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Loss of Coolant Accident and Loss of Flow Accident Analysis of the ARIES-AT Design
Fusion Technology, 2001Loss of coolant accident (LOCA) and loss of flow accident (LOFA) analysis is performed for ARIES-AT, an advanced fusion power plant design (1000 MWe). ARIES-AT employs a high performance, high temperature blanket system. It uses the high temperature SiC/SiC for structural material and LiPb for coolant-breeder.
E. A. Mogahed +4 more
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BEST ESTIMATE THERMAL-HYDRAULIC ANALYSIS OF LOSS OF COOLANT ACCIDENTS
Proceeding of Advances in Heat Transfer Engineering, 2023Analysis of loss of coolant accidents is one of the most important issues in the Design Basis Accident assessment. Since a number of LOCAs is defined in terms of break size and location of the break, the variety of analyses for postulated accidents should be performed.
Kaliatka, Algirdas +2 more
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Preliminary analysis of loss-of-coolant accident in Fukushima nuclear accident
AIP Conference Proceedings, 2012Loss-of-Coolant Accident (LOCA) in Boiling Water Reactor (BWR) especially on Fukushima Nuclear Accident will be discussed in this paper. The Tohoku earthquake triggered the shutdown of nuclear power reactors at Fukushima Nuclear Power station. Though shutdown process has been completely performed, cooling process, at much smaller level than in normal ...
Zaki Su’ud, Rio Anshari
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The AEC and the Loss of Coolant Accident
Nature, 1973Professor Wilson gives the background to the concern being expressed about the risks associated with the possible loss of coolant from a nuclear reactor.
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Analysis for loss of coolant accident in a fusion reactor
Fusion Engineering and Design, 1996Active cooling components have to be employed in the divertor of a fusion reactor to handle the large power flow from the core plasma. An extremely large thermal stress and electromagnetic force acting on these components may cause cracking of the cooling pipe.
T. Hino, Y. Hirohata, T. Yamashina
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Heat-transfer analysis in loss-of-coolant accidents
Nuclear Engineering and Design, 1968Abstract A computer program has been written for the comprehensive analysis of core-pressure-vessel heat transfer during a loss-of-coolant accident. The program, NURLOC-1.0, is based upon a generalized procedure for numerically solving the two-dimensional heat-conduction equation over multi-connected regions with various complicating factors specific
Craig T. Walters +2 more
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ARIES-CS Loss of Coolant and Loss of Flow Accident Analyses
Fusion Science and Technology, 2007Loss of Coolant Accident (LOCA) and Loss of Flow Accident (LOFA) thermal simulations have been performed for the ARIES compact stellarator fusion power plant. The ARIES-CS design uses three separate coolant loops: lithium-lead (LiPb) in the blanket, helium in the blanket and the shield, and water in the vacuum vessel.
C. J. Martin, L. A. El-Guebaly
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Analysis of MH-1A Loss of Coolant Accident
1972Abstract : Analyses of a postulated loss of coolant accident (LOCA) for the MH- 1A Nuclear Power Plant are presented for large and intermediate size breaks in the primary system. Methods and assumptions consistent with AEC Interim Acceptance Criteria were used in evaluating the performance of the Emergency Core Cooling System (ECCS). The computer codes
Paul M. Terpolilli +3 more
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BWR loss of coolant accident simulation by means of RELAP5
Nuclear Engineering and Design, 2016Abstract Application of best estimate codes and methodologies for LOCA simulation can provide the high level of details of the real plant response necessary to assess the adequacy of an emergency core cooling system. The current KKM RELAP5 model developed for the KKM plant (Muhleberg nuclear power station) has been demonstrated to be valid for ...
K. Nikitin +4 more
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An Analysis of Transients in Experiments on Loss-of-Coolant Accidents
Nuclear Science and Engineering, 1976It was found that the results of the RELAP-3 code, which is one of the typical analytical codes for analysis of the loss-of-coolant accident (LOCA) of light water reactors, do not agree well with t...
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