Results 221 to 230 of about 4,286 (261)

Analysis of MH-1A Loss of Coolant Accident

1972
Abstract : 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, James D. Franson, George Johnson, Henry C. Gignilliat   +3 more
openaire   +1 more source

Heat-transfer analysis in loss-of-coolant accidents

Nuclear Engineering and Design, 1968
Abstract 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, Joseph M. Genco, Gilbert E. Raines   +2 more
openaire   +1 more source

Analysis for loss of coolant accident in a fusion reactor

Fusion Engineering and Design, 1996
Active 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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Effect of the loss of coolant on the resonance escape probability

Annals of Nuclear Energy, 1979
In the analysis of the loss of coolant accident in natural uranium reactors of the Atucha or Candu type, the influence of the coolant voiding on the resonance escape probability appears to be of great importance. In this paper we study this effect on the resonance absorption, analyzing its behaviour vs coolant density.
C. Notari, A.M. Lerner
openaire   +1 more source

Coolant Recirculation in a Pressurized Water Reactor Core under Loss-of-Coolant Accident Conditions

Nuclear Science and Engineering, 1988
A model has been developed to predict the thermal hydraulics in the uncovered part of a pressurized water reactor core.
M. K. Moallemi, R. Viskanta
openaire   +1 more source

Loss of Coolant Accident and Loss of Flow Accident Analysis of the ARIES-AT Design

Fusion Technology, 2001
Loss 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, L. El-Guebaly, A. Abdou, P. Wilson, D. Henderson   +4 more
openaire   +1 more source

Integral Test and Engineering Analysis of Coolant Depletion during a Large-Break Loss-of-Coolant Accident

Nuclear Technology, 2005
This study concerns the development of an integrated calculation methodology with which to continually and consistently analyze the progression of an accident from the design-basis accident phase via core uncovery to the severe accident phase. The depletion rate of reactor coolant inventory was experimentally investigated after the safety injection ...
Yong Soo Kim, Chang Hwan Park, Byoung Uhn Bae, Goon Cherl Park, Kune Yull Suh, Un Chul Lee   +5 more
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An Analysis of Transients in Experiments on Loss-of-Coolant Accidents

Nuclear Science and Engineering, 1976
It 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...
openaire   +1 more source

Test and Evaluation of a Filtering System for Retention of Fibres in a Coolant Flow After Loss-of-Coolant Accident

Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems, 2012
In case of an accident the safe heat removal from the reactor core with the installed emergency core cooling system (ECCS) is one of the main features in reactor safety. During a loss-of-coolant accident (LOCA) the release of insulation material fragments in the reactor containment can lead to malfunctions of ECCS. Therefore, the retention of particles
T. Gocht, W. Kästner, A. Kratzsch, M. Strasser   +3 more
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BWR loss of coolant accident simulation by means of RELAP5

Nuclear Engineering and Design, 2016
Abstract 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, P. Mueller, J. Martin, W. van Doesburg, D. Hiltbrand   +4 more
openaire   +1 more source