Results 21 to 30 of about 211 (130)
THE IMPACT OF POWER COEFFICIENT OF REACTIVITY ON CANDU 6 REACTORS
Nuclear Engineering and Technology, 2013 The combined effects of reactivity coefficients, along with other core nuclear characteristics, determine reactor core behavior in normal operation and accident conditions.
D. KASTANYA +3 more
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Determination of burnup limit for CANDU 6 fuel using Monte-Carlo method
Nuclear Engineering and Technology, 2021 KHNP recently has obtained the approval for the commercialization of the modified 37-element (or 37 M) fuel bundle and now is loading the 37 M fuel bundles in CANDU-6 reactors in KOREA. One of the main issues for approval was the burnup limit.
Eun-ki Lee
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UNCERTAINTY CHARACTERIZATION FRAMEWORK FOR STEADY-STATE AND TRANSIENT NEUTRONICS SIMULATIONS OF A CANDU REACTOR [PDF]
EPJ Web of Conferences, 2021 This paper reports on the development and testing of a comprehensive few-group cross section input uncertainty library for the NESTLE-C nodal diffusion-based nuclear reactor core simulator. This library represents the first milestone of a first-of-a-kind
Abdel-Khalik Hany S. +3 more
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Nuclear Engineering and Technology, 2017 In any reactor physics analysis, the instantaneous power distribution in the core can be calculated when the actual bundle-wise burnup distribution is known.
Doddy Kastanya
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Ultrasonic evaluation of hydrogen concentration and hydride properties in zirconium alloys
e-Journal of Nondestructive Testing, 2023 Various ultrasonic techniques and transducers, used for CANDU reactor pressure tube inspection to detect areas with increased hydrogen concentration, estimate its level, and determine the hydride platelet features (dimensions, orientation, and spacing)
Alex Karpelson
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CANDU Safety R&D Status, Challenges, and Prospects in Canada
Science and Technology of Nuclear Installations, 2015 In Canada, safe operation of CANDU (CANada Deuterium Uranium; it is a registered trademark of Atomic Energy of Canada Limited) reactors is supported by a full-scope program of nuclear safety research and development (R&D) in key technical areas.
W. Shen, F. Doyle
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BACKUP AND ULTIMATE HEAT SINKS IN CANDU REACTORS FOR PROLONGED SBO ACCIDENTS
Nuclear Engineering and Technology, 2013 In a pressurized heavy water reactor, following loss of the primary coolant, severe core damage would begin with the depletion of the liquid moderator, exposing the top row of internally-voided fuel channels to steam cooling conditions on the inside and ...
T. NITHEANANDAN, M.J. BROWN
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The mode of operation of CANDU power reactor in thorium self-sufficient fuel cycle [PDF]
Nuclear Technology and Radiation Protection, 2008 This paper presents the results of calculations for CANDU reactor operation in the thorium fuel cycle. The calculations were performed to estimate feasibility of operation of a heavy-water thermal neutron power reactor in the self-sufficient thorium ...
Bergelson Boris R. +2 more
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ROMANIAN EXPERIENCE ON CANDU 600 FUELLING MACHINE TESTING [PDF]
Annals: Series on engineering sciences (Academy of Romanian Scientists), 2013 The CANDU 600 Fuelling Machine is a complex mechanism which must run in safety conditions and with high reliability in the CANDU Reactor. The testing and commissioning process of this nuclear equipment meets the high standards of NPP’s requirements using
Şerban Constantin VALECA +2 more
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Physics Study of Canada Deuterium Uranium Lattice with Coolant Void Reactivity Analysis
Nuclear Engineering and Technology, 2017 This study presents a coolant void reactivity analysis of Canada Deuterium Uranium (CANDU)-6 and Advanced Canada Deuterium Uranium Reactor-700 (ACR-700) fuel lattices using a Monte Carlo code.
Jinsu Park +4 more
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