belated and isochronic phases (the latter being the moment when cultural belatedness is overcome. Making use of Brazilian theory to examine problems in Canadian culture allows us to see that Canadian modernity, long thought to be simply a derivative of the UK and USA, has similarities with Brazilian modernity that are essential to understanding the space and place Canada occupies in globalization. In order to get past the blind spots that have developed in contemporary postcolonial theory, it is essential to seek out complementarities and solidarities in different national situations and in different modernities. This essay undertakes this task by exploring the homologous situations faced in Brazil

  10. Responsible Canadian energy progress report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-07-01

    The Canadian Association of Petroleum Producers (CAPP) represents oil and gas companies throughout Canada; its members produce over 90% of Canada's natural gas and crude oil output. The aim of the Association is to improve the economics of the Canadian upstream petroleum sector in an environmentally and socially responsible way. The aim of this Responsible Canadian Energy report is to present the performance data of CAPP's members for the year 2009. Data, trends, and performance analyses are provided throughout the document. This analysis makes it possible to determine where progress has been made and where performance improvement is necessary. It also presents success stories and best practices so that other companies can learn from them how to improve their own performance. This paper provides useful information on the performance of the upstream petroleum industry in Canada and highlights where the focus should be for further improvement in its performance.

  11. Omega-3 Index of Canadian adults.

    Science.gov (United States)

    Langlois, Kellie; Ratnayake, Walisundera M N

    2015-11-01

    Cardioprotective properties have been associated with two fatty acids-eicosapentaenoic acid (EPA) and docosahexaenoic acid (DHA). The Omega-3 Index indicates the percentage of EPA+DHA in red blood cell fatty acids. Omega-3 Index levels of the Canadian population have not been directly measured. Data for respondents aged 20 to 79 from cycle 3 (2012/2013) of the Canadian Health Measures Survey were used to calculate means and the prevalence of Omega-3 Index coronary heart disease (CHD) risk cut-offs-high (4% or less), moderate (more than 4% to less than 8%), and low (8% or more)-by sociodemographic and lifestyle characteristics, including fish consumption and use of omega-3 supplements. Associations between the Omega-3 Index and CHD-related factors including biomarkers, risk factors, and previous CHD events, were examined in multivariate regression models. The mean Omega-3 Index level of Canadians aged 20 to 79 was 4.5%. Levels were higher for women, older adults, Asians and other non-white Canadians, omega-3 supplement users, and fish consumers; levels were lower for smokers and people who were obese. Fewer than 3% of adults had levels associated with low CHD risk; 43% had levels associated with high risk. No CHD-related factor was associated with the Omega-3 Index when control variables were taken into account. Omega-3 Index levels among Canadian adults were strongly related to age, race, supplement use, fish consumption, smoking status and obesity. Fewer than 3% of adults had Omega-3 Index levels associated with low risk for CHD.

  12. Dynamic simulation of a two-phase control absorber for neutron flux regulation in a nuclear reactor

    International Nuclear Information System (INIS)

    Plourde, J.A.; Lepp, R.M.

    1979-08-01

    A dynamic simulation of the two-phase control absorber being proposed for future Canadian nuclear power reactors has been developed at Chalk River Nuclear Laboratories. The model, implemented on a hybrid computer, was developed to study absorber dynamics at different circuit operating conditions and with different circuit configurations. The simulation is modular, with as much correspondence as possible between individual modules and the physical entities. The dynamics of several of the modules are described by partial differential equations, with space and time as independent variables. These are solved via the Continuous Space/Discrete Time technique. The simulation has been validated with data from the Two-Phase Absorber Experimental (TOPAX) Rig installed at the ZED-2 test reactor. (author)

  13. 48 CFR 249.7000 - Terminated contracts with Canadian Commercial Corporation.

    Science.gov (United States)

    2010-10-01

    ... Canadian Commercial Corporation. 249.7000 Section 249.7000 Federal Acquisition Regulations System DEFENSE... Termination Requirements 249.7000 Terminated contracts with Canadian Commercial Corporation. (a) Terminate contracts with the Canadian Commercial Corporation in accordance with— (1) The Letter of Agreement (LOA...

  14. Canadians assess the future of uranium

    International Nuclear Information System (INIS)

    Law, C.

    1980-01-01

    Some of the views expressed at a seminar held at Calgary on uranium marketing indicate the issues presently concerning Canadian uranium producers. There was apprehension that price rises might result from selling of the strategic stockpile by the Government. Long term growth prospects and the need for continuous exploration were discussed. Criticisms were also expressed of the Canadian safequard system and its tight export regulations. (U.K.)

  15. Exploring the Psychological Contract of the Canadian Forces

    National Research Council Canada - National Science Library

    Nordick, Glenn

    1999-01-01

    ... between the members of the Canadian Forces, the military leadership, and the Government of Canada. This paper uses the theory of psychological contracting to explore the culture of the Canadian Forces (CF...

  16. AUCC-IDRC Partnership Grant 2013-2016: Canadian University ...

    International Development Research Centre (IDRC) Digital Library (Canada)

    AUCC-IDRC Partnership Grant 2013-2016: Canadian University Student Mobility in North-South Partnerships ... This project will identify promising practices in Canadian universities' student ... Using digital tech to improve life for refugees.

  17. Purification and solidification of reactor wastes at a Canadian nuclear generating station

    International Nuclear Information System (INIS)

    Buckley, L.P.; Burt, D.A.

    1981-06-01

    Chalk River Nuclear Laboratories are developing methods to condition power reactor wastes and to immobilize their radionuclides. Evaporation alone and combined with bituminization has been an important part of the program. After testing at the laboratories a 0.5 m 2 wiped-film evaporator was sent to the Douglas Point Nuclear Generating Station (220 MWe) to demonstrate its suitability to handle typical reactor liquid wastes. Two specific tasks undertaken with the wiped-film evaporator were successfully completed. The first was purification of contaminated heavy water which had leaked from the moderator circuit. The heavy water is normally recovered, cleaned by filters and ion-exchange resin and then upgraded by electrolysis. Cleaning the heavy water with the wiped-film evaporator produced better quality water for upgrading than had been achieved by any previous method and at much lower operating cost. The second task was to concentrate and immobilize a decontamination waste. The waste was generated from the decontamination of pump bowls used in the primary heat transport circuit. The simultaneous addition of the liquid waste and bitumen emulsion to the wiped-film evaporator produced a solid containing 30 wt% waste solids in a bitumen matrix. The volume reduction achieved was 16:1 based on the volumes of initial liquid waste and the final product generated. The quantity sent to storage was 20 times less than had the waste been immobilized in a cement matrix. The successful demonstration has resulted in a proposal to install a wiped-film evaporator at the station to clean heavy water and immobilize decontamination wastes. (author)

  18. NAFTA Renegotiations: An opportunity for Canadian Dairy?

    Directory of Open Access Journals (Sweden)

    Eugene Beaulieu

    2018-03-01

    Full Text Available What are the implications of a renegotiated NAFTA for Canadian dairy producers? Many observers dread the prospect of even the slightest liberalization in the dairy sector. This paper takes a different perspective, arguing that opening Canada’s dairy sector would come with benefits not just for consumers, which is undeniable, but could also transform the industry and lead to a more productive dairy sector in Canada. Canadian dairy producers have been protected domestically through supply management and internationally through import-restricting border controls for over 40 years. This combination of domestic and foreign policies keeps Canadian dairy prices artificially high and allows producers to gain enormously from the system while hitting dairy consumers directly in the pocketbook. These policies are extremely costly for Canadian consumers and benefit the protected domestic dairy producers. Canadian international trade policies result in 200-percent tariffs on imports of many dairy products and almost 300-percent tariffs on over-quota imports of cheese. The OECD estimates that from 2010 to 2016, Canadian trade policy with respect to dairy and the “supply management system” annually transfers over US$2.9 billion from Canadian consumers and taxpayers to milk producers. This is extremely expensive for Canadian consumers and this transfer to Canadian dairy producers underscores why our trade partners have focused on the exorbitant tariffs that support this system. We argue that it is not only consumers that are hurt by the status quo, but that the industry itself can evolve and thrive from increased competition. According to standard trade theory, liberalizing trade in an industry like this leads the least productive producers to exit the industry as the most-productive producers increase market share and expand. These dynamics generate a more competitive and productive industry. We present evidence that these dynamics played out in Canada

  19. Purification and solidification of reactor wastes at a Canadian nuclear generating station

    International Nuclear Information System (INIS)

    Buckley, L.P.; Burt, D.A.

    1981-01-01

    The study aimed at development and demonstration of volume reduction and solidification of CANDU reactor wastes has been underway at Chalk River Nuclear Laboratories in the Province of Ontario, Canada. The study comprises membrane separation processes, evaporator appraisal and immobilization of concentrated wastes in bitumen. This paper discusses the development work with a wiped-film evaporator and the successful completion of demonstration tests at Douglas Point Nuclear Generating Station. Heavy water from the moderator system was purified and wastes arising from pump bowl decontamination were immobilized in bitumen with the wiped-film evaporator that was used in the development tests at Chalk River

  20. Canadian tax policy and renewable energy : are the benefits illusory : a comparison of Canadian and US approaches

    International Nuclear Information System (INIS)

    Chant, A.

    2008-01-01

    Tax policies for targeted activities such as wind energy need to be efficient and effective in promoting activities that may not otherwise take place. An efficient tax policy will not have unintended consequences that may lead to tax leakage or benefits outside the targeted activity, and will be consistent with other incentives promoting the target activity. This presentation discussed Canadian tax policies related to wind power and then compared them to tax policies in the United States directed at promoting wind energy development. Benefits and subsidies available to Canadian wind energy producers include the ecoEnergy program, the Canadian Renewable and Conservation Expense (CRCE) program; and Class 43.2 directed at high efficiency and renewable energy generation equipment. The Canadian valuation methodology considers capacity factors; capital costs; leverage; interest rates; corporate tax rates; and required equity. While the ecoEnergy program is valuable as it removes the tax risk for the recipient, the CRCE may be more valuable as it does not expire and is not subject to limitations on amounts deductible. Class 43.2 is valuable but constrained by the limitations of a project's income. The United States has a production tax credit (PTC) for wind developers based on a tax credit of $15 per MWh subject to adjustment, and is available for a 10-year period, is transferable to taxable investors, and has a current value of $20. It was concluded that while Canadian subsidies are the equivalent of $7.15, US subsidies are the equivalent of $17. tabs., figs

  1. The importance of nature to Canadians: survey highlights

    National Research Council Canada - National Science Library

    DuWors, E

    1999-01-01

    .... The 1996 Survey on the Importance of Nature to Canadians (the Nature Survey) also tells us that Canadians commit large amounts of their leisure time to activities that depend on natural areas and wildlife...

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

    International Nuclear Information System (INIS)

    Dupin, Ludovic; Lucas, Thierry

    2016-01-01

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

  3. Leading Lean: a Canadian healthcare leader's guide.

    Science.gov (United States)

    Fine, Benjamin A; Golden, Brian; Hannam, Rosemary; Morra, Dante

    2009-01-01

    Canadian healthcare organizations are increasingly asked to do more with less, and too often this has resulted in demands on staff to simply work harder and longer. Lean methodologies, originating from Japanese industrial organizations and most notably Toyota, offer an alternative - tried and tested approaches to working smarter. Lean, with its systematic approaches to reducing waste, has found its way to Canadian healthcare organizations with promising results. This article reports on a study of five Canadian healthcare providers that have recently implemented Lean. We offer stories of success but also identify potential obstacles and ways by which they may be surmounted to provide better value for our healthcare investments.

  4. Test facility for investigation of heat transfer of promising coolants for the nuclear power industry

    Science.gov (United States)

    Belyaev, I. A.; Sviridov, V. G.; Batenin, V. M.; Biryukov, D. A.; Nikitina, I. S.; Manchkha, S. P.; Pyatnitskaya, N. Yu.; Razuvanov, N. G.; Sviridov, E. V.

    2017-11-01

    The results are presented of experimental investigations into liquid metal heat transfer performed by the joint research group consisting of specialist in heat transfer and hydrodynamics from NIU MPEI and JIHT RAS. The program of experiments has been prepared considering the concept of development of the nuclear power industry in Russia. This concept calls for, in addition to extensive application of water-cooled, water-moderated (VVER-type) power reactors and BN-type sodium cooled fast reactors, development of the new generation of BREST-type reactors, fusion power reactors, and thermonuclear neutron sources. The basic coolants for these nuclear power installations will be heavy liquid metals, such as lead and lithium-lead alloy. The team of specialists from NRU MPEI and JIHT RAS commissioned a new RK-3 mercury MHD-test facility. The major components of this test facility are a unique electrical magnet constructed at Budker Nuclear Physics Institute and a pressurized liquid metal circuit. The test facility is designed for investigating upward and downward liquid metal flows in channels of various cross-sections in a transverse magnetic field. A probe procedure will be used for experimental investigation into heat transfer and hydrodynamics as well as for measuring temperature, velocity, and flow parameter fluctuations. It is generally adopted that liquid metals are the best coolants for the Tokamak reactors. However, alternative coolants should be sought for. As an alternative to liquid metal coolants, molten salts, such as fluorides of lithium and beryllium (so-called FLiBes) or fluorides of alkali metals (so-called FLiNaK) doped with uranium fluoride, can be used. That is why the team of specialists from NRU MPEI and JIHT RAS, in parallel with development of a mercury MHD test facility, is designing a test facility for simulating molten salt heat transfer and hydrodynamics. Since development of this test facility requires numerical predictions and verification

  5. Nuclear power and the Canadian public

    Energy Technology Data Exchange (ETDEWEB)

    Greer-Wootten, B; Mitson, L

    1976-06-01

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

  6. Beyond Infrastructure: Canadian and European Identities in Cyberspace

    OpenAIRE

    d’Haenens, Leen

    2017-01-01

    The Canadian discourse is neither the American way nor the European way, but an oppositional culture trapped midway between economy and history. This is to say that the Canadian mind is that of the in-between: a restless oscillation between the pragmatic will to live at all costs of the Americans and a searing lament for that which has been suppressed by the modem, technical order. The essence of the Canadian intellectual condition is this: it is our fate by virtue of historical circumstance ...

  7. Use of enriched uranium in Canada's power reactors

    International Nuclear Information System (INIS)

    Dormuth, K.W.; Jackson, D.P.

    2011-01-01

    Recent trends in Canadian nuclear power reactor design and proposed development of nuclear power in Canada have indicated the possibility that Canada will break with its tradition of natural uranium fuelled systems, designed for superior neutron economy and, hence, superior uranium utilization. For instance, the Darlington B new reactor project procurement process included three reactor designs, all employing enriched fuel, although a natural uranium reactor design was included at a late stage in the ensuing environmental assessment for the project as an alternative technology. An evaluation of the alternative designs should include an assessment of the environmental implications through the entire fuel cycle, which unfortunately is not required by the environmental assessment process. Examples of comparative environmental implications of the reactor designs throughout the fuel cycle indicate the importance of these considerations when making a design selection. As Canada does not have enrichment capability, a move toward the use of enriched fuel would mean that Canada would be exporting natural uranium and buying back enriched uranium with value added. From a waste management perspective, Canada would need to deal with mill, refinery, and conversion tailings, as well as with the used fuel from its own reactors, while the enrichment supplier would retain depleted uranium with some commercial value. On the basis of reasoned estimates based on publicly available information, it is expected that enrichment in Canada is likely to be more profitable than exporting natural uranium and buying back enriched uranium. Further, on the basis of environmental assessments for enrichment facilities in other countries, it is expected that an environmental assessment of a properly sited enrichment facility would result in approval. (author)

  8. Non-proliferation issues for the disposition of fissile materials using reactor alternatives

    International Nuclear Information System (INIS)

    Jaeger, C.D.; Duggan, R.A.; Tolk, K.M.

    1996-01-01

    The Department of Energy (DOE) is analyzing long-term storage on options for excess weapons-usable fissile materials. A number of the disposition alternatives are being considered which involve the use of reactors. The various reactor alternatives are all very similar and include front-end processes that could convert plutonium to a usable form for fuel fabrication, a MOX fuel fab facility, reactors to bum the MOX fuel and ultimate disposal of spent fuel in some geologic repository. They include existing, partially completed, advanced or evolutionary light water reactors and Canadian deuterium uranium (CANDU) reactors. In addition to the differences in the type of reactors, other variants on these alternatives are being evaluated to include the location and number of the reactors, the location of the mixed oxide (MOX) fabrication facility, the ownership of the facilities (private or government) and the colocation and/or separation of these facilities. All of these alternatives and their variants must be evaluated with respect to non-proliferation resistance. Both domestic and international safeguards support are being provided to DOE's Fissile Materials Disposition Program (FMDP) and includes such areas as physical protection, nuclear materials accountability and material containment and surveillance. This paper will focus on how the non-proliferation objective of reducing security risks and strengthening arms reduction will be accomplished and what some of the nonproliferation issues are for the reactor alternatives. Proliferation risk has been defined in terms of material form, physical environment, and the level of security and safeguards that is applied to the material. Metrics have been developed for each of these factors. The reactor alternatives will be evaluated with respect to these proliferation risk factors at each of the unit process locations in the alternative

  9. Non-proliferation issues for the disposition of fissile materials using reactor alternatives

    International Nuclear Information System (INIS)

    Jaeger, C.D.; Duggan, R.A.; Tolk, K.M.

