Sensitivity Analysis of Ultimate Response Guideline for Maanshan Nuclear Power Plant with PCTRAN

碩士 === 國立清華大學 === 核子工程與科學研究所 === 103 === After the Fukushima Nuclear Disaster took place in 2011, nuclear security have been attached importance to all over the world. Therefore the Ultimate Response Guideline(URG) was developed by Taiwan Power Company for preventing Taiwan from such analogous accid...

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Main Authors: Cheng,Chao,Che, 鄭肇哲
Other Authors: Pei,Bau,Shei
Format: Others
Language:zh-TW
Published: 2015
Online Access:http://ndltd.ncl.edu.tw/handle/53752990361563893552
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spelling ndltd-TW-103NTHU52650152016-08-15T04:17:32Z http://ndltd.ncl.edu.tw/handle/53752990361563893552 Sensitivity Analysis of Ultimate Response Guideline for Maanshan Nuclear Power Plant with PCTRAN PCTRAN模擬核三廠執行斷然處置 安全措施之靈敏度分析 Cheng,Chao,Che 鄭肇哲 碩士 國立清華大學 核子工程與科學研究所 103 After the Fukushima Nuclear Disaster took place in 2011, nuclear security have been attached importance to all over the world. Therefore the Ultimate Response Guideline(URG) was developed by Taiwan Power Company for preventing Taiwan from such analogous accident of nuclear power plant as in Japan. In order to test and verify the operating procedures of URG are able to make the nuclear power reactor shut down in emergencies and ensure security of the lives and property of the citizens, PCTRAN is used to simulate the operating procedures of URG of Maanshan Nuclear Power Plant in this paper, and the result of simulation is used to analyze the effect of URG that is according to the two maneuver-play of the plant in 2014. One of the play is for number one machine, it was in serious accident, the reactor part melted down, and the other one is for number two machine, that was not in serious accident, the power recover quickly. In the same timing of play, this study compares the result of PCTRAN with MAAP(Modular Accident Analysis Program) that is a validated software for simulating the accident of nuclear power plant and validates extent of accuracy of PCTRAN. The features of PCTRAN are fast simulating and easy operating, and the flow rate of components in the system is adjustable by user. As a result, the study analyzes the sensitivity of Power Operating Relief Valve(PORV) of Steam Generation, and the rate of the differential pressure and water loss with the aperture of PORV. Furthernore, at a fixed injection time, it also analyzes the deviation of the differential pressure of steam generation with the aperture of water flow. Pei,Bau,Shei Tseng,Yung,Shin 白寶實 曾永信 2015 學位論文 ; thesis 71 zh-TW
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description 碩士 === 國立清華大學 === 核子工程與科學研究所 === 103 === After the Fukushima Nuclear Disaster took place in 2011, nuclear security have been attached importance to all over the world. Therefore the Ultimate Response Guideline(URG) was developed by Taiwan Power Company for preventing Taiwan from such analogous accident of nuclear power plant as in Japan. In order to test and verify the operating procedures of URG are able to make the nuclear power reactor shut down in emergencies and ensure security of the lives and property of the citizens, PCTRAN is used to simulate the operating procedures of URG of Maanshan Nuclear Power Plant in this paper, and the result of simulation is used to analyze the effect of URG that is according to the two maneuver-play of the plant in 2014. One of the play is for number one machine, it was in serious accident, the reactor part melted down, and the other one is for number two machine, that was not in serious accident, the power recover quickly. In the same timing of play, this study compares the result of PCTRAN with MAAP(Modular Accident Analysis Program) that is a validated software for simulating the accident of nuclear power plant and validates extent of accuracy of PCTRAN. The features of PCTRAN are fast simulating and easy operating, and the flow rate of components in the system is adjustable by user. As a result, the study analyzes the sensitivity of Power Operating Relief Valve(PORV) of Steam Generation, and the rate of the differential pressure and water loss with the aperture of PORV. Furthernore, at a fixed injection time, it also analyzes the deviation of the differential pressure of steam generation with the aperture of water flow.
author2 Pei,Bau,Shei
author_facet Pei,Bau,Shei
Cheng,Chao,Che
鄭肇哲
author Cheng,Chao,Che
鄭肇哲
spellingShingle Cheng,Chao,Che
鄭肇哲
Sensitivity Analysis of Ultimate Response Guideline for Maanshan Nuclear Power Plant with PCTRAN
author_sort Cheng,Chao,Che
title Sensitivity Analysis of Ultimate Response Guideline for Maanshan Nuclear Power Plant with PCTRAN
title_short Sensitivity Analysis of Ultimate Response Guideline for Maanshan Nuclear Power Plant with PCTRAN
title_full Sensitivity Analysis of Ultimate Response Guideline for Maanshan Nuclear Power Plant with PCTRAN
title_fullStr Sensitivity Analysis of Ultimate Response Guideline for Maanshan Nuclear Power Plant with PCTRAN
title_full_unstemmed Sensitivity Analysis of Ultimate Response Guideline for Maanshan Nuclear Power Plant with PCTRAN
title_sort sensitivity analysis of ultimate response guideline for maanshan nuclear power plant with pctran
publishDate 2015
url http://ndltd.ncl.edu.tw/handle/53752990361563893552
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