An Integrated RELAP5-3D and Multiphase CFD Code System Utilizing a Semi Implicit Coupling Technique [PDF]
, 2001 An integrated code system consisting of RELAP5-3D and a multiphase CFD program has been created through the use of a generic semi-implicit coupling algorithm.
Aumiller, D. L. +2 more
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Analysis of natural circulation characteristics for pool-type fast reactor system
International Journal of Advanced Nuclear Reactor Design and TechnologyIn the inherent safety design of the pool-type fast reactor, when the normal heat transfer routine of the primary system is lost during accident conditions, the residual heat of the reactor core is transferred to the ultimate heat sink through the ...
Yufeng Lv, Zhiwei Zhou, Xingmin Liu
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AN INTEGRATED RELAP5-3D AND MUTLIPHASE CFD CODE SYSTEM UTILIZING A SEMI-implicit coupling technique [PDF]
, 2001 An integrated code system consisting of RELAP5-3D and a multiphase CFD program has been created through the use of a generic semi-implicit coupling algorithm.
Aumiller, D.L., Tomlinson, E.T., and Weaver, W.L.
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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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Steam generator identification using piecewise affine model
Results in Nonlinear Analysis, 2019 The role of steam generators in power plants is to remove the thermal power produced in the first cycle and provide the turbine intake steam. Controlling the steam generator water level has an important role in preventing unwanted turbine trips and ...
Samaneh Sadat Sajjadi, Amin Jajarmi, Ahamad Hajipour
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Recent Improvements To The RELAP5-3D Code [PDF]
, 2006 The RELAP5-3D computer program has been recently improved. Changes were made as follows: (1) heat structures are allowed to be decoupled from hydrodynamic components, (2) built-in material properties for heat structures have been made consistent with ...
Riemke, Richard A. +2 more
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Standard problem for RELAP5 code validation for VVER-440 reactor unit
, 2006 Изложены результаты реализации стандартной проблемы для валидации расчетного кода RELAP5 на базе документальных данных аварии с течью из первого контура во второй на энергоблоке с реактором типа ВВЭР-440.
Борисенко, В.И. +2 more
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Analysis of VVER-1000 natural circulation regime for RELAP5 code validation standard problem
, 2011 Изложены основные результаты валидации расчетного кода RELAP5 в рамках международного сотрудничества специалистов Украины и Болгарии при реализации стандартной проблемы для ВВЭР-1000 энергоблока № 6 АЭС «Козлодуй». Приведен сравнительный анализ расчетных
Борисенко, В.И. +4 more
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Quantification of Uncertainty of Reflood-Related Models of RELAP5 MOD3.3 Code
, 2014 Best-Estimate plus Uncertainty Evaluation methods are gaining increased interest in the licensing process. Besides, lessons learnt from the BEMUSE benchmark and others show that deeper understanding of some present methods is necessary, especially in ...
Kovtonyuk A., D’Auria F., Petruzzi A.
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Independent code assessment at BNL in FY 1982. [TRAC-PF1; RELAP5/MOD1; TRAC-BD1]
, 1982 Independent assessment of the advanced codes such as TRAC and RELAP5 has continued at BNL through the Fiscal Year 1982. The simulation tests can be grouped into the following five categories: critical flow, counter-current flow limiting (CCFL) or ...
Neymotin, L. +5 more
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