The Impact of SAG on the Level 2 PSA Results of the ChinShan Nuclear Power Plant
碩士 === 國立清華大學 === 工程與系統科學系 === 93 === Probability Safety Assessment (PSA) is a systematic approach to estimate the risk of nuclear power plants (NPPs). PSA has been widely utilized by nuclear utilities, nuclear industry, and nuclear regulators to enhance the safety of NPPs. Over the past few years,...
Main Authors: | , |
---|---|
Other Authors: | |
Format: | Others |
Language: | zh-TW |
Published: |
2005
|
Online Access: | http://ndltd.ncl.edu.tw/handle/98977122217331435692 |
id |
ndltd-TW-093NTHU5593043 |
---|---|
record_format |
oai_dc |
spelling |
ndltd-TW-093NTHU55930432016-06-06T04:11:34Z http://ndltd.ncl.edu.tw/handle/98977122217331435692 The Impact of SAG on the Level 2 PSA Results of the ChinShan Nuclear Power Plant 嚴重事故處理指引對核一廠二階安全度評估結果的影響 Kuan-Fu Chen 陳冠甫 碩士 國立清華大學 工程與系統科學系 93 Probability Safety Assessment (PSA) is a systematic approach to estimate the risk of nuclear power plants (NPPs). PSA has been widely utilized by nuclear utilities, nuclear industry, and nuclear regulators to enhance the safety of NPPs. Over the past few years, Severe Accident Guidelines (SAGs), which delineate the mitigation actions of core meltdown accidents of NPP, are developed to support operators and staffs in the Technical Support Center (TSC) during the emergency responses of core melt accidents. The proper executions of SAGs could decrease the failure probability of containment and reduce the amount of radionuclide released to the environment during the accident. It can be expected that the implementation of SAGs will reduce the risk of the operation of NPPs. However, SAGs are not available when the conventional Level-2 PSA analyses are performed. In this study the mitigation actions of SAGs are incorporated into the Level-2 PSA of a General Electric designed Boiling Water Reactor (BWR) with Mark I containment. The plant analyzed is ChinShan Nuclear Power Plant of Taiwan Power Company (TPC). The purposes of the study are to assess the impact of SAGs on the risk of NPP and to identify the importance measure of these mitigation actions. MAAP code calculations are performed to verify and validate the mitigation actions specified in SAGs. This thesis summarizes the results of the study. Min Lee 李敏 2005 學位論文 ; thesis 157 zh-TW |
collection |
NDLTD |
language |
zh-TW |
format |
Others
|
sources |
NDLTD |
description |
碩士 === 國立清華大學 === 工程與系統科學系 === 93 === Probability Safety Assessment (PSA) is a systematic approach to estimate the risk of nuclear power plants (NPPs). PSA has been widely utilized by nuclear utilities, nuclear industry, and nuclear regulators to enhance the safety of NPPs. Over the past few years, Severe Accident Guidelines (SAGs), which delineate the mitigation actions of core meltdown accidents of NPP, are developed to support operators and staffs in the Technical Support Center (TSC) during the emergency responses of core melt accidents. The proper executions of SAGs could decrease the failure probability of containment and reduce the amount of radionuclide released to the environment during the accident. It can be expected that the implementation of SAGs will reduce the risk of the operation of NPPs. However, SAGs are not available when the conventional Level-2 PSA analyses are performed. In this study the mitigation actions of SAGs are incorporated into the Level-2 PSA of a General Electric designed Boiling Water Reactor (BWR) with Mark I containment. The plant analyzed is ChinShan Nuclear Power Plant of Taiwan Power Company (TPC).
The purposes of the study are to assess the impact of SAGs on the risk of NPP and to identify the importance measure of these mitigation actions. MAAP code calculations are performed to verify and validate the mitigation actions specified in SAGs. This thesis summarizes the results of the study.
|
author2 |
Min Lee |
author_facet |
Min Lee Kuan-Fu Chen 陳冠甫 |
author |
Kuan-Fu Chen 陳冠甫 |
spellingShingle |
Kuan-Fu Chen 陳冠甫 The Impact of SAG on the Level 2 PSA Results of the ChinShan Nuclear Power Plant |
author_sort |
Kuan-Fu Chen |
title |
The Impact of SAG on the Level 2 PSA Results of the ChinShan Nuclear Power Plant |
title_short |
The Impact of SAG on the Level 2 PSA Results of the ChinShan Nuclear Power Plant |
title_full |
The Impact of SAG on the Level 2 PSA Results of the ChinShan Nuclear Power Plant |
title_fullStr |
The Impact of SAG on the Level 2 PSA Results of the ChinShan Nuclear Power Plant |
title_full_unstemmed |
The Impact of SAG on the Level 2 PSA Results of the ChinShan Nuclear Power Plant |
title_sort |
impact of sag on the level 2 psa results of the chinshan nuclear power plant |
publishDate |
2005 |
url |
http://ndltd.ncl.edu.tw/handle/98977122217331435692 |
work_keys_str_mv |
AT kuanfuchen theimpactofsagonthelevel2psaresultsofthechinshannuclearpowerplant AT chénguānfǔ theimpactofsagonthelevel2psaresultsofthechinshannuclearpowerplant AT kuanfuchen yánzhòngshìgùchùlǐzhǐyǐnduìhéyīchǎngèrjiēānquándùpínggūjiéguǒdeyǐngxiǎng AT chénguānfǔ yánzhòngshìgùchùlǐzhǐyǐnduìhéyīchǎngèrjiēānquándùpínggūjiéguǒdeyǐngxiǎng AT kuanfuchen impactofsagonthelevel2psaresultsofthechinshannuclearpowerplant AT chénguānfǔ impactofsagonthelevel2psaresultsofthechinshannuclearpowerplant |
_version_ |
1718296480590069760 |