Results 181 to 190 of about 2,496 (228)

TEPC Performance in the CANDU Workplace

Radiation Protection Dosimetry, 1997
Tissue-equivalent proportional counters (TEPCs) have a number of features that make them an attractive option for neutron monitoring around power reactors. These features are principally the ability of the TEPC to operate in a mixed field environment, the direct determination of the dose equivalent from first principles and a reasonably well-understood
A.J. Waker, K. Szornel, J. Nunes
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Basics of CANDU Reactor Physics

2021
Nuclear fission is the splitting of a (large) nucleus, with the release of energy. The nuclei of some heavy elements, such as U-238, do exhibit spontaneous fission in nature. However, the rate of such fissions is extremely low. The half-life of uranium is longer than 100 million years, and most of its decay is by alpha emission, so spontaneous fission ...
Wei Shen, Benjamin Rouben
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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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The ndt requirements for CANDU

Non-Destructive Testing, 1974
Abstract The author describes some of the testing problems posed by the CANDU nuclear reactor system. CANDU uses heavy water as moderator and coolant and uses pressure tubes rather than a pressure vessel. It has much in common with the British steam generating heavy water reactor.
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The Management of Spent CANDU fuel

Nuclear Technology, 1974
Projections have been made regarding the quantities of spent fuel arising from reactors in Canada.
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Fuel management in CANDU reactors

Annals of Nuclear Energy, 1976
Abstract CANDU fuel management differs completely from that in LWR's. On-power refuelling of the pressurized fuel channels with short (50 cm) fuel bundles is a continuing function of reactor operations and leads rapidly to equilibrium core conditions, refuelling rate, and fuel burn-up.
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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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CANDU Fuel—Power Ramp Performance Criteria

Nuclear Technology, 1977
Extensive fuel performance data obtained from Canadian Deuterium Uranium (CANDU) power reactors and experimental reactors are analyzed. Various modes of power ramping that cause fuel defects are identified, and fuel defect criteria are derived. The probability of a defect occurring in a power ramp is found to depend on the magnitude of the ramped power,
W. J. Penn, R. K. Lo, J. C. Wood
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Subchannel analysis of CANDU-SCWR fuel

Progress in Nuclear Energy, 2009
A cooperative study has been initiated at Xi'an Jiaotong University (XJTU) with Atomic Energy of Canada Limited (AECL) to develop a subchannel code ATHAS for preliminary analyses of flow and enthalpy distributions and cladding temperatures in CANDU fuel at super-critical water conditions.
Changying Li, Jianqiang Shan, Laurence K.H. Leung   +2 more
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Thermal Fatigue in CANDU Stations

Volume 1: Plant Operations, Maintenance, Engineering, Modifications and Life Cycle; Component Reliability and Materials Issues; Next Generation Systems, 2009
The risk of thermal fatigue, and the resulting pressure boundary failures, have resulted in a significant amount of research in the Pressurized Water Reactor (PWR) and Boiling Water Reactor (BWR) communities in the past two decades. Thermal stresses arising from thermal stratification phenomena are typically not taken into account in design ...
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