PCTRAN-ABWR緊急爐心冷卻系統模式擴充

碩士 === 國立清華大學 === 工程與系統科學系 === 94 === The thesis focuses on the improvements and modifications of the PCTRAN-ABWR, a simulation code for the Lungmen Nuclear Power Plant, about the Emergency Core Cooling system (ECCS). The methodology to modify the PCTRAN-ABWR code and to improve its process flow an...

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Main Authors: Chen, Chun-Yu, 陳俊宇
Other Authors: 施純寬
Format: Others
Language:zh-TW
Published: 2006
Online Access:http://ndltd.ncl.edu.tw/handle/44712851513802119263
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spelling ndltd-TW-094NTHU55930382015-12-16T04:39:23Z http://ndltd.ncl.edu.tw/handle/44712851513802119263 PCTRAN-ABWR緊急爐心冷卻系統模式擴充 Chen, Chun-Yu 陳俊宇 碩士 國立清華大學 工程與系統科學系 94 The thesis focuses on the improvements and modifications of the PCTRAN-ABWR, a simulation code for the Lungmen Nuclear Power Plant, about the Emergency Core Cooling system (ECCS). The methodology to modify the PCTRAN-ABWR code and to improve its process flow and pressure model and the heat exchanger model can be examples for future modifications. The ECCS system includes of three subsystems, the Reactor Core Isolation Cooling subsystem, High Pressure Core Flooder subsystem and Residual Heat Removal subsystem. The approaches of the thesis are as followings: (1)Three independent divisions of ECCS are established. (2)The essential operation modes and interlock logics of ECCS system are improved. (3)The Thermal-Hydraulic relationships among the ECCS, the reactor core model and the containment are clarified. (4)The models for the process flow and pressure drop of ECCS are improved. (5)The RHR heat exchanger model is improved. As benchmarks of the ECCS modifications, the TRACG Benchmark Transient Analysis for the LUNGMEN Simulator Validation Project [1] and the SAFER/GESTR-Loss of Coolant Accident Analysis [2] are utilized. The discussions on the cases of LOCA and the impacts due to the delay of SCRAM time and the failure of the ECCS on the case of loss of all feedwater flow can be examples for future analysis. 施純寬 2006 學位論文 ; thesis 181 zh-TW
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description 碩士 === 國立清華大學 === 工程與系統科學系 === 94 === The thesis focuses on the improvements and modifications of the PCTRAN-ABWR, a simulation code for the Lungmen Nuclear Power Plant, about the Emergency Core Cooling system (ECCS). The methodology to modify the PCTRAN-ABWR code and to improve its process flow and pressure model and the heat exchanger model can be examples for future modifications. The ECCS system includes of three subsystems, the Reactor Core Isolation Cooling subsystem, High Pressure Core Flooder subsystem and Residual Heat Removal subsystem. The approaches of the thesis are as followings: (1)Three independent divisions of ECCS are established. (2)The essential operation modes and interlock logics of ECCS system are improved. (3)The Thermal-Hydraulic relationships among the ECCS, the reactor core model and the containment are clarified. (4)The models for the process flow and pressure drop of ECCS are improved. (5)The RHR heat exchanger model is improved. As benchmarks of the ECCS modifications, the TRACG Benchmark Transient Analysis for the LUNGMEN Simulator Validation Project [1] and the SAFER/GESTR-Loss of Coolant Accident Analysis [2] are utilized. The discussions on the cases of LOCA and the impacts due to the delay of SCRAM time and the failure of the ECCS on the case of loss of all feedwater flow can be examples for future analysis.
author2 施純寬
author_facet 施純寬
Chen, Chun-Yu
陳俊宇
author Chen, Chun-Yu
陳俊宇
spellingShingle Chen, Chun-Yu
陳俊宇
PCTRAN-ABWR緊急爐心冷卻系統模式擴充
author_sort Chen, Chun-Yu
title PCTRAN-ABWR緊急爐心冷卻系統模式擴充
title_short PCTRAN-ABWR緊急爐心冷卻系統模式擴充
title_full PCTRAN-ABWR緊急爐心冷卻系統模式擴充
title_fullStr PCTRAN-ABWR緊急爐心冷卻系統模式擴充
title_full_unstemmed PCTRAN-ABWR緊急爐心冷卻系統模式擴充
title_sort pctran-abwr緊急爐心冷卻系統模式擴充
publishDate 2006
url http://ndltd.ncl.edu.tw/handle/44712851513802119263
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