    1996-01-01

    The Department of Energy (DOE) is analyzing long-term storage imposition options for excess weapons-usable fissile materials. A number of the disposition alternatives are being considered which involve the use of reactors. The various reactor alternatives are all very similar and include front-end processes that could convert plutonium to a usable form for fuel fabrication, a MOX fuel fab facility, reactors to burn the MOX fuel and ultimate disposal of spent fuel in some geologic repository. They include existing, partially completed, advanced or evolutionary light water reactors and Canadian deuterium uranium (CANDU) reactors. In addition to the differences in the type of reactors, other variants on these alternatives are being evaluated to include the location and number of the reactors, the location of the mixed oxide (MOX) fabrication facility, the ownership of the facilities (private or government) and the colocation and/or separation of these facilities. All of these alternatives and their variants must be evaluated with respect to non-proliferation resistance. Both domestic and international safeguards support are being provided to DOE's Fissile Materials Disposition Program (FMDP) and includes such areas as physical protection, nuclear materials accountability and material containment and surveillance. This paper will focus on how the non-proliferation objective of reducing security risks and strengthening arms reduction will be accomplished and what some of the non-proliferation issues are for the reactor alternatives. Proliferation risk has been defined in terms of material form, physical environment, and the level of security and safeguards that is applied to the material. Metrics have been developed for each of these factors. The reactor alternatives will be evaluated with respect to these proliferation risk factors at each of the unit process locations in the alternative

  10. Dynamic analysis of Korean nuclear fuel cycle with fast reactor systems

    International Nuclear Information System (INIS)

    Jeong, Chang Joon

    2004-12-01

    The Korean nuclear fuel cycle scenario was analyzed by the dynamic analysis method, including Pressurized Water Reactor (PWR), Canadian Deuterium Uranium (CANDU) and fast reactor systems. For the once-through fuel cycle model, the existing nuclear power plant construction plan was considered up to 2016, while the nuclear demand growth rate from the year 2016 was assumed to be 1%. After setting up the once-through fuel cycle model, the Korea Advanced Liquid Metal Reactor (KALIMER) scenario was modeled to investigate the fuel cycle parameters. For the analysis of the fast reactor fuel cycle, both KAILMER-150 and KALIMER-600 reactors were considered. In this analysis, the spent fuel inventory as well as the amount of plutonium, Minor Actinides (MA) and Fission Products (FP) of the recycling fuel cycle was estimated and compared to that of the once-through fuel cycle. Results of the once-through fuel cycle calculation showed that the demand grows up to 64 GWe and total amount of spent fuel would be ∼102 kt in 2100. If the KALIMER scenario is implemented, the total spent fuel inventory can be reduced by ∼80%. However it was found that the KALIMER scenario does not contribute to reduce the amount of MA and FP, which is important when designing a repository. For the further destruction of MA, an actinide burner can be considered in the future nuclear fuel cycle

  11. Dictionaries of Canadian English

    Directory of Open Access Journals (Sweden)

    John Considine

    2011-10-01

    Full Text Available

    Abstract: The lexicographical record of English in Canada began with wordlists of the late eighteenth, nineteenth, and early twentieth centuries. From the beginning of the twentieth century onwards, the general vocabulary of English in Canada has been represented in bilingual and monolingual dictionaries, often adapted from American or British dictionaries. In the 1950s, several important projects were initiated, resulting in the publication of general dictionaries of English in Canada, and of dictionaries of Canadianisms and of the vocabulary of particular regions of Can-ada. This article gives an overview of these dictionaries and of their reception, contextualizing them in the larger picture of the lexicography of Canada's other official language, French, and of a number of its non-official languages. It concludes by looking at the future of English-language lexicography in Canada, and by observing that although it has, at its best, reached a high degree of sophistication, there are still major opportunities waiting to be taken.

    Keywords: DICTIONARY, LEXICOGRAPHY, CANADIAN ENGLISH, CANADIANISMS, NATIONAL DICTIONARIES, CANADIAN FRENCH, CANADIAN FIRST NATIONS LAN-GUAGES, BILINGUAL DICTIONARIES, REGIONAL DICTIONARIES, UNFINISHED DICTIONARY PROJECTS

    Opsomming: Woordeboeke van Kanadese Engels. Die leksikografiese optekening van Engels in Kanada begin met woordelyste van die laat agtiende, neëntiende en vroeë twintigste eeue. Van die begin van die twintigste eeu af en verder, is die algemene woordeskat van Engels weergegee in tweetalige en eentalige woordeboeke, dikwels met wysiginge ontleen aan Ameri-kaanse en Britse woordeboeke. In die 1950's is verskeie belangrike projekte onderneem wat gelei het tot die publikasie van algemene woordeboeke van Engels in Kanada, en van woordeboeke van Kanadeïsmes en van die woordeskat van bepaalde streke van Kanada. Hierdie artikel gee 'n oorsig van dié woordeboeke, en van hul ontvangs, deur

  12. Calcium, Vitamin D, Iron, and Folate Messages in Three Canadian Magazines.

    Science.gov (United States)

    Cooper, Marcia; Zalot, Lindsay; Wadsworth, Laurie A

    2014-12-01

    Data from the Canadian Community Health Survey showed that calcium, vitamin D, iron, and folate are nutrients of concern for females 19-50 years of age. The study objectives were to assess the quantity, format, and accuracy of messages related to these nutrients in selected Canadian magazines and to examine their congruency with Canadian nutrition policies. Using content analysis methodology, messages were coded using a stratified sample of a constructed year for Canadian Living, Chatelaine, and Homemakers magazines (n = 33) from 2003-2008. Pilot research was conducted to assess inter-coder agreement and to develop the study coding sheet and codebook. The messages identified (n = 595) averaged 18 messages per magazine issue. The most messages were found for calcium, followed by folate, iron, and vitamin D, and the messages were found primarily in articles (46%) and advertisements (37%). Overall, most messages were coded as accurate (82%) and congruent with Canadian nutrition policies (90%). This research demonstrated that the majority of messages in 3 Canadian magazines between 2003 and 2008 were accurate and reflected Canadian nutrition policies. Because Canadian women continue to receive much nutrition information via print media, this research provides important insights for dietitians into media messaging.

  13. Strategies for the Canadian Smallsat Program

    Science.gov (United States)

    Symonds, M. D.

    1993-11-01

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

  14. Canadian seismic agreement

    International Nuclear Information System (INIS)

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

    1990-04-01

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

  15. Canadian Mathematical Congress

    CERN Document Server

    1977-01-01

    For two weeks in August, 1975 more than 140 mathematicians and other scientists gathered at the Universite de Sherbrooke. The occasion was the 15th Biennial Seminar of the Canadian Mathematical Congress, entitled Mathematics and the Life Sciences. Participants in this inter­ disciplinary gathering included researchers and graduate students in mathematics, seven different areas of biological science, physics, chemistry and medical science. Geographically, those present came from the United States and the United Kingdom as well as from academic departments and government agencies scattered across Canada. In choosing this particular interdisciplinary topic the programme committee had two chief objectives. These were to promote Canadian research in mathematical problems of the life sciences, and to encourage co-operation and exchanges between mathematical scientists" biologists and medical re­ searchers. To accomplish these objective the committee assembled a stim­ ulating programme of lectures and talks. Six ...

  16. How Canadians feel about nuclear energy

    International Nuclear Information System (INIS)

    Anon.

    1989-01-01

    A survey conducted by Decima Research in April 1989 showed that 50% of Canadians were somewhat or strongly in favour of nuclear energy, the percentage varying from 37% in British Columbia to 65% in Ontario. A majority (56%) questioned the nuclear industry's ability to handle its waste safely, but 45% believed that it was working hard to solve the problem. It was evident that an advertising campaign by the Canadian Nuclear Association had an effect

  17. South Asian Canadian experiences of depression

    OpenAIRE

    Grewal, Amarjit

    2010-01-01

    This narrative research study explored the socio-cultural context surrounding depression through semi-structured interviews with six South Asian Canadian participants, who self identified as having experienced depression. The study sought to expand on the knowledge of depression and South Asian Canadians by considering the roles of the family, the community, and the culture in the experiences of depression. Thematic analysis of the participant interviews resulted in five major themes: the exp...

  18. Lay-screeners and use of WHO growth standards increase case finding of hospitalized Malawian children with severe acute malnutrition.

    Science.gov (United States)

    LaCourse, Sylvia M; Chester, Frances M; Preidis, Geoffrey; McCrary, Leah M; Maliwichi, Madalitso; McCollum, Eric D; Hosseinipour, Mina C

    2015-02-01

    Strategies to effectively identify and refer children with severe acute malnutrition (SAM) to Nutritional Rehabilitation units (NRU) can reduce morbidity and mortality. From December 2011 to May 2012, we conducted a prospective study task-shifting inpatient malnutrition screening of Malawian children 6-60 months to lay-screeners and evaluated World Health Organization (WHO) criteria vs. the National Center for Health Statistics (NCHS) guidelines for SAM. Lay-screeners evaluated 3116 children, identifying 368 (11.8%) with SAM by WHO criteria, including 210 (6.7%) who met NCHS criteria initially missed by standard clinician NRU referrals. Overall case finding increased by 56.7%. Mid-upper arm circumference (MUAC) and bipedal edema captured 86% (181/210) NCHS/NRU-eligible children and 89% of those who died (17/19) meeting WHO criteria. Mortality of NCHS/NRU-eligible children was 10 times greater than those without SAM (odds ratio 10.5, 95% confidence interval 5.4-20.6). Ward-based lay-screeners and WHO guidelines identified high-risk children with SAM missed by standard NRU referral. MUAC and edema detected the majority of NRU-eligible children. © The Author [2014]. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

  19. Proceedings of the 29th annual conference of the Canadian Nuclear Association and 10th annual conference of the Canadian Nuclear Society. V. 1-3

    Energy Technology Data Exchange (ETDEWEB)

    Harvey, M; Fehrenbach, P J [eds.

    1990-12-31

    The symposium was designed to highlight how the technical information for nuclear energy came to Canada, the effect this information had in Canada in the fields of Physics, Chemistry, Medicine and Nuclear Power. Volume 1 is the combined proceedings of the Canadian Nuclear Association twenty-ninth annual conference and the Canadian Nuclear Society tenth annual conference. Volume 2 is the proceedings of the Canadian Nuclear Association twenty-ninth annual conference, and volume 3 is the proceedings of the Canadian Nuclear Society tenth annual conference.

  20. Proceedings of the 29th annual conference of the Canadian Nuclear Association and 10th annual conference of the Canadian Nuclear Society. V. 1-3

    International Nuclear Information System (INIS)

    Harvey, M.; Fehrenbach, P.J.

    1989-01-01

    The symposium was designed to highlight how the technical information for nuclear energy came to Canada, the effect this information had in Canada in the fields of Physics, Chemistry, Medicine and Nuclear Power. Volume 1 is the combined proceedings of the Canadian Nuclear Association twenty-ninth annual conference and the Canadian Nuclear Society tenth annual conference. Volume 2 is the proceedings of the Canadian Nuclear Association twenty-ninth annual conference, and volume 3 is the proceedings of the Canadian Nuclear Society tenth annual conference

  1. Canadian Nuclear Association

    International Nuclear Information System (INIS)

    Reid, John

    1992-01-01

    It is the view of the Canadian Nuclear Association that continuing creation of economic wealth is vital to sustainable development. A plentiful supply of cheap energy is essential. Nuclear energy provides the cleanest source of bulk energy generation essential to any path of sustainable development

  2. The representations of work-life balance in Canadian newspapers.

    Science.gov (United States)

    Reece, Katherine T; Davis, Jane A; Polatajko, Helene J

    2009-01-01

    Work-life balance has become a topic of increasing interest in the media as well as a concern among working Canadians. Since print media discourse can both reflect and shape societal values, cultural norms and ideals of workers in this country, it is important to understand this representation and its potential influence on the occupational engagement and life transitions of Canadian workers. Articles from four major Canadian newspapers published between 2003 and 2005 were used as data sources to examine the media construction of "work-life balance". Thematic analysis of 100 articles was performed using a modified affinity diagramming process. Representations within the Canadian print media conveyed both themes pertaining to the perceived experiences of imbalance and balance, as well as, a process of life balance. Obtaining balance was portrayed as an ongoing process during which an individual negotiates and sacrifices in an attempt to achieve his or her ideal level of balance. Environmental expectations and individual practices and perceptions were conveyed as reasons for the success or derailment of balance. The representations of work-life balance found in the Canadian print media were predominantly of professionals, focused on the demands of work and family, and did not appear to be a broad representation of the multiple realities that all Canadians face.

  3. The effect of irradiation and irradiation temperature on the fracture toughness of cold-worked Zr-2.5 wt percent Nb

    International Nuclear Information System (INIS)

    Simpson, L.A.; Ellis, R.B.; Stark, D.J.; Shillinglaw, A.J.

    1984-09-01

    The use of fracture mechanics methods and small specimens to assess the effect of metallurgical variables on fracture toughness and critical crack length in reactor pressure tubes is reviewed. Fracture toughness tests on specimens irradiated in the NRU research reactor at 260 degrees C are described and compared with results from a previous irradiation in the WR-1 research reactor at 350 degrees C. The J-resistance curve is used as the measure of fracture toughness, and is shown to be very sensitive to the metallurgical state. The lower irradiation temperature (260 degrees C), characteristic of the operating temperature range for power reactors, has a significant effect on fracture toughness. Circumferential hydrides also have an effect. Estimates of critical crack length are made using the J-resistance data, and are seen to slightly underestimate the actual critical crack length as determined in full-scale burst tests. This conservatism is not large enough to impose a significant penalty in design applications

  4. Financing Canadian international operations

    International Nuclear Information System (INIS)

    Beagle, G.

    1996-01-01

    A primer on financing international operations by Canadian corporations was provided. Factors affecting the availability to project finance (location, political risk), the various forms of financing (debt, equity, and combinations), the main sources of government backed financing to corporations (the International Finance Corporation) (IFC), the European Bank for Reconstruction and Development (EBRD), the Asian Development Bank (ADB), the Overseas Property Insurance Corporation (OPIC), government or agency guarantees, political risk coverage, the use of offshore financial centres, and the where, when and how these various organizations operate, were reviewed. Examples of all of the above, taken from the experiences of Canadian Occidental Petroleum of Calgary in the U.S., in South America, in the Middle and Far East, and in Kazakhstan, were used as illustrations. figs

  5. CFD simulation of flow and heat transfer in Canadian SCWR bundles

    International Nuclear Information System (INIS)

    Podila, K.; Rao, Y.F.

    2014-01-01

    Within the Generation-IV (Gen-IV) International Forum, Atomic Energy of Canada Limited (AECL) is leading the effort in developing a conceptual design for the Canadian supercritical water-cooled reactor (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 possible occurrence of heat transfer deterioration (HTD) in the supercritical bundle flows. In the current investigation, a 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 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 (23.5MPa). Ultimately, the goal of this study is to aid the development of a criterion for the onset of HTD in the proposed SCWR bundles, which is planned in the next phase of the project. (author)

  6. Canadian prediction equations of spirometric lung function for Caucasian adults 20 to 90 years of age: Results from the Canadian Obstructive Lung Disease (COLD) study and the Lung Health Canadian Environment (LHCE) study

    DEFF Research Database (Denmark)

    Tan, Wan C; Bourbeau, J; Hernandez, P

    2011-01-01

    BACKGROUND: Currently, no reference or normative values for spirometry based on a randomly selected Canadian population exist. OBJECTIVE: The aim of the present analysis was to construct spirometric reference values for Canadian adults 20 to 90 years of age by combining data collected from health...

  7. Canadian attitudes to nuclear power

    International Nuclear Information System (INIS)

    Davies, J.E.O.; Dobson, J.K.; Baril, R.G.

    1977-05-01

    A national assessment was made of public attitudes towards nuclear power, along with regional studies of the Maritimes and mid-western Canada and a study of Canadian policy-makers' views on nuclear energy. Public levels of knowledge about nuclear power are very low and there are marked regional differences. Opposition centers on questions of safety and is hard to mollify due to irrational fear and low institutional credibility. Canadians rate inflation as a higher priority problem than energy and see energy shortages as a future problem (within 5 years) and energy independence as a high priority policy. (E.C.B.)

  8. Issues in Canadian LLRW management

    International Nuclear Information System (INIS)

    Charlesworth, D.H.

