Preliminary Investigations of the Feasibility of In-Vessel Melt Retention Strategies for a Small Modular Reactor ConceptSource: Journal of Nuclear Engineering and Radiation Science:;2019:;volume( 005 ):;issue: 002::page 20905DOI: 10.1115/1.4042360Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: The study presented in this paper is part of the technological surveillance performed at the Electricité De France (EDF) Research and Development (R&D) Center, in the Pericles department, and investigates the feasibility of modeling in-vessel melt retention (IVMR) phenomena for small modular reactors (SMR) with the modular accident analysis program version 5 in its EDF proprietary version (MAAP5_EDF), applying conservative hypotheses, such as constant decay heat after corium relocation to the lower head. The study takes advantage of a corium stratification model in the lower head of the vessel, developed by EDF R&D for large-sized prospective pressurized water reactors (PWRs). The analysis is based on a stepwise approach in order to evaluate the impact of various effects during IVMR conditions. First, an analytical calculation is performed in order to establish a reference case to which the MAAP5_EDF code results are compared. In a second step, the impact of the lower head geometry, vessel steel ablation, and subsequent relocation on the heat flux has been analyzed for cases where heat dissipation through radiation is neglected (in first approximation). Finally, the impact of heat losses through radiation as well as the crust formation around the pool has been assessed. The results demonstrate the applicability of the MAAP5_EDF code to SMRs, with heat fluxes lower than 1.1 MW/m2 for relevant cases, and identify modeling improvements.
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contributor author | Andriolo, Lena | |
contributor author | Meriot, Clément | |
contributor author | Bakouta, Nikolai | |
date accessioned | 2019-06-08T09:29:01Z | |
date available | 2019-06-08T09:29:01Z | |
date copyright | 3/15/2019 12:00:00 AM | |
date issued | 2019 | |
identifier issn | 2332-8983 | |
identifier other | ners_005_02_020905.pdf | |
identifier uri | http://yetl.yabesh.ir/yetl1/handle/yetl/4257655 | |
description abstract | The study presented in this paper is part of the technological surveillance performed at the Electricité De France (EDF) Research and Development (R&D) Center, in the Pericles department, and investigates the feasibility of modeling in-vessel melt retention (IVMR) phenomena for small modular reactors (SMR) with the modular accident analysis program version 5 in its EDF proprietary version (MAAP5_EDF), applying conservative hypotheses, such as constant decay heat after corium relocation to the lower head. The study takes advantage of a corium stratification model in the lower head of the vessel, developed by EDF R&D for large-sized prospective pressurized water reactors (PWRs). The analysis is based on a stepwise approach in order to evaluate the impact of various effects during IVMR conditions. First, an analytical calculation is performed in order to establish a reference case to which the MAAP5_EDF code results are compared. In a second step, the impact of the lower head geometry, vessel steel ablation, and subsequent relocation on the heat flux has been analyzed for cases where heat dissipation through radiation is neglected (in first approximation). Finally, the impact of heat losses through radiation as well as the crust formation around the pool has been assessed. The results demonstrate the applicability of the MAAP5_EDF code to SMRs, with heat fluxes lower than 1.1 MW/m2 for relevant cases, and identify modeling improvements. | |
publisher | The American Society of Mechanical Engineers (ASME) | |
title | Preliminary Investigations of the Feasibility of In-Vessel Melt Retention Strategies for a Small Modular Reactor Concept | |
type | Journal Paper | |
journal volume | 5 | |
journal issue | 2 | |
journal title | Journal of Nuclear Engineering and Radiation Science | |
identifier doi | 10.1115/1.4042360 | |
journal fristpage | 20905 | |
journal lastpage | 020905-7 | |
tree | Journal of Nuclear Engineering and Radiation Science:;2019:;volume( 005 ):;issue: 002 | |
contenttype | Fulltext |