Results 231 to 240 of about 4,286 (261)
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RADIOACTIVITY CONFINEMENT FOR LOSS OF COOLANT ACCIDENTS IN NET
1993This paper provides an overview of confinement pressurization for the case of Loss of Coolant Accidents (LOCAs) occurring during plasma burn as well as during conditioning and baking. The radioactivity confinement strategy is outlined.
Edgar Ebert +2 more
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Loss of coolant analysis of AP600 reactor
2020İV ÖZET Bu çalışmanın ana amacı AP600 reaktör sisteminin küçük (Kor soğutucu girişi akış alanının %1'i), orta (%30'u) ve büyük (%100'u) kırık soğutucu kaybı kazası termal- hidrolik analizidir. Geçiş durumları için AP600 termâl-hidrolik parametreleri ve sis tem bileşkelerinin kaza koşullarındaki davranışları ayrıntılı olarak incelenmiştir.
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The effect of coolant loss on current leads for superconducting magnets
Cryogenics, 1981Abstract In this paper, we have examined the recovery of current leads for superconducting magnets after loss of coolant. It is found that if a lead is without cooling for longer than a time τ max , thermal runaway can be prevented by an increase in cooling or a decrease in current through the lead.
C. Chyba, L.G. Hyman, L. Roberts
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Nuclear Science and Engineering, 1959
A loss-of-coolant accident in a pressurized water, nuclear power plant is one which permits coolant to escape from the primary system. If such an accident were allowed to proceed uninhibiied by corrective measures, the core may lose sufficient coolant such as to permit core heatup.
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A loss-of-coolant accident in a pressurized water, nuclear power plant is one which permits coolant to escape from the primary system. If such an accident were allowed to proceed uninhibiied by corrective measures, the core may lose sufficient coolant such as to permit core heatup.
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Requirements for statistical safety demonstration for loss of coolant analyses
Nuclear Engineering and Design, 2019Abstract During the recent years, an increasing interest in computational safety analysis of Nuclear Power Plants (NPPs) is to replace the conservative evaluation model calculations by best estimate calculations supplemented by uncertainty analysis of the code results.
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The Loss-of-Coolant Accident Analysis in Pressurized Water Reactors
Nuclear Science and Engineering, 1969A generalized digital computer approach to analyze the loss-of-coolant accident in pressurized water reactors requires a systematic specification of the plant geometric, physical, and topological c...
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Review of Existing Codes for Loss-of-Coolant Accident Analysis
1977Within the last two years it has become customary in the United States to categorize all LOCA codes into two main groupings: the codes employed in the licensing application which obey the conservative assumptions prescribed by the NRC Acceptance Criteria described in Appendix K to 10 CFR 100 (1).
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Failure-Bearing Capability of Oxidized Zircaloy-4 Cladding under Simulated Loss-of-Coolant Condition
Journal of Nuclear Science and Technology, 1983Hiroshi Uetsuka, Satoru Kawasaki
exaly