    1988-01-01

    Some of the issues which are of concern in Canada are similar to those being discussed in the US because Canadian low-level radioactive waste (LLRW) production is similar in quantity and characteristics to that which will be handled by some state compacts. This paper gives a Canadian viewpoint of: the choice between interim storage and permanent disposal; the importance of considering inadvertent intrusion; the role of waste categorization and stability; and the concerns in assessing disposal performance. The discussion is related to Atomic Energy of Canada Limited's LLRW disposal program, and its approach to resolving these issues

  9. Canadian capital spending to slip 4.7% in 1993

    International Nuclear Information System (INIS)

    Anon.

    1993-01-01

    Total capital and exploration spending by the Canadian petroleum industry is estimated at $6.579 billion in 1993, a drop of 4.7% from estimated 1992 outlays. Last year Canadian capital spending of $6.9 billion represented a drop of 8.9% from 1991 outlays, according to an Oil and Gas Journal survey. All survey related spending estimates in this paper are in U.S. dollars. All individual company spending estimates are in Canadian dollars

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

    International Nuclear Information System (INIS)

    2012-01-01

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

  11. A nuclear reactor for district heating

    International Nuclear Information System (INIS)

    Bancroft, A.R.; Fenton, N.

    1989-07-01

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

  12. Canada's reactor exports

    International Nuclear Information System (INIS)

    Morrison, R.W.

    1981-01-01

    A brief sketch of the development of Canada's nuclear exports is presented and some of the factors which influence the ability to export reactors have been identified. The potential market for CANDUs is small and will develop slowly. The competition will be tough. There are few good prospects for immediate export orders in the next two or three years. Nonetheless there are reasonable opportunities for CANDU exports, especially in the mid-to-late 1980s. Such sales could be of great benefit to Canada and could do much to sustain the domestic nuclear industry. Apart from its excellent economic and technical performance, the main attraction of the CANDU seems to be the autonomy it confers on purchasing countries, the effectiveness with which the associated technology can be transferred, and the diversification it offers to countries which wish to reduce their dependence on the major industrial suppliers. Each sales opportunity is unique, and marketing strategy will have to be tailored to the customer's needs. Over the next decade, the factors susceptible to Canadian government action which are most likely to influence CANDU exports will be the political commitment of the government to those reactor exports, the performance established by the four 600 MWe CANDUs now nearing completion, the continuing successful operation of the nuclear program in Ontario, and the co-ordination of the different components of Canada's nuclear program (AECL, nuclear industry, utilities, and government) in putting forth a coherent marketing effort and following through with effective project management

  13. Whither Chinese involvement in the Canadian oil industry

    International Nuclear Information System (INIS)

    Schulz, B.

    2006-01-01

    Chinese oil companies have become increasingly focused on securing Canadian oil. However, most of the oil sands leases with good geological and economic prospects are owned by Canadian or Canadian subsidiary companies that have proven unwilling to sell future revenue and reserves bases to the Chinese. The opportunity for a trade of Canadian oil assets for improved Chinese market entry has been limited to Husky, which has existing Chinese connections, as well as to global companies such as Exxon, Shell and BP. In May 2005, the Chinese company Sinopec completed a $105 million deal with Calgary-based Synenco and formed a joint venture for oil sands production and an upgrader. Chinese interests are also involved in the Calgary-based Value Creation Group of Companies as well as in BA Energy. Enbridge has recently invested $25 million in the Heartland upgrader project, presumably with the aim of building pipelines to move new products to Asia. The most significant problem for Canadian oil sands companies and the greatest opportunity for Chinese companies involves the utilization of trained Chinese workers for the $100 billion in oil sands construction planned for the next decade. Significant immigration barriers exist for Chinese workers in Canada, and there is a legitimate concern that Chinese workers may want to stay in Canada. It was concluded that while there may be mutual opportunities for collaboration between Chinese and Canadian energy companies, the Alberta government currently faces challenges in work shortages, immigration, and pressures from unions and environmental lobbyists. 1 fig

  14. Whither Chinese involvement in the Canadian oil industry

    Energy Technology Data Exchange (ETDEWEB)

    Schulz, B. [Calgary Univ., AB (Canada). Haskayne School of Business

    2006-09-15

    Chinese oil companies have become increasingly focused on securing Canadian oil. However, most of the oil sands leases with good geological and economic prospects are owned by Canadian or Canadian subsidiary companies that have proven unwilling to sell future revenue and reserves bases to the Chinese. The opportunity for a trade of Canadian oil assets for improved Chinese market entry has been limited to Husky, which has existing Chinese connections, as well as to global companies such as Exxon, Shell and BP. In May 2005, the Chinese company Sinopec completed a $105 million deal with Calgary-based Synenco and formed a joint venture for oil sands production and an upgrader. Chinese interests are also involved in the Calgary-based Value Creation Group of Companies as well as in BA Energy. Enbridge has recently invested $25 million in the Heartland upgrader project, presumably with the aim of building pipelines to move new products to Asia. The most significant problem for Canadian oil sands companies and the greatest opportunity for Chinese companies involves the utilization of trained Chinese workers for the $100 billion in oil sands construction planned for the next decade. Significant immigration barriers exist for Chinese workers in Canada, and there is a legitimate concern that Chinese workers may want to stay in Canada. It was concluded that while there may be mutual opportunities for collaboration between Chinese and Canadian energy companies, the Alberta government currently faces challenges in work shortages, immigration, and pressures from unions and environmental lobbyists. 1 fig.

  15. The American 'severe fuel damage program'

    International Nuclear Information System (INIS)

    Sdouz, G.

    1982-03-01

    The TMI-2 accident has initiated a new phase of safety research. It is necessary to consider severe accidents with degraded or molten core. For NRC there was a need for an improved understanding of this reactor behaviour and the 'Severe Fuel Dage Program' was initiated. Planned are in-pile experiments in PBF, NRU and ESSOR and in addition separate effects tests and results from TMI-2. The analytical component of the program is the development of different versions of the code SCDAP for the detailed analysis during severe accident transients. (Author) [de

  16. A New In-core Production Method of Co-60 in CANDU Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Lyu, Jinqi; Kim, Woosong; Kim, Yonghee [KAIST, Daejeon (Korea, Republic of); Park, Younwon [BEES Inc, Daejeon (Korea, Republic of)

    2016-05-15

    This study introduces an innovative method for Co-60 production in the CANDU6 core. In this new scheme, the central fuel element is replaced by a Co-59 target and Co-60 is obtained after the fuel bundle is discharged. It has been shown that the new method can produce significantly higher amount of Co-60 than the conventional Co production method in CANDU6 reactors without compromising the fuel burnup by removing some (<50%) of the adjuster rods in the whole core. The coolant void reactivity is noticeably reduced when a Co-59 target is loaded into the central pin of the fuel bundle. Meanwhile, the peak power in a fuel bundle is just a little higher due to the central Co-59 target than in conventional CANDU6 fuel design. The basic technology for Co-60 producing was developed by MDS Nordion and Atomic Energy of Canada Limited (AECL) in 1946 and the same technology was adapted and applied in CANDU6 power reactors. The standard CANDU6 reactor has 21 adjuster rods which are fully inserted into the core during normal operation. The stainless steel adjuster rods are replaced with neutronically-equivalent Co-59 adjusters to produce Co-60. Nowadays, the roles of the adjuster rods are rather vague since nuclear reactors cannot be quickly restarted after a sudden reactor trip due to more stringent regulations. In some Canadian CANDU6 reactors, some or all the adjuster rods are removed from the core to maximize the uranium utilization.

  17. Analysis of severe core damage accident progression for the heavy water reactor

    International Nuclear Information System (INIS)

    Tong Lili; Yuan Kai; Yuan Jingtian; Cao Xuewu

    2010-01-01

    In this study, the severe accident progression analysis of generic Canadian deuterium uranium reactor 6 was preliminarily provided using an integrated severe accident analysis code. The selected accident sequences were multiple steam generator tube rupture and large break loss-of-coolant accidents because these led to severe core damage with an assumed unavailability for several critical safety systems. The progressions of severe accident included a set of failed safety systems normally operated at full power, and initiative events led to primary heat transport system inventory blow-down or boil off. The core heat-up and melting, steam generator response,fuel channel and calandria vessel failure were analyzed. The results showed that the progression of a severe core damage accident induced by steam generator tube rupture or large break loss-of-coolant accidents in a CANDU reactor was slow due to heat sinks in the calandria vessel and vault. (authors)

  18. Canadian Petroleum Products Inst. annual report, 1991

    International Nuclear Information System (INIS)

    1992-01-01

    The Canadian Petroleum Products Institute (CPPI) was created in 1989 as a nonprofit association of Canadian refiners and marketers of petroleum products. In 1991, the Atlantic Petroleum Association, the Quebec Petroleum Association, the Ontario Petroleum Association, the Canada West Petroleum Association, and the Petroleum Association for Conservation of the Canadian Environment (PACE) were integrated into the CPPI. The objective of the CPPI is to serve and represent the refining and marketing sectors of the petroleum industry with respect to environment, health and safety, and business issues. An industry overview is provided, as well as highlights of environmental achievements and challenges, and economics and operations for the year. Lists of CPPI publications, standing committees, and officers are also included. 9 figs

  19. Canadian small wind market

    International Nuclear Information System (INIS)

    Moorhouse, E.

    2010-01-01

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

  20. Concentrations and distributions of trace and minor elements in Chinese and Canadian coals and ashes

    International Nuclear Information System (INIS)

    Sun Jingxin; Jervis, R.E.

    1987-01-01

    A total of 35 trace and minor elements including some of environmental significance were determined in each of a selection of 15 Chinese and 6 Canadian thermal coals and their ashes by using the SLOWPOKE-2 nuclear reactor facility of the University of Toronto. The concentrations and distributions of these constituents among the coals and their combustion products (viz. ash and volatile matter) are presented. The detailed results showed wide variations in trace impurity concentrations (up to a factor of 100 and more) among the coals studied. Values for elemental enrichment factors (EF) relative to normal crustal abundances indicated that only As(EF=13), Br(5.7), I(16), S(230), Sb(11) and Se(320) were appreciably enriched in coal. (author) 14 refs.; 5 tabs

  1. Diet and Blood Pressure Control in Chinese Canadians: Cultural Considerations.

    Science.gov (United States)

    Zou, Ping

    2017-04-01

    Hypertension is highly prevalent in Chinese Canadians and diet has been identified as an important modifiable risk factor for hypertension. The current anti-hypertensive dietary recommendations in hypertension care guidelines lack examination of cultural factors, are not culturally sensitive to ethnic populations, and cannot be translated to Chinese Canadian populations without cultural considerations. Guided by Leininger's Sunrise Model of culture care theory, this paper investigates how cultural factors impact Chinese Canadians' dietary practice. It is proposed that English language proficiency, health literacy, traditional Chinese diet, migration and acculturation, and Traditional Chinese Medicine influence Chinese Canadians' dietary practices. A culturally congruent nursing intervention should be established and tailored according to related cultural factors to facilitate Chinese Canadians' blood pressure control. In addition, further study is needed to test the model adapted from Sunrise Model and understand its mechanism.

  2. Denials of Racism in Canadian English Language Textbooks

    Science.gov (United States)

    Gulliver, Trevor; Thurrell, Kristy

    2016-01-01

    This critical discourse analysis examines denials of racism in descriptions of Canada and Canadians from English language textbooks. Denials of racism often accompany racist and nationalist discourse, preempting observations of racism. The study finds that in representations of Canada or Canadians, English language texts minimize and downplay…

  3. Policy Analysis of the Canadian Oil Sands Experience

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2013-09-01

    For those who support U.S. oil sands development, the Canadian oil sands industry is often identified as a model the U.S. might emulate, yielding financial and energy security benefits. For opponents of domestic oil sands development, the Canadian oil sands experience illustrates the risks that opponents of development believe should deter domestic policymakers from incenting U.S. oil sands development. This report does not seek to evaluate the particular underpinnings of either side of this policy argument, but rather attempts to delve into the question of whether the Canadian experience has relevance as a foundational model for U.S. oil sands development. More specifically, this report seeks to assess whether and how the Canadian oil sands experience might be predictive or instructive in the context of fashioning a framework for a U.S. oil sands industry. In evaluating the implications of these underpinnings for a prospective U.S. oil sands industry, this report concentrates on prospective development of the oil sands deposits found in Utah.

  4. Forecasting Canadian nuclear power station construction costs

    International Nuclear Information System (INIS)

    Keng, C.W.K.

    1985-01-01

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

  5. Antioxidant health messages in Canadian women's magazines.

    Science.gov (United States)

    Steinberg, Alissa; Paisley, Judy; Bandayrel, Kristofer

    2011-01-01

    Recently, antioxidants have taken centre stage in media and advertising messages. While 80% of Canadians think they are well-informed about nutrition, many are confused about the health effects of specific nutrients. Forty-six percent of Canadians seek information from newspapers and books, and 67% of women rely on magazines. We examined the content and accuracy of antioxidant health messages in Canadian women's magazines. The top three Canadian magazines targeted at women readers were selected. A screening tool was developed, pilot tested, and used to identify eligible articles. A coding scheme was created to define variables, which were coded and analyzed. Seventy-seven percent of 36 magazine issues contained articles that mentioned antioxidants (n=56). Seventy-one percent (n=40) of articles reported positive health effects related to antioxidant consumption, and 36% and 40% of those articles framed those effects as definite and potential, respectively (p<0.01). The articles sampled conveyed messages about positive antioxidant health effects that are not supported by current evidence. Improved standards of health reporting are needed. Nutrition professionals may need to address this inaccuracy when they develop communications on antioxidants and health risk.

  6. Self-Perceived Eating Habits and Food Skills of Canadians.

    Science.gov (United States)

    Slater, Joyce J; Mudryj, Adriana N

    2016-01-01

    This study identified and described Canadians' self-perceived eating habits and food skills through the use of population-based data. Data from the Canadian Community Health Survey 2013 Rapid Response on Food Skills was used to examine the eating quality and patterns of Canadians. Data were collected from all provinces in January and February 2013. Respondent variables (sex, age, Aboriginal/immigrant status) were examined to assess differentiations between socio-demographic groupings (family structure, marital status, education, and income). Logistic regression was used to determine whether demographic variables increased the likelihood of certain responses. Forty-six percent of Canadians believe they have excellent/very good eating habits, with 51% categorizing their habits as good or fair. Similarly, the majority report having good food skills. Sex and age were significantly associated with food skills, with women rating their cooking skill proficiency higher than men (72% vs 55%), and older Canadians reporting higher food skill knowledge than their younger counterparts. Results indicate that while portions of the Canadian population have adequate food skills, others are lacking, which may negatively impact their diet. Findings from this study have implications for education and health promotion programs focusing on foods skills, particularly among vulnerable target groups. Copyright © 2016 Society for Nutrition Education and Behavior. Published by Elsevier Inc. All rights reserved.

  7. Thorium-Based Fuels Preliminary Lattice Cell Studies for Candu Reactors

    International Nuclear Information System (INIS)

    Margeanu, C.A.; Rizoiu, A.C.

    2009-01-01

    The choice of nuclear power as a major contributor to the future global energy needs must take into account acceptable risks of nuclear weapon proliferation, in addition to economic competitiveness, acceptable safety standards, and acceptable waste disposal options. Candu reactors offer a proven technology, safe and reliable reactor technology, with an interesting evolutionary potential for proliferation resistance, their versatility for various fuel cycles creating premises for a better utilization of global fuel resources. Candu reactors impressive degree of fuel cycle flexibility is a consequence of its channel design, excellent neutron economy, on-power refueling, and simple fuel bundle. These features facilitate the introduction and exploitation of various fuel cycles in Candu reactors in an evolutionary fashion. The main reasons for our interest in Thorium-based fuel cycles have been, globally, to extend the energy obtainable from natural Uranium and, locally, to provide a greater degree of energy self-reliance. Applying the once through Thorium (OTT) cycle in existing and advanced Candu reactors might be seen as an evaluative concept for the sustainable development both from the economic and waste management points of view. Two Candu fuel bundles project will be used for the proposed analysis, namely the Candu standard fuel bundle with 37 fuel elements and the CANFLEX fuel bundle with 43 fuel elements. Using the Canadian proposed scheme - loading mixed ThO 2 -SEU CANFLEX bundles in Candu 6 reactors - simulated at lattice cell level led to promising conclusions on operation at higher fuel burnups, reduction of the fissile content to the end of the cycle, minor actinide content reduction in the spent fuel, reduction of the spent fuel radiotoxicity, presence of radionuclides emitting strong gamma radiation for proliferation resistance benefit. The calculations were performed using the lattice codes WIMS and Dragon (together with the corresponding nuclear data

  8. Informal presentations by fuel fabricators and others [contributed by W. Ross, U.S. NRC

    International Nuclear Information System (INIS)

    Ross, W.

