Coupling of a Reactor Analysis Code and a Lower Head Thermal Analysis SolverSource: Journal of Nuclear Engineering and Radiation Science:;2019:;volume( 005 ):;issue: 001::page 11017DOI: 10.1115/1.4041278Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: Due to the recent high interest on in-vessel melt retention (IVR), development of detailed thermal and structural analysis tool, which can be used in a core-melt severe accident, is inevitable. Although RELAP/SCDAPSIM is a reactor analysis code, originally developed for U.S. NRC, which is still widely used for severe accident analysis, the modeling of the lower head is rather simple, considering only a homogeneous pool. PECM/S, a thermal structural analysis solver for the reactor pressure vessel (RPV) lower head, has a capability of predicting molten pool heat transfer as well as detailed mechanical behavior including creep, plasticity, and material damage. The boundary condition, however, needs to be given manually and thus the application of the stand-alone PECM/S to reactor analyses is limited. By coupling these codes, the strength of both codes can be fully utilized. Coupled analysis is realized through a message passing interface, OpenMPI. The validation simulations have been performed using LIVE test series and the calculation results are compared not only with the measured values but also with the results of stand-alone RELAP/SCDAPSIM simulations.
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contributor author | Madokoro, Hiroshi | |
contributor author | Miassoedov, Alexei | |
contributor author | Schulenberg, Thomas | |
date accessioned | 2019-03-17T09:41:58Z | |
date available | 2019-03-17T09:41:58Z | |
date copyright | 1/24/2019 12:00:00 AM | |
date issued | 2019 | |
identifier issn | 2332-8983 | |
identifier other | ners_005_01_011017.pdf | |
identifier uri | http://yetl.yabesh.ir/yetl1/handle/yetl/4255626 | |
description abstract | Due to the recent high interest on in-vessel melt retention (IVR), development of detailed thermal and structural analysis tool, which can be used in a core-melt severe accident, is inevitable. Although RELAP/SCDAPSIM is a reactor analysis code, originally developed for U.S. NRC, which is still widely used for severe accident analysis, the modeling of the lower head is rather simple, considering only a homogeneous pool. PECM/S, a thermal structural analysis solver for the reactor pressure vessel (RPV) lower head, has a capability of predicting molten pool heat transfer as well as detailed mechanical behavior including creep, plasticity, and material damage. The boundary condition, however, needs to be given manually and thus the application of the stand-alone PECM/S to reactor analyses is limited. By coupling these codes, the strength of both codes can be fully utilized. Coupled analysis is realized through a message passing interface, OpenMPI. The validation simulations have been performed using LIVE test series and the calculation results are compared not only with the measured values but also with the results of stand-alone RELAP/SCDAPSIM simulations. | |
publisher | The American Society of Mechanical Engineers (ASME) | |
title | Coupling of a Reactor Analysis Code and a Lower Head Thermal Analysis Solver | |
type | Journal Paper | |
journal volume | 5 | |
journal issue | 1 | |
journal title | Journal of Nuclear Engineering and Radiation Science | |
identifier doi | 10.1115/1.4041278 | |
journal fristpage | 11017 | |
journal lastpage | 011017-9 | |
tree | Journal of Nuclear Engineering and Radiation Science:;2019:;volume( 005 ):;issue: 001 | |
contenttype | Fulltext |