Analysis of cold leg small break LOCA for AP1000

Jiang Yang; Wen Xi Tian; Guang Hui Su; Sui Zheng Qiu

Analysis of cold leg small break LOCA for AP1000

Jiang Yang
, Wen Xi Tian
, Guang Hui Su
, Sui Zheng Qiu

能源与动力工程学院

Xi'an Jiaotong University

科研成果: 期刊稿件 › 文章 › 同行评审

9 引用（Scopus）

摘要

Based on the PWR best-estimate program RELAP5/MOD3.4, the reactor coolant system and the passive core cooling system of AP1000 were modeled and analyzed. Some key transient parameters were obtained, including RCS pressure, break discharge, cladding temperature, etc. The result is in close agreement with the result generated by NOTRUMP code from Westinghouse (USA). The calculation results show that safeguard system of AP1000 can effectively lower the temperature and reduce the pressure of the first loop, also can prevent core overheating. The safety of AP1000 during a small-break loss-of-coolant accident is verified.

源语言	英语
页（从-至）	541-547
页数	7
期刊	Yuanzineng Kexue Jishu/Atomic Energy Science and Technology
卷	45
期	5
出版状态	已出版 - 5月 2011

其它文件与链接

链接到 Scopus 的出版物

引用此

@article{48b647174fa5475a9c637b5a6337112b,

title = "Analysis of cold leg small break LOCA for AP1000",

abstract = "Based on the PWR best-estimate program RELAP5/MOD3.4, the reactor coolant system and the passive core cooling system of AP1000 were modeled and analyzed. Some key transient parameters were obtained, including RCS pressure, break discharge, cladding temperature, etc. The result is in close agreement with the result generated by NOTRUMP code from Westinghouse (USA). The calculation results show that safeguard system of AP1000 can effectively lower the temperature and reduce the pressure of the first loop, also can prevent core overheating. The safety of AP1000 during a small-break loss-of-coolant accident is verified.",

keywords = "AP1000, RELAP5, Small-break loss-of-coolant accident",

author = "Jiang Yang and Tian, \{Wen Xi\} and Su, \{Guang Hui\} and Qiu, \{Sui Zheng\}",

year = "2011",

month = may,

language = "英语",

volume = "45",

pages = "541--547",

journal = "Yuanzineng Kexue Jishu/Atomic Energy Science and Technology",

issn = "1000-6931",

publisher = "Atomic Energy Press",

number = "5",

}

TY - JOUR

T1 - Analysis of cold leg small break LOCA for AP1000

AU - Yang, Jiang

AU - Tian, Wen Xi

AU - Su, Guang Hui

AU - Qiu, Sui Zheng

PY - 2011/5

Y1 - 2011/5

N2 - Based on the PWR best-estimate program RELAP5/MOD3.4, the reactor coolant system and the passive core cooling system of AP1000 were modeled and analyzed. Some key transient parameters were obtained, including RCS pressure, break discharge, cladding temperature, etc. The result is in close agreement with the result generated by NOTRUMP code from Westinghouse (USA). The calculation results show that safeguard system of AP1000 can effectively lower the temperature and reduce the pressure of the first loop, also can prevent core overheating. The safety of AP1000 during a small-break loss-of-coolant accident is verified.

AB - Based on the PWR best-estimate program RELAP5/MOD3.4, the reactor coolant system and the passive core cooling system of AP1000 were modeled and analyzed. Some key transient parameters were obtained, including RCS pressure, break discharge, cladding temperature, etc. The result is in close agreement with the result generated by NOTRUMP code from Westinghouse (USA). The calculation results show that safeguard system of AP1000 can effectively lower the temperature and reduce the pressure of the first loop, also can prevent core overheating. The safety of AP1000 during a small-break loss-of-coolant accident is verified.

KW - AP1000

KW - RELAP5

KW - Small-break loss-of-coolant accident

UR - https://www.scopus.com/pages/publications/79959302408

M3 - 文章

AN - SCOPUS:79959302408

SN - 1000-6931

VL - 45

SP - 541

EP - 547

JO - Yuanzineng Kexue Jishu/Atomic Energy Science and Technology

JF - Yuanzineng Kexue Jishu/Atomic Energy Science and Technology

IS - 5

ER -

Analysis of cold leg small break LOCA for AP1000

摘要

其它文件与链接

学术指纹

引用此