    1993-01-01

    This paper is representing the the attitude of only one of the major offices of NRC. This is Office of Nuclear Reactor Regulations. Under this office regulates all phases, safety and environmental and safeguard aspects, of about 70 power reactors and about 70 non-power reactors. Another portion of NRC is the Office of Nuclear Material Safety and Safeguards. Under this office is regulated the licensing activities of around 600 licensees of all types. Including all licenses of transportation, import-export, and such as this, as well as special nuclear materials not related to the use of reactors. So when we talk about regulating the use and the protection of special nuclear materials, we are talking about all types of special nuclear materials, not just the type that is used in a reactor. Consequently, when a review is being made, such as now being made at the direction of the Commission to see if relaxation of regulations can be given to reduced enrichment, it is not only under the auspices of the Office of nuclear reactor regulations, but also of this other office. Therefore, it has to be more or less a policy statement of the Commission. As far as current regulations are concerned, the NRC has one threshold: it's either above 20% enrichment or it's below 20% enrichment. We are going to look and see if the SNM license in this area as well as the SNM license in that area can be changed so that some intermediate regulations can be applied to the steps in between 90% and 20%. We also regulate on the basis of the kilogram formula quantity. Most of our most stringent regulations are based on te possession of kilograms of highly enriched uranium. If uranium enrichment is dropped to the 45-50% level, then the composition of the alloys would have to increase from 21 wt.% (NRU) or 28 wt.% (NRX) to somewhere in region of 40 to 50%, possibly more. We know that the Al-40 wt.% U alloy can be extruded to the required diameter. We also know that the alloy is more brittle than the

  9. Operative Landscape at Canadian Neurosurgery Residency Programs.

    Science.gov (United States)

    Tso, Michael K; Dakson, Ayoub; Ahmed, Syed Uzair; Bigder, Mark; Elliott, Cameron; Guha, Daipayan; Iorio-Morin, Christian; Kameda-Smith, Michelle; Lavergne, Pascal; Makarenko, Serge; Taccone, Michael S; Wang, Bill; Winkler-Schwartz, Alexander; Sankar, Tejas; Christie, Sean D

    2017-07-01

    Background Currently, the literature lacks reliable data regarding operative case volumes at Canadian neurosurgery residency programs. Our objective was to provide a snapshot of the operative landscape in Canadian neurosurgical training using the trainee-led Canadian Neurosurgery Research Collaborative. Anonymized administrative operative data were gathered from each neurosurgery residency program from January 1, 2014, to December 31, 2014. Procedures were broadly classified into cranial, spine, peripheral nerve, and miscellaneous procedures. A number of prespecified subspecialty procedures were recorded. We defined the resident case index as the ratio of the total number of operations to the total number of neurosurgery residents in that program. Resident number included both Canadian medical and international medical graduates, and included residents on the neurosurgery service, off-service, or on leave for research or other personal reasons. Overall, there was an average of 1845 operative cases per neurosurgery residency program. The mean numbers of cranial, spine, peripheral nerve, and miscellaneous procedures were 725, 466, 48, and 193, respectively. The nationwide mean resident case indices for cranial, spine, peripheral nerve, and total procedures were 90, 58, 5, and 196, respectively. There was some variation in the resident case indices for specific subspecialty procedures, with some training programs not performing carotid endarterectomy or endoscopic transsphenoidal procedures. This study presents the breadth of neurosurgical training within Canadian neurosurgery residency programs. These results may help inform the implementation of neurosurgery training as the Royal College of Physicians and Surgeons residency training transitions to a competence-by-design curriculum.

  10. Approaching French Language Literature in Canadian Studies

    OpenAIRE

    Mansfield, Charlie

    2005-01-01

    This book forms a self-study pack and teaching guide to help English speakers start using computers and the web to support their studies of French Canadian Literature, song, film and multimedia. Readers will need access to the Internet so that they can experience ‘Electronic Encounters’ with Canadian media in French and English. The approach is underpinned with ideas drawn from the analysis of travel writing.

  11. The Canadian nuclear industry - a national asset

    International Nuclear Information System (INIS)

    1985-03-01

    The economic importance of the Canadian nuclear industry in saving costs and creating jobs is expounded. The medical work of Atomic Energy of Canada Limited is also extolled. The Canadian Nuclear Association urges the federal government to continue to support the industry at home, and to continue to promote nuclear exports. This report was prepared in response to the Federal Finance Minister's 'A New Direction for Canada'

  12. Bridging Grant : Building Canadian Support for Global Health ...

    International Development Research Centre (IDRC) Digital Library (Canada)

    The Canadian Coalition for Global Health Research (CCGHR) is a not-for-profit organization dedicated to supporting research for global health equity. The CCGHR provides a networking and action platform for the Canadian global health research community and partners in low- and middle-income countries. This grant will ...

  13. African-Canadian Educators' Perspectives: Critical Factors for Success

    Science.gov (United States)

    Finlayson, Maureen

    2011-01-01

    This study investigates the perspectives of African-Canadian educators on critical factors for success in their educational careers. Interviews were conducted and life histories were constructed to analyze the complex and multifaceted nature of the experiences of ten African-Canadian educators. These data indicate that family and community…

  14. Canadians' perceptions of food, diet, and health--a national survey.

    Directory of Open Access Journals (Sweden)

    Alyssa Schermel

    Full Text Available Poor nutrition is harmful to one's health as it can lead to overweight and obesity and a number of chronic diseases. Understanding consumer perceptions toward diet and nutrition is critical to advancing nutrition-related population health interventions to address such issues. The purpose of this paper was to examine Canadians' perceived health and diet status, compared to their actual health status, and general concern about their own diet and beliefs about health. Also analyzed were some of the perceived barriers to eating "healthy" foods, with a focus on the availability of "healthy" processed foods.Two surveys were administered online to a group of Canadian panelists from all ten provinces during May 2010 to January 2011. Thirty thousand were invited; 6,665 completed the baseline survey and 5,494 completed the second survey. Panelists were selected to be nationally representative of the Canadian adult population by age, sex, province and education level, according to 2006 census data.Approximately one third of Canadians perceived their health or diet to be very good while very few Canadians perceived their health or diet to be very poor. While the majority of Canadians believed food and nutrition to be very important for improving one's health, fewer Canadians were concerned about their own diets. The majority of Canadians reported difficulty finding "healthy" processed foods (low in salt and sugar and with sufficient vitamins and minerals. Many also reported difficulty finding healthy foods that are affordable.Although consumers believe that nutrition is one of the most important factors for maintaining health, there are still a number of attitudinal and perceived environmental barriers to healthy eating.

  15. Transnational archives: the Canadian case

    Directory of Open Access Journals (Sweden)

    Julia Creet

    2011-05-01

    Full Text Available This paper is a brief overview of the concept of the transnational archive as a counterpoint to the idea that a national archive is necessarily a locus of a static idea of nation. The Canadian national archives is used as a case study of an archives that was transnational in its inception, and one that has continued to change in its mandate and materials as a response to patterns in migration and changing notions of multiculturalism as a Canadian federal policy. It introduces the most recent formation of the transnational archive and its denizens: the genealogical archive inhabited by family historians.

  16. Ready to regulate small reactors in Canada

    Energy Technology Data Exchange (ETDEWEB)

    Herstead, S.; Cook, S.; De Vos, M.; Howden, B.D. [Canadian Nuclear Safety Commission, Ottawa, Ontario (Canada)

    2012-07-01

    The success of any new build project is reliant upon all stakeholders - applicants, vendors, contractors and regulatory agencies - being ready to do their part. Over the past several years, the Canadian Nuclear Safety Commission (CNSC) has been working to ensure that it has the appropriate regulatory framework and internal processes in place for the timely and efficient licensing of all types of reactor, regardless of size. The CNSC's general nuclear safety objective requires that nuclear facilities be designed and operated in a manner that will protect the health, safety and security of persons and the environment from unreasonable risk, and to implement Canada's international commitments on the peaceful use of nuclear energy. For smaller facilities, this has traditionally allowed for the use of a graded approach to achieving safety.

  17. Management of patients with refractory angina: Canadian Cardiovascular Society/Canadian Pain Society joint guidelines.

    Science.gov (United States)

    McGillion, Michael; Arthur, Heather M; Cook, Allison; Carroll, Sandra L; Victor, J Charles; L'allier, Philippe L; Jolicoeur, E Marc; Svorkdal, Nelson; Niznick, Joel; Teoh, Kevin; Cosman, Tammy; Sessle, Barry; Watt-Watson, Judy; Clark, Alexander; Taenzer, Paul; Coyte, Peter; Malysh, Louise; Galte, Carol; Stone, James

    2012-01-01

    Refractory angina (RFA) is a debilitating disease characterized by cardiac pain resistant to conventional treatments for coronary artery disease including nitrates, calcium-channel and β-adrenoceptor blockade, vasculoprotective agents, percutaneous coronary interventions, and coronary artery bypass grafting. The mortality rate of patients living with RFA is not known but is thought to be in the range of approximately 3%. These individuals suffer severely impaired health-related quality of life with recurrent and sustained pain, poor general health status, psychological distress, impaired role functioning, and activity restriction. Effective care for RFA sufferers in Canada is critically underdeveloped. These guidelines are predicated upon a 2009 Canadian Cardiovascular Society (CCS) Position Statement which identified that underlying the problem of RFA management is the lack of a formalized, coordinated, interprofessional strategy between the cardiovascular and pain science/clinical communities. The guidelines are therefore a joint initiative of the CCS and the Canadian Pain Society (CPS) and make practice recommendations about treatment options for RFA that are based on the best available evidence. Concluding summary recommendations are also made, giving direction to future clinical practice and research on RFA management in Canada. Copyright © 2012 Canadian Cardiovascular Society. Published by Elsevier Inc. All rights reserved.

  18. Canadian natural gas winter 2005-06 outlook

    International Nuclear Information System (INIS)

    2005-11-01

    An outline of the Canadian natural gas commodity market was presented along with an outlook for Canadian natural gas supply and prices for the winter heating season of 2005-2006. In Canada, the level of natural gas production is much higher than domestic consumption. In 2004, Canadian natural gas production was 16.9 billion cubic feet per day (Bcf/d), while domestic consumption was much lower at 8.2 Bcf/d. The United States, whose natural gas consumption is higher than production, imported about 16 per cent of its natural gas supply from Canada and 3 per cent from other countries via liquefied natural gas imports. Canadian natural gas exports to the United States in 2004 was 8.7 Bcf/d, representing 51 per cent of Canada's production. In Canada, the most important natural gas commodity markets that determine natural gas commodity prices include the intra-Alberta market and the market at the Dawn, Ontario natural gas hub. A well connected pipeline infrastructure connects the natural gas commodity markets in Canada and the United States, allowing supply and demand fundamentals to be transferred across all markets. As such, the integrated natural gas markets in both countries influence the demand, supply and price of natural gas. Canadian natural gas production doubled from 7 to 16.6 Bcf/d between 1986 and 2001. However, in the past 3 years, production from western Canada has leveled out despite record high drilling activity. This can be attributed to declining conventional reserves and the need to find new natural gas in smaller and lower-quality reservoirs. The combination of steady demand growth with slow supply growth has resulted in high natural gas prices since the beginning of 2004. In particular, hurricane damage in August 2005 disrupted natural gas production in the Gulf of Mexico's offshore producing region, shutting-in nearly 9 Bcf/d at the height of damage. This paper summarized some of the key factors that influence natural gas market and prices, with

  19. Mental health concerns among Canadian physicians: results from the 2007-2008 Canadian Physician Health Study.

    Science.gov (United States)

    Compton, Michael T; Frank, Erica

    2011-01-01

    In light of prior reports on the prevalence of stress, depression, and other mental health problems among physicians in training and practice, we examined the mental health concerns of Canadian physicians using data from the 2007-2008 Canadian Physician Health Study. Among 3213 respondents, 5 variables (depressive symptoms during the past year, anhedonia in the past year, mental health concerns making it difficult to handle one's workload in the past month, problems with work-life balance, and poor awareness of resources for mental health problems) were examined in relation to sex, specialty, practice type (solo practice vs group or other practice settings), and practice setting (inner city, urban/suburban, or rural/small town/remote). Nearly one quarter of physicians reported a 2-week period of depressed mood, and depression was more common among female physicians and general practitioners/family physicians. Anhedonia was reported by one fifth; anesthesiologists were most likely to report anhedonia, followed by general practitioners/family physicians. More than one quarter reported mental health concerns making it difficult to handle their workload, which was more common among female physicians and general practitioners/family physicians and psychiatrists. Nearly one quarter reported poor work-life balance. Lack of familiarity with mental health resources was problematic, which was more prominent among female physicians and specialists outside of general practice/family medicine or psychiatry. Mental health concerns are relatively common among Canadian physicians. Training programs and programmatic/policy enhancements should redouble efforts to address depression and other mental health concerns among physicians for the benefit of the workforce and patients served by Canadian physicians. Copyright © 2011 Elsevier Inc. All rights reserved.

  20. CanWEA Pan-Canadian wind integration study paper

    Energy Technology Data Exchange (ETDEWEB)

    Tremblay, Martin [GL Garrad Hassan Canada Inc, Ottawa, ON (Canada); Gardner, Paul [GL Garrad Hassan and Partners, Glasgow (United Kingdom); Price, Doug; Le, Don [GL Garrad Hassan America, San Diego, CA (United States)

    2010-07-01

    GL Garrad Hassan has been contracted by CanWEA to undertake a scoping study for a future Pan-Canadian Wide-Scale Wind Integration Study. The scoping study provides the methodology and the rationale on which the actual wind integration study and request for proposals will be based on. Major system operators and owners of each Canadian Province along with experts involved in major US wind integration studies have been consulted and contributed to the decisional process. This paper provides a summary of the factors considered in the study and outline the actual methodology that was adopted for the future Pan-Canadian wind integration study. (orig.)

  1. Political Ideology and Economic Freedom across Canadian Provinces

    DEFF Research Database (Denmark)

    Bjørnskov, Christian; Potrafke, Niklas

    This paper examines how political ideology influenced economic freedom in the Canadian provinces. We analyze the dataset of economic freedom indicators compiled by the Fraser Institute in 10 Canadian provinces over the 1981-2005 period and introduce two different indices of political ideology......: government and parliament ideology. The results suggest that government ideology influenced labor market reforms: market-oriented governments promoted liberalization of the labor market. Parliamentary ideology did not influence economic liberalization at all. This finding (1) identifies differences between...... leftist and rightwing governments concerning the role of government in the economy and (2) indicates that ideological polarization concerns governments but less parliamentary fractions in the Canadian provinces. ...

  2. Risk factors in stock returns of Canadian oil and gas companies

    International Nuclear Information System (INIS)

    Sadorsky, P.

    2001-01-01

    This paper uses a multifactor market model to estimate the expected returns to Canadian oil and gas industry stock prices. Results are presented to show that exchange rates, crude oil prices and interest rates each have large and significant impacts on stock price returns in the Canadian oil and gas industry. In particular, an increase in the market or oil price factor increases the return to Canadian oil and gas stock prices while an increase in exchange rates or the term premium decreases the return to Canadian oil and gas stock prices. Furthermore, the oil and gas sector is less risky than the market and its moves are pro-cyclical. This suggests that Canadian oil and gas stocks may not be a good hedge against inflation

  3. Mining Legal and Business Resources on Canadian Banking

    Directory of Open Access Journals (Sweden)

    Rajiv Johal

    2013-06-01

    Full Text Available Given the distinct nature of the Canadian banking system, it is important for novice researchers to know which business and legal resources to consult in order to quickly find information that is particular to Canadian banking. However, there are very few articles or monographs in the library literature that describe how to find information sources exclusively on this subject from a Canadian perspective. Most available publications tend to specialize in sources for the US banking and Federal Reserve System with little attention to Canada. The paper begins with a brief introduction to Canadian banking. From there, the authors demonstrate where researchers can find primary sources such as legislation, regulations and case law. In addition, this article identifies and discusses the different types of information found on the websites of associations and government agencies such as the Office of the Superintendent of Financial Institutions, which supervises and regulates various areas of Canada’s financial system. Also discussed are secondary sources such as industry research and reports that are available from reliable websites and subscription-based resources. This paper also explores the best business and legal databases for researchers. Based on results from searching in periodical directories and indexes, the paper additionally provides a description of the most pertinent academic, trade and general publications relevant to the Canadian banking system and where their contents are indexed.

  4. Canadian nuclear risk experience

    International Nuclear Information System (INIS)

    Hamel, P.E.

    1982-05-01

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

  5. Job displacement effects of Canadian immigrants by country of origin and occupation.

    Science.gov (United States)

    Roy, A S

    1997-01-01

    "Some previous Canadian studies have shown that considering the labor market as a whole and also pooling all immigrants as a group, immigrants do not have any job displacement effects on the Canadian born. This study presents some new evidence. It disaggregates immigrants by country of origin and by occupation groups and provides an analysis of job displacement effects of immigrants on the native-born Canadians by these dimensions. The study finds that (1) U.S. immigrants and the Canadians are substitutes [for] competing groups in the labor market and the effect is quite significant; (2) Canadians and Europeans are competing groups in certain occupations, while they have complementary skills in others; and (3) immigrants from the Third World and the Canadians are slightly competing groups in certain occupations." excerpt

  6. A light-water detritiation project at Chalk River Laboratories

    International Nuclear Information System (INIS)

    Boniface, H.A.; Castillo, I.; Everatt, A.E.; Ryland, D.K.

