Results 211 to 220 of about 5,597 (253)

Degraded Cooling in a CANDU Reactor

Nuclear Science and Engineering, 1984
Loss of coolant accident (LOCA) analysis for a Canada Deuterium Uranium (CANDU) reactor considers a wide range of postulated break sizes and locations in the heat transport piping. Coincident failure of the emergency coolant injection system to operate on demand must also be considered.
R. A. Brown, C. Blahnik, A. P. Muzumdar
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Moderator heat recovery of CANDU reactors

Journal of Heat Recovery Systems, 1986
Abstract A moderator heat recovery scheme is proposed for CANDU reactors. The proposed circuit utilizes all the moderator heat to the first stages of the plant feedwater heating system. CANDU-600 reactors are considered with moderator heat load varying from 120 to 160 MWth, and moderator outlet temperature (from calandria) varying from 80 to 100°C ...
Hassan E.S. Fath, Sabah T. Ahmed
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ROP margin improvement options for CANDU reactors

Annals of Nuclear Energy, 2015
Abstract Over the past few years, Candu Energy Inc. (a wholly owned subsidiary of SNC-Lavalin Inc., which acquired the assets of Atomic Energy of Canada Limited’s Commercial Reactor Division) has been continuously developing and evaluating various options to improve the regional overpower protection (ROP) margin in aged CANDU 600 MW (CANDU 6 ...
D. Kastanya, P. White, V. Caxaj, A.-S. Seidu   +3 more
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CANDU 300: The economic small reactor

Nuclear Engineering and Design, 1988
Abstract The CANDU nuclear power system has evolved in a carefully planned and systematic manner over the past 40 years. Thirty-one CANDU power stations are now in commercial operation, or under construction, world wide. Changes in the demands of the world power market, and growing interest in smaller nuclear units led AECL to develop the CANDU 300,
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Pressure Tube Development for CANDU Reactors

1984
A development program is described in which reactor grade Zr-2.5Nb pressure tubes were produced with properties comparable to current reactor tubes but which are expected to show lower in-reactor creep and growth. Lower creep and growth rates would mean smaller axial elongations of tubes in service.
RG Fleck, EG Price, BA Cheadle
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Ontario to Mothball Two CANDU Reactors

Science, 2005
NUCLEAR POWERFacing a $1.6-billion repair bill, the government of Ontario decided this month to mothball two 540-megawatt Canada Deuterium-Uranium (CANDU) nuclear reactors more than a decade before their projected retirement date, leading to questions about the future of CANDU.
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Transmutation of minor actinides in CANDU reactors

2010 1st International Nuclear & Renewable Energy Conference (INREC), 2010
Large quantities of nuclear waste plutonium have been accumulated in the civilian LWRs and CANDU reactors in form of minor actinides (MAs). Reactor grade plutonium and other transuranium elements can be used as a booster fissile fuel material in form of mixed ThO 2 /MAO 2 fuel in a CANDU fuel bundle in order to assure reactor criticality.
Sumer Sahin, Haci Mehmet Sahin, Adem Acr, Tawfik Ahmed Al-Kusayer   +3 more
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Scenarios for the Transmutation of Actinides in CANDU Reactors

18th International Conference on Nuclear Engineering: Volume 1, 2010
With world stockpiles of used nuclear fuel increasing, the need to address the long-term utilization of this resource is being studied. Many of the transuranic (TRU) actinides in nuclear spent fuel produce decay heat for long durations, resulting in significant nuclear waste management challenges.
Bronwyn Hyland, Brian Gihm
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Validation of photoneutron signals during CANDU reactor defuelling

Annals of Nuclear Energy, 2021
Abstract Photoneutrons are important in CANDU reactors, playing a role in the dynamic properties of the reactors, and acting as neutron sources during subcritical operations. During the defuelling of the Darlington Unit 2 CANDU reactor, delayed photoneutrons provided the neutron source, and the variation of neutron-monitoring signals with time and ...
J.V. Donnelly, M. Foster, C. Corner
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Applications to CANDU Reactors

2012
This chapter gives examples of how engineering data of DHC initiation, growth rate, and solvus determinations, supported by theoretical models, and associated underlying property measurements and analyses, are applied in integrity assessments of pressure tubes of CANDU reactors. Examples are given of (1) planar and volumetric flaw assessment approaches
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