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contributor authorMadokoro, Hiroshi
contributor authorMiassoedov, Alexei
contributor authorSchulenberg, Thomas
date accessioned2019-03-17T09:41:58Z
date available2019-03-17T09:41:58Z
date copyright1/24/2019 12:00:00 AM
date issued2019
identifier issn2332-8983
identifier otherners_005_01_011017.pdf
identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4255626
description abstractDue 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.
publisherThe American Society of Mechanical Engineers (ASME)
titleCoupling of a Reactor Analysis Code and a Lower Head Thermal Analysis Solver
typeJournal Paper
journal volume5
journal issue1
journal titleJournal of Nuclear Engineering and Radiation Science
identifier doi10.1115/1.4041278
journal fristpage11017
journal lastpage011017-9
treeJournal of Nuclear Engineering and Radiation Science:;2019:;volume( 005 ):;issue: 001
contenttypeFulltext


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