    2010-01-01

    The NRU reactor rod bays is a large, open pool of water that receives hundreds of fuel rods annually, each carrying a small amount of residual tritiated heavy water. The tritium concentration of the rod bays water has risen over the years, to a level that is of concern to the operations staff and to the environment. The proposed long-term solution is to reduce the rod bays tritium concentration by direct detritiation of the water. The Combined Electrolytic-Catalytic Exchange (CECE) process is well suited to the light-water detritiation problem. With a tritium-protium separation factor greater than five, a CECE detritiation process can easily achieve the eight orders of magnitude separation required to split a tritiated light-water feed into an essentially tritium-free effluent stream and a tritiated heavy water product suitable for recycling through a heavy water upgrader. This paper describes a CECE light-water detritiation process specifically designed to reduce the tritium concentration in the NRU rod bays to an acceptable level. The conceptual design of a 600 Mg/a detritiation process has been developed and is now at the stage of project review and the beginning of detailed design. (author)

  7. Knowledge Translation and Patient Safety: The Canadian Adverse Events Study

    OpenAIRE

    Baker, G. Ross; Norton, Peter; Flintoft, Virginia

    2006-01-01

    The Canadian Adverse Events Study was the first national study of adverse events in Canadian hospitals. Learning from the controversy surrounding similar studies in other countries, the team engaged in extensive knowledge translation activities throughout the life of the project. Using meetings, Web-based communication and other tools, the team successfully prepared most Canadian stakeholders for the study’s release, allowing them to develop anticipatory patient safety initiatives. However, u...

  8. Statistics in action a Canadian outlook

    CERN Document Server

    Lawless, Jerald F

    2014-01-01

    Commissioned by the Statistical Society of Canada (SSC), Statistics in Action: A Canadian Outlook helps both general readers and users of statistics better appreciate the scope and importance of statistics. It presents the ways in which statistics is used while highlighting key contributions that Canadian statisticians are making to science, technology, business, government, and other areas. The book emphasizes the role and impact of computing in statistical modeling and analysis, including the issues involved with the huge amounts of data being generated by automated processes.The first two c

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

    International Nuclear Information System (INIS)

    Roots, F.

    1994-01-01

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

  10. Ties that Bind? American Influences on Canadian Education

    Science.gov (United States)

    Von Heyking, Amy

    2004-01-01

    Concerns about the "Americanization" of Canadian schools have been raised frequently throughout the history of Canadian education. Fear of American influence was behind the requirement in the 1816 Common School Act in Upper Canada that all teachers take an oath of allegiance to the Crown. It was the reason for the strong promotion of the…

  11. 2003 survey of Canadian radiation oncology residents

    International Nuclear Information System (INIS)

    Yee, Don; Fairchild, Alysa; Keyes, Mira; Butler, Jim; Dundas, George

    2005-01-01

    Purpose: Radiation oncology's popularity as a career in Canada has surged in the past 5 years. Consequently, resident numbers in Canadian radiation oncology residencies are at all-time highs. This study aimed to survey Canadian radiation oncology residents about their opinions of their specialty and training experiences. Methods and Materials: Residents of Canadian radiation oncology residencies that enroll trainees through the Canadian Resident Matching Service were identified from a national database. Residents were mailed an anonymous survey. Results: Eight of 101 (7.9%) potential respondents were foreign funded. Fifty-two of 101 (51.5%) residents responded. A strong record of graduating its residents was the most important factor residents considered when choosing programs. Satisfaction with their program was expressed by 92.3% of respondents, and 94.3% expressed satisfaction with their specialty. Respondents planning to practice in Canada totaled 80.8%, and 76.9% plan to have academic careers. Respondents identified job availability and receiving adequate teaching from preceptors during residency as their most important concerns. Conclusions: Though most respondents are satisfied with their programs and specialty, job availability and adequate teaching are concerns. In the future, limited time and resources and the continued popularity of radiation oncology as a career will magnify the challenge of training competent radiation oncologists in Canada

  12. Microplastics in aquatic environments: Implications for Canadian ecosystems.

    Science.gov (United States)

    Anderson, Julie C; Park, Bradley J; Palace, Vince P

    2016-11-01

    Microplastics have been increasingly detected and quantified in marine and freshwater environments, and there are growing concerns about potential effects in biota. A literature review was conducted to summarize the current state of knowledge of microplastics in Canadian aquatic environments; specifically, the sources, environmental fate, behaviour, abundance, and toxicological effects in aquatic organisms. While we found that research and publications on these topics have increased dramatically since 2010, relatively few studies have assessed the presence, fate, and effects of microplastics in Canadian water bodies. We suggest that efforts to determine aquatic receptors at greatest risk of detrimental effects due to microplastic exposure, and their associated contaminants, are particularly warranted. There is also a need to address the gaps identified, with a particular focus on the species and conditions found in Canadian aquatic systems. These gaps include characterization of the presence of microplastics in Canadian freshwater ecosystems, identifying key sources of microplastics to these systems, and evaluating the presence of microplastics in Arctic waters and biota. Crown Copyright © 2016. Published by Elsevier Ltd. All rights reserved.

  13. Canadian Neutron Source (CNS): a research reactor solution for medical isotopes and neutrons for science

    International Nuclear Information System (INIS)

    Chapman, D.

    2009-01-01

    This presentation describes a dual purpose research facility at the University of Saskatchewan for Canada for the production of medical isotopes and neutrons for scientific research. The proposed research reactor is intended to supply most of Canada's medical isotope requirements and provide a neutron source for Canada's research community. Scientific research would include materials research, biomedical research and imaging.

  14. CanWEA/CME wind industry supply chain opportunities for Canadian manufacturers

    International Nuclear Information System (INIS)

    2010-04-01

    Between 1999 and 2009, worldwide wind energy production capacity has increased at an average annual rate of 25 percent. One of the most important opportunities for Canada's industrial supply base involves providing products and services to the North American wind energy industry. This report discussed global wind energy development, with particular reference to North American wind energy development; United States wind energy development; and Canadian wind energy development. The energy price benefit of wind was also discussed. Other topics that were discussed included the aging infrastructure, market growth and greenhouse gas reduction commitments; provincial wind development opportunities; and wind development opportunities for the Canadian supply chain. The report concluded with some recommended actions to encourage a globally competitive Canadian wind supply industry. Recommendations were provided under the headings of communication; partnership facilitation; capability development; and policy to develop a sustainable Canadian supply chain. It was concluded that a priority should be placed on accelerating the development of a Canadian supply chain for the wind power industry to ensure maximum economic benefit for Canadian business. 2 tabs., 1 fig.

  15. Development of excavation technologies at the Canadian underground research laboratory

    International Nuclear Information System (INIS)

    Kuzyk, Gregory W.; Martino, Jason B.

    2008-01-01

    Several countries, Canada being among them, are developing concepts for disposal of used fuel from power generating nuclear reactors. As in underground mining operations, the disposal facilities will require excavation of many kilometres of shafts and tunnels through the host rock mass. The need to maintain the stability of excavations and safety of workers will be of paramount importance. Also, excavations required for many radioactive waste repositories will ultimately need to be backfilled and sealed to maintain stability and minimize any potential for migration of radionuclides, should they escape their disposal containers. The method used to excavate the tunnels and shafts, and the rock damage that occurs due to excavation, will greatly affect the performance characteristics of repository sealing systems. The underground rock mechanics and geotechnical engineering work performed at the Canadian Underground Research Laboratory (URL) has led to the development of excavation technologies that reduce rock damage in subsurface excavations. This paper discusses the excavation methods used to construct the URL and their application in planning for the construction of similar underground laboratories and repositories for radioactive wastes. (author)

  16. Where in the World are Canadian Oil and Gas Companies? 2011

    Directory of Open Access Journals (Sweden)

    Niloo Hojjati

    2017-06-01

    Full Text Available Canada is well recognized for its prominence as an oil and gas jurisdiction in regard to its resources within its own borders. However, there is little available analysis and information regarding the presence of Canadian companies in the international arena. Begun in 2011 as an internal research tool for the development of the Extractive Resource Governance Program, this project seeks to answer the vital question: Where in the world are Canadian oil and gas companies? To answer this question, firm-level data from publicly traded Canadian companies are collected and analyzed, culminating in the development of an online tool for public use. This map allows interested users to geographically locate jurisdictions around the world where publicly traded Canadian oil and gas (hereafter O&G companies have activities, over time. The map is available at http://www.policyschool.ca/ research-teaching/teaching-training/extractive-resource-governance/ergp-map/. This project, hereafter referred to as the WIW project, provides a measure that quantifies Canadian oil and gas activity around the world and identifies key jurisdictions that are of particular interest to Canadian O&G companies. The data collected holds value for various stakeholders such as governments, regulatory bodies, academia, civil society, and industry across the extractive resource spectrum. Prior to further discussion regarding the 2011 annual data results, it is valuable to provide a brief overview of the methodology used in the collection of data for this research project. The WIW project examines the global activities of Canadian O&G companies in 218 countries spanning seven international regions of analysis.1 The aim of the WIW project is to examine the international presence of Canadian companies in foreign countries. As such, it is important to note that this project does not provide information related to the activities of Canadian companies within Canada’s border, such as the

  17. Meeting Canadian Forces Expansion Goals through Retention

    Science.gov (United States)

    2010-05-01

    poverty, etc. The recruiting slogan has resonated well with the Canadian Public thanks to an effective advertising campaign. 2 Canadian Department of...for Joint Task Force Two selection is most probably trying to realize his full potential; an armour officer who enrolls in a voluntary continuing...meet with a recruiting staff member to start the process. This has opened the CF entry door much wider to those living in remote locations ; they

  18. Hydrogeology and water quality of the North Canadian River alluvium, Concho Reserve, Canadian County, Oklahoma

    Science.gov (United States)

    Becker, C.J.

    1998-01-01

    A growing user population within the Concho Reserve in Canadian County, Oklahoma, has increased the need for drinking water. The North Canadian River alluvium is a reliable source of ground water for agriculture, industry, and cities in Canadian County and is the only ground-water source capable of meeting large demands. This study was undertaken to collect and analyze data to describe the hydrogeology and ground-water quality of the North Canadian River alluvium within the Concho Reserve. The alluvium forms a band about 2 miles long and 0.5 mile wide along the southern edge of the Concho Reserve. Thickness of the alluvium ranges from 19 to 75 feet thick and averages about 45 feet in the study area. Well cuttings and natural gamma-ray logs indicate the alluvium consists of interfingering lenses of clay, silt, and sand. The increase of coarse-grained sand and the decrease of clay and silt with depth suggests that the water-bearing properties of the aquifer within the study area improve with depth. A clay layer in the upper part of the aquifer may be partially responsible for surface water ponding in low areas after above normal precipitation and may delay the infiltration of potentially contaminated water from land surface. Specific conductance measurements indicate the ground-water quality improves in a northern direction towards the terrace. Water-quality properties, bacteria counts, major ion and nutrient concentrations, trace-element and radionuclide concentrations, and organic compound concentrations were measured in one ground-water sample at the southern edge of the Concho Reserve and comply with the primary drinking-water standards. Measured concentrations of iron, manganese, sulfate, and total dissolved solids exceed the secondary maximum contaminant levels set for drinking water. The ground water is a calcium sulfate bicarbonate type and is considered very hard, with a hardness of 570 milligrams per liter as calcium carbonate.

  19. Providing cleaner air to Canadians

    International Nuclear Information System (INIS)

    2001-02-01

    This booklet is designed to explain salient aspects of the Ozone Annex, negotiated and signed recently by Canada and the United States, in a joint effort to improve air quality in North America. By significantly reducing the transboundary flows of air pollutants that cause smog, the Ozone Annex will benefit some 16 million people in central and eastern Canada and provide an example for a future round of negotiations to address concerns of the millions of Canadians and Americans who live in the border area between British Columbia and Washington State. The brochure provide summaries of the Canadian and American commitments, focusing on transportation, monitoring and reporting. The Ozone Annex complements other air quality initiatives by the Government of Canada enacted under the Environmental Protection Act, 1999. These measures include regulations to reduce sulphur content to 30 parts per million by Jan 1, 2005; proposing to restrict toxic particulate matter (PM) to less than 10 microns; establishing daily smog forecasts in the Maritimes and committing to a national program built upon existing smog advisories and forecasts in Quebec, Ontario and British Columbia; and investing in more clean air research through the newly created Canadian Foundation for Climate and Atmospheric Sciences

  20. Mercury in Canadian crude oil

    International Nuclear Information System (INIS)

    Hollebone, B.P.

    2005-01-01

    Estimates for average mercury concentrations in crude oil range widely from 10 ng/g of oil to 3,500 ng/g of oil. With such a broad range of estimates, it is difficult to determine the contributions of the petroleum sector to the total budget of mercury emissions. In response to concerns that the combustion of petroleum products may be a major source of air-borne mercury pollution, Environment Canada and the Canadian Petroleum Products Institute has undertaken a survey of the average total mercury concentration in crude oil processed in Canadian refineries. In order to calculate the potential upper limit of total mercury in all refined products, samples of more than 30 different types of crude oil collected from refineries were measured for their concentration of mercury as it enters into a refinery before processing. High temperature combustion, cold vapour atomic absorption and cold vapour atomic fluorescence were the techniques used to quantify mercury in the samples. The results of the study provide information on the total mass of mercury present in crude oil processed in Canada each year. Results can be used to determine the impact of vehicle exhaust emissions to the overall Canadian mercury emission budget. 17 refs., 2 tabs., 2 figs

  1. Ecknomic benefits arising from the Canadian nuclear industry

    International Nuclear Information System (INIS)

    1982-03-01

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

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

    International Nuclear Information System (INIS)

    2007-01-01

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

  3. Canadian Cardiovascular Society/Canadian Anesthesiologists' Society/Canadian Heart Rhythm Society joint position statement on the perioperative management of patients with implanted pacemakers, defibrillators, and neurostimulating devices.

    Science.gov (United States)

    Healey, Jeff S; Merchant, Richard; Simpson, Chris; Tang, Timothy; Beardsall, Marianne; Tung, Stanley; Fraser, Jennifer A; Long, Laurene; van Vlymen, Janet M; Manninen, Pirjo; Ralley, Fiona; Venkatraghavan, Lashmi; Yee, Raymond; Prasloski, Bruce; Sanatani, Shubhayan; Philippon, François

    2012-01-01

    There are more than 200,000 Canadians living with permanent pacemakers or implantable defibrillators, many of whom will require surgery or invasive procedures each year. They face potential hazards when undergoing surgery; however, with appropriate planning and education of operating room personnel, adverse device-related outcomes should be rare. This joint position statement from the Canadian Cardiovascular Society (CCS) and the Canadian Anesthesiologists' Society (CAS) has been developed as an accessible reference for physicians and surgeons, providing an overview of the key issues for the preoperative, intraoperative, and postoperative care of these patients. The document summarizes the limited published literature in this field, but for most issues, relies heavily on the experience of the cardiologists and anesthesiologists who contributed to this work. This position statement outlines how to obtain information about an individual's type of pacemaker or implantable defibrillator and its programming. It also stresses the importance of determining if a patient is highly pacemaker-dependent and proposes a simple approach for nonelective evaluation of dependency. Although the document provides a comprehensive list of the intraoperative issues facing these patients, there is a focus on electromagnetic interference resulting from electrocautery and practical guidance is given regarding the characteristics of surgery, electrocautery, pacemakers, and defibrillators which are most likely to lead to interference. The document stresses the importance of preoperative consultation and planning to minimize complications. It reviews the relative merits of intraoperative magnet use vs reprogramming of devices and gives examples of situations where one or the other approach is preferable. Copyright © 2012 Canadian Cardiovascular Society. Published by Elsevier Inc. All rights reserved.

  4. The impact of climate change on Canadian peatlands

    International Nuclear Information System (INIS)

    Tarnocai, C.

    2009-01-01

    This paper discussed the sensitivity of Canadian peatlands to climate change, with particular emphasis on the carbon dynamics, water regime changes and the contribution of peatlands to atmospheric greenhouse gases. Peatlands cover 12 per cent of the Canadian landscape, with most occurring in the boreal and subarctic regions. In total, the peatlands contain nearly 147 Gt of soil organic carbon, or about 56 per cent of the organic carbon stored in all Canadian soils. A peatland sensitivity model that was used to determine the effect of climate warming on peatlands revealed that about 60 per cent of the boreal and subarctic regions and 56 per cent of the organic carbon mass in all Canadian peatlands will be severely to extremely severely affected by climate change, and at an accelerated rate than ever before. Climate change predictions suggest that the greatest effects of climate warming on Canadian peatlands will occur in areas with perennially frozen peat. The major concern in these areas is that the melting of the frozen peat will result in waterlogged conditions. In contrast, drying of non-permafrost peatlands will result in a higher frequency and extent of wildfires. As a result of these changes, large amounts of carbon in the forms of carbon dioxide (CO 2 ) and methane (CH 4 ) will be released into the atmosphere from these peatlands, which will further accelerate climate warming. 43 refs., 2 tabs., 7 figs.

