The Establishment of Thermal Hydraulic Model for Kuosheng Nuclear Power Plant’s Mark-III Containment

碩士 === 國立清華大學 === 核子工程與科學研究所 === 99 === ABSTRACT The loss of coolant accident (LOCA) is an important issue of design basis accidents (DBA) because it will cause the failure of containment. This thesis has focused on the investigation of the main steam line break and recirculation line break (Dou...

Full description

Bibliographic Details
Main Authors: Peng, Po-Hao, 彭柏皓
Other Authors: Pei, Bau-Shei
Format: Others
Language:zh-TW
Published: 2011
Online Access:http://ndltd.ncl.edu.tw/handle/99702473470983142187
id ndltd-TW-099NTHU5265005
record_format oai_dc
spelling ndltd-TW-099NTHU52650052015-10-13T20:04:06Z http://ndltd.ncl.edu.tw/handle/99702473470983142187 The Establishment of Thermal Hydraulic Model for Kuosheng Nuclear Power Plant’s Mark-III Containment 核能二廠Mark-III圍阻體熱水流分析模式建立 Peng, Po-Hao 彭柏皓 碩士 國立清華大學 核子工程與科學研究所 99 ABSTRACT The loss of coolant accident (LOCA) is an important issue of design basis accidents (DBA) because it will cause the failure of containment. This thesis has focused on the investigation of the main steam line break and recirculation line break (Double ended guillotine) for the Mark-III containment to ensure that the containment must withstand the peak values of pressure and temperature loadings as an accident impact occurs. We have utilized GOTHIC program to establish the short-term and long-term analysis models respectively. For the short-term analysis model, we have adopted the blowdown mass and energy release data offered from final safety analysis report (FSAR) to build up the boundary condition. For the long-term analysis model, we have joined the RPV and ECCS models with the homogeneous equilibrium critical flow model to calculate the value of blowdown rate. Furthermore, given in more confident and crucial, the short-term analysis model and the long-term analysis model of the conditions have been assumed to be different, in which the initial water level of suppression pool is higher for the short-term one but lower for the long-term one. As a result, the simulated data have been compared to the data of FSAR, and we will analysis and specify the reasonableness and corrections of the results. In conclusions, the given results from this work are consistent with the data of FSAR dependent on time. More importantly, the peak value of the temperature and pressure for this accident is much lower than the designed safe value so the containment will be safe and sound when a single accident event occurs. Key words:GOTHIC、Mark-III、Containment、LOCA、DBA Pei, Bau-Shei Shih, Chun-Kuan Chen, Yen-Shu 白寶實 施純寬 陳彥旭 2011 學位論文 ; thesis 68 zh-TW
collection NDLTD
language zh-TW
format Others
sources NDLTD
description 碩士 === 國立清華大學 === 核子工程與科學研究所 === 99 === ABSTRACT The loss of coolant accident (LOCA) is an important issue of design basis accidents (DBA) because it will cause the failure of containment. This thesis has focused on the investigation of the main steam line break and recirculation line break (Double ended guillotine) for the Mark-III containment to ensure that the containment must withstand the peak values of pressure and temperature loadings as an accident impact occurs. We have utilized GOTHIC program to establish the short-term and long-term analysis models respectively. For the short-term analysis model, we have adopted the blowdown mass and energy release data offered from final safety analysis report (FSAR) to build up the boundary condition. For the long-term analysis model, we have joined the RPV and ECCS models with the homogeneous equilibrium critical flow model to calculate the value of blowdown rate. Furthermore, given in more confident and crucial, the short-term analysis model and the long-term analysis model of the conditions have been assumed to be different, in which the initial water level of suppression pool is higher for the short-term one but lower for the long-term one. As a result, the simulated data have been compared to the data of FSAR, and we will analysis and specify the reasonableness and corrections of the results. In conclusions, the given results from this work are consistent with the data of FSAR dependent on time. More importantly, the peak value of the temperature and pressure for this accident is much lower than the designed safe value so the containment will be safe and sound when a single accident event occurs. Key words:GOTHIC、Mark-III、Containment、LOCA、DBA
author2 Pei, Bau-Shei
author_facet Pei, Bau-Shei
Peng, Po-Hao
彭柏皓
author Peng, Po-Hao
彭柏皓
spellingShingle Peng, Po-Hao
彭柏皓
The Establishment of Thermal Hydraulic Model for Kuosheng Nuclear Power Plant’s Mark-III Containment
author_sort Peng, Po-Hao
title The Establishment of Thermal Hydraulic Model for Kuosheng Nuclear Power Plant’s Mark-III Containment
title_short The Establishment of Thermal Hydraulic Model for Kuosheng Nuclear Power Plant’s Mark-III Containment
title_full The Establishment of Thermal Hydraulic Model for Kuosheng Nuclear Power Plant’s Mark-III Containment
title_fullStr The Establishment of Thermal Hydraulic Model for Kuosheng Nuclear Power Plant’s Mark-III Containment
title_full_unstemmed The Establishment of Thermal Hydraulic Model for Kuosheng Nuclear Power Plant’s Mark-III Containment
title_sort establishment of thermal hydraulic model for kuosheng nuclear power plant’s mark-iii containment
publishDate 2011
url http://ndltd.ncl.edu.tw/handle/99702473470983142187
work_keys_str_mv AT pengpohao theestablishmentofthermalhydraulicmodelforkuoshengnuclearpowerplantsmarkiiicontainment
AT péngbǎihào theestablishmentofthermalhydraulicmodelforkuoshengnuclearpowerplantsmarkiiicontainment
AT pengpohao hénéngèrchǎngmarkiiiwéizǔtǐrèshuǐliúfēnxīmóshìjiànlì
AT péngbǎihào hénéngèrchǎngmarkiiiwéizǔtǐrèshuǐliúfēnxīmóshìjiànlì
AT pengpohao establishmentofthermalhydraulicmodelforkuoshengnuclearpowerplantsmarkiiicontainment
AT péngbǎihào establishmentofthermalhydraulicmodelforkuoshengnuclearpowerplantsmarkiiicontainment
_version_ 1718043842473623552