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Ells, C.E.; Coleman, C.E.; Fidleris, V.; Causey, A.R.
Proceedings of the Canadian Nuclear Society 8. annual conference
Proceedings of the Canadian Nuclear Society 8. annual conference
AbstractAbstract
[en] The CANDU calandria tubes, made of annealed Zircaloy-2, have given excellent service in-reactor. The properties of Zircaloy-2, including its response to neutron irradiation, are very satisfactory for this application. Examination of calandria tubes removed from reactors has shown that the material should continue to respond well to the reactor environment. Thus, continued good service from the tubes is predicted
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Canadian Nuclear Society, Toronto, ON (Canada); 483 p; 1987; p. 382-389; Canadian Nuclear Society 8. annual conference; Saint John, NB (Canada); 16-17 Jun 1987
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[en] There is a growing concern over what will replace the United States nuclear power generation units once their current 40 year licenses expire. The issues that must be addressed are complex and wide ranging but essentially come to this, are the present units capable of operating beyond the original licenses in a safe and economical manner
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Canadian Nuclear Society, Toronto, ON (Canada); 483 p; 1987; p. 3-7; Canadian Nuclear Society 8. annual conference; Saint John, NB (Canada); 16-17 Jun 1987
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AbstractAbstract
[en] The corrosion and deuterium pickup performance of Zr-2.5 wt% Nb pressure tubes in Ontario Hydro's operating CANDU nuclear reactors is presented and interpreted. Zr-2.5 wt% Nb performance is compared to available data in the worldwide literature and to that for CANDU Zircaloy-2 pressure tube experience. The possible influence of trace impurities on corrosion performance is reviewed
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Source
Canadian Nuclear Society, Toronto, ON (Canada); 483 p; 1987; p. 368-374; Canadian Nuclear Society 8. annual conference; Saint John, NB (Canada); 16-17 Jun 1987
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AbstractAbstract
[en] This conference contains papers under the major topics of plant life extension, safety and the environment, reactor physics, thermohydraulics I, development and deployment, thermohydraulics II, operations I, safety r and d post chernobyl, fuel channels, operations II, and nuclear technology developments
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1987; 483 p; Canadian Nuclear Society 8. annual conference; Saint John, NB (Canada); 16-17 Jun 1987
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[en] This paper describes a fully automated ultrasonic inspection system designed to detect cracked hydride blisters in pressure tubes during a SLAR inspection. Both the ultrasonic and computer control aspects of the system are discussed and the results of both laboratory and in-reactor tests are summarized
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Source
Canadian Nuclear Society, Toronto, ON (Canada); 483 p; 1987; p. 194-198; Canadian Nuclear Society 8. annual conference; Saint John, NB (Canada); 16-17 Jun 1987
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So, C.B.; Gillespie, G.E.; Moyer, R.G.; Litke, D.G.
Proceedings of the Canadian Nuclear Society 8. annual conference
Proceedings of the Canadian Nuclear Society 8. annual conference
AbstractAbstract
[en] A series of four experiments has been performed to measure the circumferential temperature distribution and deformation of pressure tubes under slow coolant boildown conditions. During the experiments, the stratified steam flow resulted in a local hot spot at the top of the pressure tube. Presented are the experimental data from these tests, as well as important inferred channel thermalhydraulic information
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Source
Canadian Nuclear Society, Toronto, ON (Canada); 483 p; 1987; p. 241-248; Canadian Nuclear Society 8. annual conference; Saint John, NB (Canada); 16-17 Jun 1987
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Kenchington, J.M.; Ellis, P.J.; Meranda, D.G.
Proceedings of the Canadian Nuclear Society 8. annual conference
Proceedings of the Canadian Nuclear Society 8. annual conference
AbstractAbstract
[en] The development of leak detection monitoring by the Annulus Gas System (AGS) for the Ontario Hydro Nuclear Stations over the last several years is reviewed. Verified models were used to modify the AGS and provide the operators with safe operating limits. The current AGS design gives the operator an adequate warning to take timely action and if needed to shutdown the reactor safely in a controlled fashion
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Canadian Nuclear Society, Toronto, ON (Canada); 483 p; 1987; p. 425-432; Canadian Nuclear Society 8. annual conference; Saint John, NB (Canada); 16-17 Jun 1987
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AbstractAbstract
[en] The effects of the Chernobyl accident on the Safety Research and Development programs for watercooled reactors are examined including lessons which can be learned from the Chernobyl accident which would cause a major change in the direction of the watercooled reactor safety research programs
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Canadian Nuclear Society, Toronto, ON (Canada); 483 p; 1987; p. 305-306; Canadian Nuclear Society 8. annual conference; Saint John, NB (Canada); 16-17 Jun 1987
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[en] The procurement practice on pressure tubes for CANDU reactors is described. The reference design, the metallurgical and the quality assurance requirements relating to the procurement actions are noted. The objectives of procurement engineering are related to improving the tube quality and performance by specific changes in the pressure tube fabrication and the qualification procedure governing changes is briefly outlined. The future direction of pressure tube procurement practice is discussed
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Canadian Nuclear Society, Toronto, ON (Canada); 483 p; 1987; p. 361-367; Canadian Nuclear Society 8. annual conference; Saint John, NB (Canada); 16-17 Jun 1987
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AbstractAbstract
[en] An automated inspection and analysis system was developed at the Chalk River Nuclear Laboratories for the SLAR project. The system uses a combination of eddy current and ultrasonic technology and has the capability of both automated remote data acquisition and computerized data analysis for the determination of spacer locations, spacer orientation, and the determination of the gap between the pressure tube and calandria tube
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Source
Canadian Nuclear Society, Toronto, ON (Canada); 483 p; 1987; p. 188-193; Canadian Nuclear Society 8. annual conference; Saint John, NB (Canada); 16-17 Jun 1987
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