  5. Short-term Canadian natural gas deliverability 2007-2009

    International Nuclear Information System (INIS)

    2007-01-01

    This report examined factors that may influence gas supply in the near future, and presented an outlook for natural gas deliverability up to the year 2009. Deliverability was projected under the following 3 scenarios to reflect varying levels of drilling investment that may occur: (1) a reference case; (2) a high case; and (3) a low case. Canadian natural gas has provided approximately 25 per cent of North America's natural gas production over the past few years. Marketable gas sales in 2006 were approximately $42 billion. Approximately 98 per cent of the total Canadian volume of natural gas is produced in the western Canadian sedimentary basin (WCSB). Results of the scenario analyses showed that deliverability decreased in all 3 projected scenarios. By 2009, Canadian natural gas deliverability was projected to decrease to between 410 and 449 million m 3 /d. The report also noted that the annual decline rate of the average natural gas well is 55 per cent. Producers have been maintaining deliverability by increasing the number of wells drilled annually. Gas producers are now targeting the western side of the basin, and are drilling deeper wells in order to access richer deposits of gas. Coalbed methane (CBM) production is also expected to increase over the next few years. It was concluded that Canadian deliverability will continue to play an important role in North American gas supplies. 6 tabs., 6 figs

  6. Canadian contribution to the European Union Home Team program for ITER

    International Nuclear Information System (INIS)

    Murdoch, D.K.; Blevins, J.D.; Gierszewski, P.; Matsugu, R.

    1998-01-01

    Canadian participation in R and D and design tasks for the ITER project is predominantly in the fuel cycle, remote handling and safety fields. These tasks are carried out in Canada by Ontario Hydro, research institutes, industry and universities. In addition, Canada provides the services of a number of specialist engineers and scientists in key positions at the three ITER work sites and in the European Home Team. The Canadian contribution, which is coordinated by the Canadian Fusion Fuels Technology Project (CFFTP), forms an integral part of the European Union Home Team program. The key components of the Canadian contribution are described. (author)

  7. The Dividend and Share Repurchase Policies of Canadian Firms

    NARCIS (Netherlands)

    A. de Jong (Abe); R. van Dijk (Ronald); C.H. Veld

    2001-01-01

    textabstractWe empirically investigate dividend and share repurchase policies of Canadian firms. We have sent a questionnaire to the 500 largest non-financial Canadian companies listed on the Toronto Stock Exchange, of which 191 usable responses were returned. These data are used to measure

  8. Computers behind bars : Information technology in Canadian prison libraries

    DEFF Research Database (Denmark)

    Prange, Laurie

    of information can have upon Canadian prison libraries. Gathered information is compared with the results of Canadian policy regarding the provision of information to inmates. The analysis of the collected facts can provide insight to help prison librarians deal with the increasing popularity of electronic...

  9. Knowledge synthesis and the Canadian Institutes of Health Research

    Directory of Open Access Journals (Sweden)

    Graham Ian D

    2012-02-01

    Full Text Available Abstract The Canadian Institutes of Health Research (CIHR is Canada's premier health-research funding agency. We fund nearly 14,000 researchers and trainees in four theme areas: biomedical, clinical, health services, and population and public-health research. Our mandate is 'to excel according to international standards of scientific excellence, in the creation of new knowledge and its translation into improved health for Canadians, more effective health services and products and a strengthened Canadian health care system'. Knowledge synthesis is a key element of the knowledge-translation objectives of CIHR, as outlined in our definition of knowledge-translation.

  10. Canadian crude oil production and supply forecast 2006-2020

    International Nuclear Information System (INIS)

    2006-05-01

    In order to enable members to plan for pipeline capacity requirements for transporting Canadian crude oil to markets, the Canadian Association of Petroleum Producers (CAPP) 2006-2020 crude oil production and supply forecast provides a long-range outlook of Canadian crude oil production. It provides a forecast of supply and demand for both western and eastern Canada. Because offshore eastern oil production does not rely on pipeline access to reach markets, the analysis primarily focuses on western Canadian production and supply. Over the next fifteen years, Alberta's oil sands provides the main source of growth in the western Canadian production forecast. A survey of CAPP members encompassing all oil sands projects was conducted. Survey responses reflect both planned and envisioned projects over a fifteen year period, although some of the envisioned projects have been risk adjusted by modifying the potential completion schedules for projects which are deemed more uncertain. Detailed tables are provided on forecast data. Three sets of tables are included to show production, two supply scenarios and a high level assessment of the need for incremental pipeline capacity. The report also discusses delays and risk factors that could slow the pace of oil sands development and the corresponding increase in production being forecast in the base case. 16 tabs

  11. The turning black tide : energy prices and the Canadian dollar

    International Nuclear Information System (INIS)

    Issa, R.; Lafrance, R.; Murray, J.

    2008-01-01

    This paper examined the relationship between energy prices and the Canadian-United States dollar real exchange rate. The researchers evaluated the standard Amano-van Norden (AvN) equation formulated to demonstrate that higher real energy prices lead to a depreciation of the Canadian dollar. Major developments in the Canadian energy market were discussed, as well as policy initiatives designed to address Canada's trade balance by increasing energy exports. The study examined the AvN equation using Monte Carlo experiments to determine the parameter stability of the equation. Results indicated that the co-integrating relationship in the standard AvN equation were no longer supported. Structural break tests were used to demonstrate that major changes in Canada's energy policies and cross-border trade and investment strategies have led to an increase in the Canadian dollar's value when energy prices are high. The study presented a new equation designed to account for Canadian dollar's appreciation since 2003. It was concluded that net energy exports in the 1990s outweighed the negatives associated with Canada's energy-intensive production processes. 39 refs., 6 tabs., 10 figs

  12. Financial outlook for the Canadian gas industry

    International Nuclear Information System (INIS)

    Friedenberg, B.

    1994-01-01

    The financial outlook for the Canadian natural gas industry is discussed in terms of the price of Canadian gas and its production and transportation costs. Demand growth for natural gas is fairly steady, reflecting economic growth and technological advances. Supply growth is more volatile, overshooting demand growth in an up market and undershooting in a down market. In the past year and a half, gas prices have improved as the supply deliverability surplus has eroded. It is predicted that supply will again exceed demand and prices will decline, the length of this price cycle being a few years. Production costs for western Canadian gas had been declining during the mid-1980s to 1991, and current replacement costs average ca $1.87/GJ. It is doubtful that fieldgate costs will increase to overtake fieldgate market prices and the Canadian gas industry will remain in a healthy state. The availability and cost of gas transport, however, is critically important. The major costs of pipeline transport are fixed demand charges and the value of transport services out of western Canada is determined by the demand and the supply (the location and size of the pipeline infrastructure, which is essentially fixed over short to medium time frames). This value can vary significantly as the demand for pipeline space varies both daily and seasonally. Excess pipeline capacity is generally good for the Canadian producing industry since it lowers transport costs, but excess capacity also plays a role in linking producing-basin and market area prices to one another. This is illustrated for the case of Alberta and Texas gas prices, which show higher correlation with falling load factors on ex-Alberta pipeline capacity. 5 figs

  13. Status of irradiation testing and PIE of MOX (Pu-containing) fuel

    International Nuclear Information System (INIS)

    Dimayuga, F.C.; Zhou, Y.N.; Ryz, M.A.

    1995-01-01

    This paper describes AECL's mixed oxide (MOX) fuel-irradiation and post-irradiation examination (PIE) program. Post-irradiation examination results of two major irradiation experiments involving several (U, Pu)O 2 fuel bundles are highlighted. One experiment involved bundles irradiated to burnups ranging fro 400 to 1200 MWh/kgHe in the Nuclear Power Demonstration (NPD) reactor. The other experiment consisted of several (U, Pu)O 2 bundles irradiated to burnups of up to 500 Mwh/kgHe in the National Research Universal (NRU) reactor. Results of these experiments demonstrate the excellent performance of CANDU MOX fuel. This paper also outlines the status of current MOX fuel irradiation tests, including the irradiation of various (U, Pu)O 2 bundles. The strategic importance of MOX fuel to CANDU fuel-cycle flexibility is discussed. (author)

  14. Effectiveness, Improvement and Educational Change: A Distinctively Canadian Approach?

    Science.gov (United States)

    Hargreaves, Andy; Fink, Dean

    1998-01-01

    A distinctive Canadian school of thought on educational change is inclined to synthesize diverse bodies of work and integrate nonrational and emotional dimensions with rational and technically effective ones in a socially critical way. Highlights the Canadian perspective through discussions about complex systems, contexts of change, critical…

  15. How Canadian Universities Use Social Media to Brand Themselves

    Science.gov (United States)

    Bélanger, Charles H.; Bali, Suchita; Longden, Bernard

    2014-01-01

    This paper explores social media marketing strategies applied by Canadian universities as a tool for institutional branding, recruitment and engagement of home and international students. The target sample involves the total population of Canadian university-status institutions ("N" = 106). Qualitative data were collected from two major…

  16. International Disputes and Cultural Ideas in the Canadian Arctic

    DEFF Research Database (Denmark)

    Burke, Danita Catherine

    of the Canadian-Arctic relationship. Using Canada as the focus for the analysis, the purpose of this project is to contribute to the existing Arctic studies and international relations literature by examining how interests and disputes in the Canadian Arctic region have been affected by domestic cultural...

  17. The development of a remote gauging and inspection capability for fuel channels in Candu reactors

    International Nuclear Information System (INIS)

    Dolbey, M.P.; Kupcis, O.A.

    1979-01-01

    Equipment under development for the inspection and gauging of pressure tubes in CANDU (Canadian Deuterium Uranium) type reactors is described. A brief overview of the mechanical scanning system is presented followed by a detailed description of the measurement and data processing systems for the gauging of diameter and wall thickness, volumetric inspection of the tube wall and gauging of the annular gap between the pressure tube and the calandria tube. Experience of testing ultrasonic transducers in very high (10 6 Roentgens/hour)(R/h) radiation fields is reviewed. (author)

  18. Canadian pediatric gastroenterology workforce: Current status, concerns and future projections

    Science.gov (United States)

    Morinville, Véronique; Drouin, Éric; Lévesque, Dominique; Espinosa, Victor M; Jacobson, Kevan

    2007-01-01

    BACKGROUND: There is concern that the Canadian pediatric gastroenterology workforce is inadequate to meet health care demands of the pediatric population. The Canadian Association of Gastroenterology Pediatric Committee performed a survey to determine characteristics and future plans of the Canadian pediatric gastroenterology workforce and trainees. METHODS: Estimates of total and pediatric populations were obtained from the 2001 Census of Population, Statistics Canada (with estimates to July 1, 2005). Data on Canadian pediatric gastroenterologists, including clinical full-time equivalents, sex, work interests, opinions on workforce adequacy, retirement plans, fellowship training programs and future employment plans of fellows, were gathered through e-mail surveys and telephone correspondence in 2005 and 2006. RESULTS: Canada had an estimated population of 32,270,507 in 2005 (6,967,853 people aged zero to 17 years). The pediatric gastroenterology workforce was estimated at 9.2 specialists per million children. Women accounted for 50% of the workforce. Physician to pediatric population ratios varied, with Alberta demonstrating the highest and Saskatchewan the lowest ratios (1:69,404 versus 1:240,950, respectively). Between 1998 and 2005, Canadian pediatric gastroenterology fellowship programs trained 65 fellows (65% international trainees). Twenty-two fellows (34%) entered the Canadian workforce. CONCLUSIONS: The survey highlights the variable and overall low numbers of pediatric gastroenterologists across Canada, an increasingly female workforce, a greater percentage of part-time physicians and a small cohort of Canadian trainees. In conjunction with high projected retirement rates, greater demands on the work-force and desires to partake in nonclinical activities, there is concern for an increasing shortage of pediatric gastroenterologists in Canada in future years. PMID:17948136

  19. The Canadian experience in frontier environmental protection

    International Nuclear Information System (INIS)

    Jones, G.H.

    1991-01-01

    Early Canadian frontier exploration (from 1955 onshore and from 1966 for offshore drilling) caused insignificant public concern. The 1967-1968 Torrey Canyon Tanker and Santa Barbara disasters roused public opinion and governments. In Canada, 1969-1970 Arctic gas blowouts, a tanker disaster, and damage to the 'Manhattan' exacerbated concerns and resulted in new environmental regulatory constraints. From 1970, the Arctic Petroleum Operations Association learned to operate safely with environmental responsibility. It studied physical environment for design criteria, and the biological and human environment to ameliorate impact. APOA's research projects covered sea-ice, permafrost, sea-bottom, oil-spills, bird and mammal migration, fish habitat, food chains, oceanography, meteorology, hunters'/trappers' harvests, etc. In 1971 Eastcoast Petroleum Operators' Association and Alaska Oil and Gas Association followed APOA's cooperative research model. EPOA stressed icebergs and fisheries. Certain research was handled by the Canadian Offshore Oil Spill Research Association. By the mid-1980s these associations had undertaken $70,000,000 of environmental oriented research, with equivalent additional work by member companies on specific needs and similar sums by Federal agencies often working with industry on complementary research. The frontier associations then merged with the Canadian Petroleum Association, already active environmentally in western Canada. Working with government and informing environmental interest groups, the public, natives, and local groups, most Canadian frontier petroleum operations proceeded with minimal delay and environmental disturbance

  20. Canadians, nuclear weapons, and the Cold War security dilemma

    International Nuclear Information System (INIS)

    Eaton, M.A.

    2007-01-01

    This dissertation provides a history of Canadian ideas about nuclear weapons from the late 1950s until the end of the Trudeau era in 1984. Throughout this period, Canadians reacted to the insecurity they felt in the world around them by expressing many conflicting, often irreconcilable views about a range of nuclear weapon issues, including Canada's acquisition of nuclear warheads in 1963, the U.S. ABM program in the 1960s and early 1970s, the role of Canadian nuclear technology in the development of India's first nuclear explosion, and the Trudeau government's decision to allow the U.S. military to test cruise missiles in northern Canada The dissertation concludes with an examination of the emergence of a broadly-based, increasingly mainstream and influential anti-nuclear movement in the early 1980s, the clearest manifestation of the insecurity Canadians experienced at the time. .The nuclear debates examined in this dissertation reveal that Canadians were divided over nuclear weapons, nuclear strategy, the arms race, proliferation, and arms control and disarmament. In particular, they came to fundamentally different conclusions about how Canada's nuclear weapon policies, and its support for the nuclear policies of its alliances, would contribute to international stability and order. Some believed that their security rested on the maintenance of a strong Western nuclear deterrent and supported Canada contributing to its credibility; others believed that the constant modernisation of nuclear arsenals fuelled by the superpower arms race posed a serious threat to their security. This conceptual dilemma-the security through nuclear strength argument versus the fear that the quest for security through quantitative and qualitative improvements of nuclear stockpiles increased the likelihood of nuclear war-left Canadians divided over the value and utility of nuclear weapons and the strategies developed around them. At the same time, Canadians' ideas about nuclear weapons

  1. Canadians, nuclear weapons, and the Cold War security dilemma

    Energy Technology Data Exchange (ETDEWEB)

    Eaton, M.A

    2007-07-01

    This dissertation provides a history of Canadian ideas about nuclear weapons from the late 1950s until the end of the Trudeau era in 1984. Throughout this period, Canadians reacted to the insecurity they felt in the world around them by expressing many conflicting, often irreconcilable views about a range of nuclear weapon issues, including Canada's acquisition of nuclear warheads in 1963, the U.S. ABM program in the 1960s and early 1970s, the role of Canadian nuclear technology in the development of India's first nuclear explosion, and the Trudeau government's decision to allow the U.S. military to test cruise missiles in northern Canada The dissertation concludes with an examination of the emergence of a broadly-based, increasingly mainstream and influential anti-nuclear movement in the early 1980s, the clearest manifestation of the insecurity Canadians experienced at the time. .The nuclear debates examined in this dissertation reveal that Canadians were divided over nuclear weapons, nuclear strategy, the arms race, proliferation, and arms control and disarmament. In particular, they came to fundamentally different conclusions about how Canada's nuclear weapon policies, and its support for the nuclear policies of its alliances, would contribute to international stability and order. Some believed that their security rested on the maintenance of a strong Western nuclear deterrent and supported Canada contributing to its credibility; others believed that the constant modernisation of nuclear arsenals fuelled by the superpower arms race posed a serious threat to their security. This conceptual dilemma-the security through nuclear strength argument versus the fear that the quest for security through quantitative and qualitative improvements of nuclear stockpiles increased the likelihood of nuclear war-left Canadians divided over the value and utility of nuclear weapons and the strategies developed around them. At the same time, Canadians

  2. Outward bound: Unprecedented opportunity lures all Canadian energy sectors to international oil scene

    International Nuclear Information System (INIS)

    Jaremko, G.

