Decay Heat Removal in GEN IV Gas-Cooled Fast Reactors

The safety goal of the current designs of advanced high-temperature thermal gas-cooled reactors (HTRs) is that no core meltdown would occur in a depressurization event with a combination of concurrent safety system failures. This study focused on the analysis of passive decay heat removal (DHR) in a...

Full description

Bibliographic Details
Main Authors: Lap-Yan Cheng, Thomas Y. C. Wei
Format: Article
Language:English
Published: Hindawi Limited 2009-01-01
Series:Science and Technology of Nuclear Installations
Online Access:http://dx.doi.org/10.1155/2009/797461
id doaj-be191c7f7e6149cda3fa2c4be6261098
record_format Article
spelling doaj-be191c7f7e6149cda3fa2c4be62610982020-11-24T22:37:18ZengHindawi LimitedScience and Technology of Nuclear Installations1687-60751687-60832009-01-01200910.1155/2009/797461797461Decay Heat Removal in GEN IV Gas-Cooled Fast ReactorsLap-Yan Cheng0Thomas Y. C. Wei1Brookhaven National Laboratory, Energy Sciences and Technology Department, P.O. Box 5000, Upton, NY 11973-5000, USAArgonne National Laboratory, Nuclear Engineering Division, 9700 S. Cass Avenue, Argonne, IL 60439, USAThe safety goal of the current designs of advanced high-temperature thermal gas-cooled reactors (HTRs) is that no core meltdown would occur in a depressurization event with a combination of concurrent safety system failures. This study focused on the analysis of passive decay heat removal (DHR) in a GEN IV direct-cycle gas-cooled fast reactor (GFR) which is based on the technology developments of the HTRs. Given the different criteria and design characteristics of the GFR, an approach different from that taken for the HTRs for passive DHR would have to be explored. Different design options based on maintaining core flow were evaluated by performing transient analysis of a depressurization accident using the system code RELAP5-3D. The study also reviewed the conceptual design of autonomous systems for shutdown decay heat removal and recommends that future work in this area should be focused on the potential for Brayton cycle DHRs.http://dx.doi.org/10.1155/2009/797461
collection DOAJ
language English
format Article
sources DOAJ
author Lap-Yan Cheng
Thomas Y. C. Wei
spellingShingle Lap-Yan Cheng
Thomas Y. C. Wei
Decay Heat Removal in GEN IV Gas-Cooled Fast Reactors
Science and Technology of Nuclear Installations
author_facet Lap-Yan Cheng
Thomas Y. C. Wei
author_sort Lap-Yan Cheng
title Decay Heat Removal in GEN IV Gas-Cooled Fast Reactors
title_short Decay Heat Removal in GEN IV Gas-Cooled Fast Reactors
title_full Decay Heat Removal in GEN IV Gas-Cooled Fast Reactors
title_fullStr Decay Heat Removal in GEN IV Gas-Cooled Fast Reactors
title_full_unstemmed Decay Heat Removal in GEN IV Gas-Cooled Fast Reactors
title_sort decay heat removal in gen iv gas-cooled fast reactors
publisher Hindawi Limited
series Science and Technology of Nuclear Installations
issn 1687-6075
1687-6083
publishDate 2009-01-01
description The safety goal of the current designs of advanced high-temperature thermal gas-cooled reactors (HTRs) is that no core meltdown would occur in a depressurization event with a combination of concurrent safety system failures. This study focused on the analysis of passive decay heat removal (DHR) in a GEN IV direct-cycle gas-cooled fast reactor (GFR) which is based on the technology developments of the HTRs. Given the different criteria and design characteristics of the GFR, an approach different from that taken for the HTRs for passive DHR would have to be explored. Different design options based on maintaining core flow were evaluated by performing transient analysis of a depressurization accident using the system code RELAP5-3D. The study also reviewed the conceptual design of autonomous systems for shutdown decay heat removal and recommends that future work in this area should be focused on the potential for Brayton cycle DHRs.
url http://dx.doi.org/10.1155/2009/797461
work_keys_str_mv AT lapyancheng decayheatremovalingenivgascooledfastreactors
AT thomasycwei decayheatremovalingenivgascooledfastreactors
_version_ 1725717586886262784