Results 111 to 120 of about 2,939 (182)
RELAP5/MOD3.3 Best Estimate Analyses for Human Reliability Analysis
Science and Technology of Nuclear Installations, 2010 To estimate the success criteria time windows of operator actions the conservative approach was used in the conventional probabilistic safety assessment (PSA). The current PSA standard recommends the use of best-estimate codes.
Andrej Prošek, Borut Mavko
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RESTRUCTURING RELAP5-3D FOR NEXT GENERATION NUCLEAR PLANT ANALYSIS [PDF]
, 2006 RELAP5-3D is used worldwide for analyzing nuclear reactors under both operational transients and postulated accident conditions. Development of the RELAP code series began in 1975 and since that time the code has been continuously improved, enhanced ...
Mesina, George L. +2 more
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Science and Technology of Nuclear Installations, 2019 COMSOL Multiphysics has been used to conduct thermal-hydraulic analysis in multiple nuclear applications. The aim of this study is to benchmark the prediction accuracy of COMSOL Multiphysics in performing thermal-hydraulic analysis of TRIGA (Training ...
Ahmed K. Alkaabi, Jeffrey C. King
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Verification and Validation of Corrected Versions of RELAP5 for ATR Reactivity Analyses [PDF]
, 2008 Two versions of the RELAP5 computer code, RELAP5/MOD2.5 and RELAP5/MOD3 Version 3.2.1.2, are used to support safety analyses of the Advanced Test Reactor (ATR). Both versions of RELAP5 contain a point reactor kinetics model that has been used to simulate
Davis, Cliff B.
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RBMK thermohydraulic safety assessments using RELAP5/MOD3 codes
, 1995 The capability of the RELAP5/MOD3 code to validate various transients encountered in RBMK reactor postulated accidents has been assessed. The assessment results include a loss of coolant accident at the inlet of the core pressure tube, the blockage of a ...
Schmitt, B.E., Tsiklauri, G.V.
core +1 more source
二次开发的
He jishu为验证经二次开发后的RELAP5程序在倾斜条件下的适用性，基于缩小比例的反应堆二次侧非能动余热排出系统（Passive Residual Heat Removal System，PRS）实验装置，开展了倾斜角度为-24°~+24°的工况下的余热排出实验。在此基础上，使用二次开发后的RELAP5程序对实验工况进行了模拟计算，利用实验数据验证其适用性，并进行了进一步对比分析。研究结果表明：二次开发后的RELAP5程序能有效预测倾斜条件下系统运行特性的变化 ...
郝 承明 +8 more
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Computation of Gap Conductance in Different Fuel Assemblies in VVER-1000 Type Reactors [PDF]
مجله علوم و فنون هستهای, 2011 In this paper, a calculation for fresh fuels gap conductance at different axial lengths of fuel assemblies of the VVER-1000 type reactors has been made using two models of Calza-Bini and Relap5.
M Rahgoshay, KH Shokri
doaj
RELAP5-3D Code Includes Athena Features and Models [PDF]
, 2006 Version 2.3 of the RELAP5-3D computer program includes all features and models previously available only in the ATHENA version of the code. These include the addition of new working fluids (i.e., ammonia, blood, carbon dioxide, glycerol, helium, hydrogen,
Riemke, Richard A. +2 more
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RELAP5/MOD3.1 코드를 이용한 이차응축계통 성능 해석
, 1996 학위논문(석사) - 한국과학기술원 : 원자력공학과, 1996.2, [ ix, 73 p. ]The RELAP5/MOD3.1 computer code is applied to the evaluation of performance of Secondary Condensers. The calculation of condensation heat transfer coefficients in RELAP5/MOD3.1 depends on the node size
Kim, Hyoung-Tae, 김형태
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, 2010 This is a M. Eng. degree project at Uppsala University carried out at the Forsmark nuclear power plant in Sweden. The purpose of it is to compare the two codes RELAP5 and TRACE during transient changes in mass flow against experiment.
Bjorklund, Karl
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