    1998-01-01

    The global dimensions of Canadian energy enterprises were reviewed. It has been found that as the Western Canadian Sedimentary Basin is getting more mature, the opportunities in Canada are declining, hence the worldwide involvements of Canadian oil and service and supply companies in exploration, drilling, production and servicing in many parts of the world. Canadian Occidental Petroleum in Yemen, Canadian Fracmaster in Russia, Destiny Resource Services in South America, Gabon, Yemen and Papua New Guinea, Pacalta Resources Limited in Ecuador, Talisman Energy in Indonesia, TransCanada Pipelines, Ocelot Energy Inc and Nova Corporation building pipelines in South America and in Zambia, and Atco everywhere, are just some of the examples cited. So far, Canadian push abroad is short of a rush as only 10 per cent of spending and production by Canadian oil and gas companies is overseas, compared to 50 per cent for Americans. The ratio is about the same for Canadian service and supply companies. Canada has the advantage of being almost the only industrial society without an unpleasant imperial past. That, combined with the 'nice guy' image of the maple leaf will inevitably lead to even greater Canadian share of the international oil and gas business. The decline in the traditional role of U. S. companies in global oil markets after 1985 (according to a recent API report) and the tremendous opportunities created by the opening of the former Soviet Union to foreign capital will also contribute to enhancing the international role played by Canadian oil, gas, and service and supply companies

  3. The Transcultural Diabetes Nutrition Algorithm: A Canadian Perspective

    Science.gov (United States)

    Sievenpiper, John L.; Jenkins, David; Yale, Jean-François; Bell, Rhonda; Després, Jean-Pierre; Ransom, Thomas P. P.; Dupre, John; Kendall, Cyril; Hegazi, Refaat A.; Marchetti, Albert; Hamdy, Osama; Mechanick, Jeffrey I.

    2014-01-01

    The Transcultural Diabetes Nutrition Algorithm (tDNA) is a clinical tool designed to facilitate implementation of therapeutic lifestyle recommendations for people with or at risk for type 2 diabetes. Cultural adaptation of evidence-based clinical practice guidelines (CPG) recommendations is essential to address varied patient populations within and among diverse regions worldwide. The Canadian version of tDNA supports and targets behavioural changes to improve nutritional quality and to promote regular daily physical activity consistent with Canadian Diabetes Association CPG, as well as channelling the concomitant management of obesity, hypertension, dyslipidemia, and dysglycaemia in primary care. Assessing glycaemic index (GI) (the ranking of foods by effects on postprandial blood glucose levels) and glycaemic load (GL) (the product of mean GI and the total carbohydrate content of a meal) will be a central part of the Canadian tDNA and complement nutrition therapy by facilitating glycaemic control using specific food selections. This component can also enhance other metabolic interventions, such as reducing the need for antihyperglycaemic medication and improving the effectiveness of weight loss programs. This tDNA strategy will be adapted to the cultural specificities of the Canadian population and incorporated into the tDNA validation methodology. PMID:24550982

  4. How Medical Tourism Enables Preferential Access to Care: Four Patterns from the Canadian Context.

    Science.gov (United States)

    Snyder, Jeremy; Johnston, Rory; Crooks, Valorie A; Morgan, Jeff; Adams, Krystyna

    2017-06-01

    Medical tourism is the practice of traveling across international borders with the intention of accessing medical care, paid for out-of-pocket. This practice has implications for preferential access to medical care for Canadians both through inbound and outbound medical tourism. In this paper, we identify four patterns of medical tourism with implications for preferential access to care by Canadians: (1) Inbound medical tourism to Canada's public hospitals; (2) Inbound medical tourism to a First Nations reserve; (3) Canadian patients opting to go abroad for medical tourism; and (4) Canadian patients traveling abroad with a Canadian surgeon. These patterns of medical tourism affect preferential access to health care by Canadians by circumventing domestic regulation of care, creating jurisdictional tensions over the provision of health care, and undermining solidarity with the Canadian health system.

  5. CANDU fuel - fifteen years of power reactor experience

    International Nuclear Information System (INIS)

    Fanjoy, G.R.; Bain, A.S.

    1977-01-01

    CANDU (Canada Deuterium Uranium) fuel has operated in power reactors since 1962. Analyses of performance statistics, supplemented by examinations of fuel from power reactors and experimental loops have yielded: (a) A thorough understanding of the fundamental behaviour of CANDU fuel. (b) Data showing that the predicted high utilization of uranium has been achieved. Actual fuelling costs in 1976 at the Pickering Generating Station are 1.2 m$/kWh (1976 Canadian dollars) with the simple oncethrough natural-UO 2 fuel cycle. (c) Criteria for operation, which have led to the current very low defect rate of 0.03% of all assemblies and to ''CANLUB'' fuel, which has a graphite interlayer between the fuel and sheath to reduce defects on power increases. (d) Proof that the short length (500 mm), collapsible cladding features of the CANDU bundle are successful and that the fuel can operate at high-power output (current peak outer-element linear power is 58 +- 15% kW/m). Involvement by the utility in all stages of fuel development has resulted in efficient application of this fundamental knowledge to ensure proper fuel specifications, procurement, scheduling into the reactor and feedback to developers, designers and manufacturers. As of mid-1976 over 3 x 10 6 individual elements have been built in a well-estabilished commercially competitive fuel fabrication industry and over 2 x 10 6 elements have been irradiated. Only six defects have been attributed to faulty materials or fabrication, and the use of high-density UO 2 with low-moisture content precluded defects from hydrogen contamination and densification. Development work on UO 2 and other fuel cycles (plutonium and thorium) is continuing, and, because CANDU reactors use on-power fuelling, bundles can be inserted into power reactors for testing. Thus new fuel designs can be quickly adopted to ensure that the CANDU system continues to provide low-cost energy with high reliability

  6. Engendering migrant health: Canadian perspectives

    National Research Council Canada - National Science Library

    Spitzer, Denise L

    2011-01-01

    "Voluntary migrants to Canada are generally healthier than the average Canadian, but after ten years in the country they report poorer health and higher rates of chronic disease than those born here...

  7. The Canadian heavy water situation

    International Nuclear Information System (INIS)

    Dahlinger, A.

    The Canadian heavy water industry is analyzed. Supply and demand are predicted through 1985. Pricing is broken down into components. Backup R and D contributes greatly to process improvements. (E.C.B.)

  8. Some loop experiments in the NRX reactor to study the corrosion of mild steel by flowing water at 90oF

    International Nuclear Information System (INIS)

    Allison, G.M.

    1956-11-01

    This work was undertaken to find the water conditions necessary for minimum corrosion in the mild steel thermal shield recirculating systems in NRX and NRU. This report contains the chemical and corrosion results obtained by operating three mild steel loops in which water at 85-95 o F was recirculated through test sections located in J-rod positions in the NRX reactor. Lowest corrosion rates were found when the water was maintained at pH 10.5 with or without oxygen being present. In both cases the corrosion was general in nature and no pitting occurred. At pH 7 with oxygen present in the water severe pitting took place and the corrosion rate was several times higher than similar conditions without oxygen in the water. Under oxygen-free conditions the corrosion product was Fe 3 O 4 . At pH 7 and with 3-5 ppm of O 2 in the water the corrosion product was a mixture of Fe 3 O 4 and γ-Fe 2 O 3 . At high pH with oxygen present Fe 3 O 4 predominated with some traces of Fe 2 O 3 . The systems tested may he listed in order of increasing corrosiveness: High pH with or without O 2 in the water 2 present and continual purification 2 present and no purification or pH control 2 present. (author)

  9. Canadian fusion fuels technology project

    International Nuclear Information System (INIS)

    1986-01-01

    The Canadian Fusion Fuels Technology Project was launched in 1982 to coordinate Canada's provision of fusion fuels technology to international fusion power development programs. The project has a mandate to extend and adapt existing Canadian tritium technologies for use in international fusion power development programs. 1985-86 represents the fourth year of the first five-year term of the Canadian Fusion Fuels Technology Project (CFFTP). This reporting period coincides with an increasing trend in global fusion R and D to direct more effort towards the management of tritium. This has resulted in an increased linking of CFFTP activities and objectives with those of facilities abroad. In this way there has been a continuing achievement resulting from CFFTP efforts to have cooperative R and D and service activities with organizations abroad. All of this is aided by the cooperative international atmosphere within the fusion community. This report summarizes our past year and provides some highlights of the upcoming year 1986/87, which is the final year of the first five-year phase of the program. AECL (representing the Federal Government), the Ministry of Energy (representing Ontario) and Ontario Hydro, have given formal indication of their intent to continue with a second five-year program. Plans for the second phase will continue to emphasize tritium technology and remote handling

  10. Reliability issues : a Canadian perspective

    International Nuclear Information System (INIS)

    Konow, H.

    2004-01-01

    A Canadian perspective of power reliability issues was presented. Reliability depends on adequacy of supply and a framework for standards. The challenges facing the electric power industry include new demand, plant replacement and exports. It is expected that demand will by 670 TWh by 2020, with 205 TWh coming from new plants. Canada will require an investment of $150 billion to meet this demand and the need is comparable in the United States. As trade grows, the challenge becomes a continental issue and investment in the bi-national transmission grid will be essential. The 5 point plan of the Canadian Electricity Association is to: (1) establish an investment climate to ensure future electricity supply, (2) move government and industry towards smart and effective regulation, (3) work to ensure a sustainable future for the next generation, (4) foster innovation and accelerate skills development, and (5) build on the strengths of an integrated North American system to maximize opportunity for Canadians. The CEA's 7 measures that enhance North American reliability were listed with emphasis on its support for a self-governing international organization for developing and enforcing mandatory reliability standards. CEA also supports the creation of a binational Electric Reliability Organization (ERO) to identify and solve reliability issues in the context of a bi-national grid. tabs., figs

  11. Canadian Civil Society Organizations and Human Rights and Global ...

    International Development Research Centre (IDRC) Digital Library (Canada)

    This project aims to strengthen the capacity of Canadian civil society organizations (CSOs) to inform Canadian policy on human rights and global justice. ... in the developing world continue to face obstacles that limit their ability to establish careers and become leaders in the fields of science, technology, engineering, and ...

  12. Canadian Medicare: prognosis guarded.

    Science.gov (United States)

    Naylor, C D; Fooks, C; Williams, J I

    1995-08-01

    Beset by unprecedented fiscal pressures, Canadian medicare has reached a crossroads. The authors review the impact of recent cuts in federal transfer payments on provincial health care programs and offer seven suggestions to policymakers trying to accommodate these reductions. (1) Go slowly: public health care spending is no longer rising and few provinces have the necessary systems in place to manage major reductions. (2) Target reductions, rewarding quality and efficiency instead of making across-the-board cuts. (3) Replace blame with praise:give health care professionals and institutions credit for their contributions. (4) Learn from the successful programs and policies already in place across the country. (5) Foster horizontal and vertical integration of services. (6) Promote physician leadership by rewarding efforts to promote the efficient use of resources. (7) Monitor the effects of cutbacks: physician groups should cooperate with government in maintaining a national "report card" on services, costs and the health status of Canadians.

  13. Mortality among long-term Chalk River employees

    International Nuclear Information System (INIS)

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

    1986-12-01

    Mortality among Chalk River Nuclear Laboratory (CRNL) employees who died during employment or after retirement has been updated to 1985 December 31. Data in tabular form are presented for overall mortality for male and female employees, for the participants in the clean-up for the NRX and NRU reactor accidents and for a group of CRNL staff with lifetime accumulative doses in excess of 0.2 Sv. Data are also presented on the different types of cancer causing death among male employees. No statistically significant increases in cancer deaths were found in any of the groups analyzed. 25 refs

  14. Full-Length High-Temperature Severe Fuel Damage Test No. 5: Final safety analysis

    International Nuclear Information System (INIS)

    Lanning, D.D.; Lombardo, N.J.; Panisko, F.E.

    1993-09-01

    This report presents the final safety analysis for the preparation, conduct, and post-test discharge operation for the Full-Length High Temperature Experiment-5 (FLHT-5) to be conducted in the L-24 position of the National Research Universal (NRU) Reactor at Chalk River Nuclear Laboratories (CRNL), Ontario, Canada. The test is sponsored by an international group organized by the US Nuclear Regulatory Commission. The test is designed and conducted by staff from Pacific Northwest Laboratory with CRNL staff support. The test will study the consequences of loss-of-coolant and the progression of severe fuel damage

  15. The Canadian Association of Gastroenterology Education Committee Report

    Directory of Open Access Journals (Sweden)

    Ronald J Bridges

    2004-01-01

    Full Text Available I am pleased to provide an update regarding the activities and future directions of the Canadian Association of Gastroenterology (CAG Education Committee. The mandate of the CAG Education Committee is to facilitate, develop and promote excellence as it pertains to educational initiatives for the Canadian gastroenterology community. Professional education has long remained a priority of the CAG - a fact well recognized by the membership. The 2002 CAG Strategic Planning Survey showed that members rate Canadian Digestive Diseases Week (CDDW as the most important CAG service, on par with Digestive Diseases Week regarding its usefulness (1. CDDW 2004 offered delegates a variety of basic science and clinical symposia, the popular and well received 'Breakfast with the Expert' sessions and a comprehensive Postgraduate Course reviewing key developments in gastroenterology, nutrition and hepatology.

  16. Assessing perceived health risks of climate change : Canadian public opinion 2008

    International Nuclear Information System (INIS)

    2008-03-01

    This paper discussed a survey conducted to evaluate the awareness, knowledge, attitudes, and behaviours of Canadians in relation to climatic change. A total of 1600 telephone surveys were conducted with a broad range of age groups. The study showed that climate change is considered by many Canadians to pose a significant threat at both local and global levels. Evidence of climate change has been noted in many communities. However, relatively few Canadians understand how climate change may impact human health. While many Canadians associated climatic change with air pollution hazards and ozone depletion, most Canadians were not aware of the potential negative health impacts related to changes in disease vectors, extreme weather events, and coastal flooding. The strongest awareness and concern about health impacts were expressed by Canadians concerned about global warming. Individuals with chronic health conditions were more likely to be attuned to the potential health impacts of climatic change. Seniors viewed climate change as a longer term problem. Only 10 per cent of Canadians viewed global warming as a major health risk. Sixty-nine per cent of Canadians believed that global warming was happening, while 63 per cent attributed climate change to human activity. Nearly half of all respondents believed that an extreme weather disaster would affect their community during the course of their lifetime. The report suggested that marketing or communications campaigns should build public awareness of the health risks associated with direct or proximal environmental risks. Information about health risks should be specific, and communications should be tailored to age cohorts. Television and print media should be used to build awareness of the health risks of climate change. Provincial concerns related to climatic change were also outlined. tabs., figs

  17. Women and nuclear issues: Comments in a Canadian perspective

    International Nuclear Information System (INIS)

    Dionne-Marsolais, Rita

    1989-01-01

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

  18. The turning black tide : energy prices and the Canadian dollar

    Energy Technology Data Exchange (ETDEWEB)

    Issa, R.; Lafrance, R.; Murray, J. [Bank of Canada, Ottawa, ON (Canada)

    2008-08-15

    This paper examined the relationship between energy prices and the Canadian-United States dollar real exchange rate. The researchers evaluated the standard Amano-van Norden (AvN) equation formulated to demonstrate that higher real energy prices lead to a depreciation of the Canadian dollar. Major developments in the Canadian energy market were discussed, as well as policy initiatives designed to address Canada's trade balance by increasing energy exports. The study examined the AvN equation using Monte Carlo experiments to determine the parameter stability of the equation. Results indicated that the co-integrating relationship in the standard AvN equation were no longer supported. Structural break tests were used to demonstrate that major changes in Canada's energy policies and cross-border trade and investment strategies have led to an increase in the Canadian dollar's value when energy prices are high. The study presented a new equation designed to account for Canadian dollar's appreciation since 2003. It was concluded that net energy exports in the 1990s outweighed the negatives associated with Canada's energy-intensive production processes. 39 refs., 6 tabs., 10 figs.

  19. The Specifics of Post-War Canadian Immigration Policy (1945–1957

    Directory of Open Access Journals (Sweden)

    Mariia Burtseva

    2017-12-01

    Full Text Available Immigration plays a significant role in various areas of the society’s life and the international policy. Investigating the Canadian experience of immigration is one of the major elements for understanding different aspects of actual mass relocation. The principal objective of this study is to investigate the specifics of Canadian immigration policy following the Second World War. The research is based on analyzing legislation regulations that established Canadian immigration policy from 1945 to 1957. The findings indicated that there were multilateral causes for the after-war immigration changes. And that in reality, Canadian immigration policy in the post-war decade was quite ambiguous because of enacting liberal and discriminatory legislation at the same time.

  20. The Canadian nuclear fuel waste management program

    International Nuclear Information System (INIS)

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

    1983-05-01

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

  1. Canadian heavy water production

    International Nuclear Information System (INIS)

    Dahlinger, A.; Lockerby, W.E.; Rae, H.K.

    1977-05-01

    The paper reviews Canadian experience in the production of heavy water, presents a long-term supply projection, relates this projection to the anticipated long-term electrical energy demand, and highlights principal areas for further improvement that form the bulk of our research and development program on heavy water processes

  2. Adaptation of the ITER facility design to a Canadian site

    International Nuclear Information System (INIS)

    Smith, S.

    2001-01-01

    This paper presents the status of Canadian efforts to adapt the newly revised ITER facility design to suit the specific characteristics of the proposed Canadian site located in Clarington, west of Toronto, Ontario. ITER Canada formed a site-specific design team in 1999, comprising participants from three Canadian consulting companies to undertake this work. The technical aspects of this design activity includes: construction planning, geotechnical investigations, plant layout, heat sink design, electrical system interface, site-specific modifications and tie-ins, seismic design, and radwaste management. These areas are each addressed in this paper. (author)

  3. The objectives and activities of the Canadian Radiation Protection Association

    International Nuclear Information System (INIS)

    Haynes, M.J.

    1998-01-01

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

  4. Canadian heavy water production

    International Nuclear Information System (INIS)

    Dahlinger, A.; Lockerby, W.E.; Rae, H.K.

    1977-01-01

    The paper reviews Canadian experience in the production of heavy water, presents a long-term supply projection, relates this projection to the anticipated long-term electrical energy demand, and highlights principal areas for further improvement that form the bulk of the Canadian R and D programme on heavy water processes. Six Canadian heavy water plants with a total design capacity of 4000Mg/a are in operation or under construction. All use the Girdler-Sulphide (GS) process, which is based on deuterium exchange between water and hydrogen sulphide. Early operating problems have been overcome and the plants have demonstrated annual capacity factors in excess of 70%, with short-term production rates equal to design rates. Areas for further improvement are: to increase production rates by optimizing the control of foaming to give both higher sieve tray efficiency and higher flow rates, to reduce the incapacity due to deposition of pyrite (FeS 2 ) and sulphur (between 5% and 10%), and to improve process control and optimization of operating conditions by the application of mathematical simulations of the detailed deuterium profile throughout each plant. Other processes being studied, which look potentially attractive are the hydrogen-water exchange and the hydrogen-amine exchange. Even if they become successful competitors to the GS process, the latter is likely to remain the dominant production method for the next 10-20 years. This programme, when related to the long-term electricity demand, indicates that heavy water supply and demand are in reasonable balance and that the Candu programme will not be inhibited because of shortages of this commodity. (author)

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

    International Nuclear Information System (INIS)

    Paget, S.

    2006-01-01

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

  6. International surgery: definition, principles and Canadian practice

    Science.gov (United States)

    Lett, Ronald

    2003-01-01

    This article is dedicated to the Canadian international surgeon, Norman Bethune (1890–1939). International surgery is defined as a humanitarian branch of medicine concerned with the treatment of bodily injuries or disorders by incision or manipulations, emphasizing cooperation and understanding among nations and involving education, research, development and advocacy. In this article I review the colonial past, the dark ages following the Declaration of Alma-Ata, the progress made and the present challenges in international surgery. I present a definition of international surgery that recognizes the current era of surgical humanitarianism, validates a global understanding of surgical issues and promotes cooperation among nations. Included are the principles of international surgery: education, research, infrastructure development and advocacy. International surgical projects are classified according to type (clinical, relief, developmental) and integration strategy (vertical or horizontal). Also reviewed are the Canadian practice of international surgery by nongovernmental, professional and academic organizations and the requirements of international and Canadian funding agencies, the development concepts basic to all projects, including results-based management and the cross-cutting themes of gender equity, environmental protection and human safety. I recommend formalizing international surgery into a discipline as a means of promoting surgical care in low-income countries. If international surgery is to be sustained in Canada, infrastructure and support from Canadian surgeons is particularly important. An understanding of the history, definition and classification of international surgery should promote surgical care in low-income countries. PMID:14577711

  7. Conference summaries

    International Nuclear Information System (INIS)

    1991-01-01

    This volume contains conference summaries for the 31. annual conference of the Canadian Nuclear Association and the 12. annual conference of the Canadian Nuclear Society. Topics of discussion include: reactor physics; thermalhydraulics; industrial irradiation; computer applications; fuel channel analysis; small reactors; severe accidents; fuel behaviour under accident conditions; reactor components, safety related computer software; nuclear fuel management; fuel behaviour and performance; reactor safety; reactor engineering; nuclear waste management; and, uranium mining and processing

  8. Canadian nuclear power plant construction cost forecast and analysis

    International Nuclear Information System (INIS)

    Keng, C.W.K.

    1985-01-01

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

  9. Engendering migrant health: Canadian perspectives

    National Research Council Canada - National Science Library

    Spitzer, Denise L

    2011-01-01

    .... What contributes to this deterioration, and how can its effects be mitigated? Engendering Migrant Health brings together researchers from across Canada to address the intersections of gender, immigration, and health in the lives of new Canadians...

  10. The Transcultural Diabetes Nutrition Algorithm: A Canadian Perspective

    Directory of Open Access Journals (Sweden)

    Réjeanne Gougeon

    2014-01-01

    Full Text Available The Transcultural Diabetes Nutrition Algorithm (tDNA is a clinical tool designed to facilitate implementation of therapeutic lifestyle recommendations for people with or at risk for type 2 diabetes. Cultural adaptation of evidence-based clinical practice guidelines (CPG recommendations is essential to address varied patient populations within and among diverse regions worldwide. The Canadian version of tDNA supports and targets behavioural changes to improve nutritional quality and to promote regular daily physical activity consistent with Canadian Diabetes Association CPG, as well as channelling the concomitant management of obesity, hypertension, dyslipidemia, and dysglycaemia in primary care. Assessing glycaemic index (GI (the ranking of foods by effects on postprandial blood glucose levels and glycaemic load (GL (the product of mean GI and the total carbohydrate content of a meal will be a central part of the Canadian tDNA and complement nutrition therapy by facilitating glycaemic control using specific food selections. This component can also enhance other metabolic interventions, such as reducing the need for antihyperglycaemic medication and improving the effectiveness of weight loss programs. This tDNA strategy will be adapted to the cultural specificities of the Canadian population and incorporated into the tDNA validation methodology.

  11. The Canadian oil market: Annual review for 1993

    International Nuclear Information System (INIS)

    1994-07-01

    An overview is provided of the salient features of the Canadian oil market for 1993. This is the first annual version of the review; previous reviews (1986 to March 1993) were published quarterly. Statistics and discussion are given for refined petroleum product demand, drilling and exploration activity, crude oil supply and disposition, major oil pipelines, refinery activity, crude oil and petroleum product stocks, crude oil prices, and refined petroleum product prices. In 1993, demand for refined products continued to slowly recover against a background of generally stable prices. Drilling activity nearly doubled from 1992, due to such factors as royalty relief, rising demand, improved prices, and lower interest rates. Crude oil production rose nearly 10% over the last two years, with most of the rise occurring in 1993, and imports in 1993 reached their highest level in 15 years. Deliveries of crude to Canadian refineries rose in almost all regions. Half of Canadian crude production was exported, and the 1993 oil trade surplus reached a record $3.4 billion. Monthly Interprovincial PipeLines apportionment levels reached record highs in 1993. Refinery rationalization continued and capacity fell 6%, raising average refinery utilization to 84%. The price of Canadian sweet crude declined 7% to a five-year low. 45 figs., 9 tabs

  12. Conceptual design of a quasi-homogeneous pressurized heavy water reactor to be operated in the closed Th-U233 fuel cycle

    International Nuclear Information System (INIS)

    1979-06-01

    This paper deals with the heavy water reactor, which, from the neutron economy point of view, offers advantages over the light water reactor. Its capability to be fuelled with natural uranium has also been considered a desirable nuclear option by various countries with sufficient domestic uranium resources not wishing to be dependent on the import of enrichment and other fuel cycle services which, in addition, would draw on the foreign exchange reserves. Pressurized heavy water reactors have been designed and built according to two somewhat different versions. While the Canadian CANDU-PHWR concept uses pressure tubes in a nearly unpressurized moderator tank (calandria), the German development line takes advantage of the established and well proven LWR technology, and, thus, uses a pressure vessel design where coolant channels and the surrounding moderator are held at equal pressure. This pressure vessel type heavy water reactor which has been built on a commercial demonstration plant level at ATUCHA in Argentina is described in a companion paper where also a conceptual design for a 685 MWsub(e) PHWR is discussed

  13. What do we know about Canadian involvement in medical tourism?: a scoping review.

    Science.gov (United States)

    Snyder, Jeremy; Crooks, Valorie A; Johnston, Rory; Kingsbury, Paul

    2011-01-01

    Medical tourism, the intentional pursuit of elective medical treatments in foreign countries, is a rapidly growing global industry. Canadians are among those crossing international borders to seek out privately purchased medical care. Given Canada's universally accessible, single-payer domestic health care system, important implications emerge from Canadians' private engagement in medical tourism. A scoping review was conducted of the popular, academic, and business literature to synthesize what is currently known about Canadian involvement in medical tourism. Of the 348 sources that were reviewed either partly or in full, 113 were ultimately included in the review. The review demonstrates that there is an extreme paucity of academic, empirical literature examining medical tourism in general or the Canadian context more specifically. Canadians are engaged with the medical tourism industry not just as patients but also as investors and business people. There have been a limited number of instances of Canadians having their medical tourism expenses reimbursed by the public medicare system. Wait times are by far the most heavily cited driver of Canadians' involvement in medical tourism. However, despite its treatment as fact, there is no empirical research to support or contradict this point. Although medical tourism is often discussed in the Canadian context, a paucity of data on this practice complicates our understanding of its scope and impact.

  14. Canadian gas exports to U.S. set fourth consecutive record

    International Nuclear Information System (INIS)

    Anon.

    1992-01-01

    Canadian natural gas exports in 1991 set a record for the fourth year in a row, Canadian Enerdata Ltd. reports. The Markham, Ont., consulting firm the shipments of gas to the U.S., Canada's only export customer for that fuel, jumped 16.8% in 1991 to 1.679 tcf. That volume replaced the previous record of 1.437 tcf exported just 1 year earlier. Enerdata figures show the 1991 export performance increased Canada's share of the U.S. gas market to a record high of 8.7%, up from 7.7% in 1990, 7.1% in 1989, 7.0% in 1988, 5.9% in 1987, and, only 4.6% in 1986. This paper reports that the performance positions Canadian exporters well for larger increases in volume and price as the U.S. gas market tightens and Canadian gas export capacity is increased in the mid-1990s

  15. Depression and suicidal ideation among Canadians aged 15 to 24.

    Science.gov (United States)

    Findlay, Leanne

    2017-01-18

    Among Canadians aged 15 to 24, the rate of depression is higher than at any other age, and suicide is the second leading cause of death. The current study provides detailed information about depression and suicidal ideation among young Canadians, including their use of mental health support. Data from the 2012 Canadian Community Health Survey-Mental Health (CCHS-MH) were used to describe rates and experiences of depression and suicidal ideation among Canadians aged 15 to 24, including psychosocial characteristics of those who had depression or reported suicidal thoughts. Characteristics associated with seeking professional support were also examined. About 11% of Canadians aged 15 to 24 had experienced depression in their lifetime; 7%, in the past year. Approximately 14% reported having had suicidal thoughts in their lifetime; 6%, in the past year. Lifetime depression and suicidal thoughts were moderately correlated (r = .34, p ⟨ .001). Individuals with lifetime depression had more than four times the odds of seeking professional support in the previous year, compared with those who did not have lifetime depression; those with lifetime suicidal thoughts had more than three times the odds of seeking professional support, compared with those who did not have lifetime suicidal thoughts. Psychosocial factors such as negative social interactions and lower perceived ability to deal with stress were associated with depression and suicidal thoughts, although these associations differed for males and females. The findings suggest that many young Canadians have depression and/or suicidal thoughts. Their odds of seeking professional support are significantly high.

  16. Dietary Sodium Intakes and Food Sources of Sodium in Canadian-Born and Asian-Born Individuals of Chinese Ethnicity at a Canadian University Campus

    Science.gov (United States)

    Yu, Yan Han; Farmer, Anna; Mager, Diana; Willows, Noreen

    2014-01-01

    Objective: To document the sodium intake and food sources of sodium of Canadian-born Chinese (CBC) and Asian-born Chinese (ABC) individuals at a Canadian university campus. Participants: Healthy adults aged 18-58 years originating from Canada, China, Hong Kong, or Taiwan were recruited from the University of Alberta (n = 40 CBC, n = 41 ABC)…

  17. Canadian petroleum history bibliography. Release update

    Energy Technology Data Exchange (ETDEWEB)

    Cass, D.

    2010-01-07

    The petroleum history bibliography was created over several years as a record dedicated to preserving the history of the Canadian petroleum industry. It comprises a list of more than 5000 publications, including books, theses, films, audio tapes, published articles and stories of the many companies that have come and gone. It aims to include all publications and audio visual products from the Social Sciences and Humanities on company histories, biographies, autobiographies, fiction, poetry and humour. An author index is included. Most government documents are excluded as they are accessible through Library and Archives Canada. This bibliography is an ongoing piece of work, and welcomes any additions relating to the study and preservation of Canadian petroleum industry history.

  18. Maintenance of ageing CANDU reactors. A regulatory perspective

    International Nuclear Information System (INIS)

    Dunstan, T.

    1996-01-01

    The subject of this paper is, 'requirements for maintenance of ageing reactors from the perspective of a regulator', with a focus on the particular theme of; 'continuing safety assurance'. A major role of maintenance is to ensure the continuing reliability and effectiveness of safety related systems and equipment. Continuing safety assurance is an issue the Atomic Energy Control Board has been wrestling with for some time. From my perspective, much remains to be done before the AECB can be confident that Canadian nuclear plants have the necessary programs in place to achieve continuing safety assurance. To introduce the topic, it would be appropriate to say a few words about the AECB's position with respect to the situation at the Pickering NGS. Why did we blow the whistle last August and, what are we doing about it? (author)

  19. Beyond "medical tourism": Canadian companies marketing medical travel.

    Science.gov (United States)

    Turner, Leigh

    2012-06-15

    Despite having access to medically necessary care available through publicly funded provincial health care systems, some Canadians travel for treatment provided at international medical facilities as well as for-profit clinics found in several Canadian provinces. Canadians travel abroad for orthopaedic surgery, bariatric surgery, ophthalmologic surgery, stem cell injections, "Liberation therapy" for multiple sclerosis, and additional interventions. Both responding to public interest in medical travel and playing an important part in promoting the notion of a global marketplace for health services, many Canadian companies market medical travel. Research began with the goal of locating all medical tourism companies based in Canada. Various strategies were used to find such businesses. During the search process it became apparent that many Canadian business promoting medical travel are not medical tourism companies. To the contrary, numerous types of businesses promote medical travel. Once businesses promoting medical travel were identified, content analysis was used to extract information from company websites. Company websites were analyzed to establish: 1) where in Canada these businesses are located; 2) the destination countries and health care facilities that they market; 3) the medical procedures they promote; 4) core marketing messages; and 5) whether businesses market air travel, hotel accommodations, and holiday tours in addition to medical procedures. Searches conducted from 2006 to 2011 resulted in identification of thirty-five Canadian businesses currently marketing various kinds of medical travel. The research project began with what seemed to be the straightforward goal of establishing how many medical tourism companies are based in Canada. Refinement of categories resulted in the identification of eighteen businesses fitting the category of what most researchers would identify as medical tourism companies. Seven other businesses market regional, cross

  20. Problems in clinical practice of domestic supply of 99Mo/99mTc. Current status and action plans on domestic production of 99Mo raw materials for medical use

    International Nuclear Information System (INIS)

    Nakamura, Yoshihide

    2012-01-01

    NRU in Canada and HFR in the Netherlands which had been producing the most important medical isotope, 99 Mo, were shut down in 2009-2010. As the production of more than 95% of global 99 Mo supply were performed in only five research reactors in the world including the two reactors mentioned above, these shutdowns resulted in global supply shortage of 99 Mo. Although the medical isotope crisis were alleviated after the two reactors returning to service, all of these five 99 Mo producing reactors are approximately 50 years old. Because the remaining life time of these reactors is not so long, the construction of new reactors or the development of new technologies to produce bulk 99 Mo, such as the neutron activation of 98 Mo in a reactor or charged particle reaction by accelerator, are proposed for the long-term security of supply of 99 Mo. The methods using the molybdenum target lead to much lower specific activity of 99 Mo compared to the production with fission method. The new chemical processing technologies, such as manufacturing 99m Tc-labeled radiopharmaceuticals from such low specific activity 99 Mo, are required for the development of domestic practical production of 99 Mo. (author)