铅铋冷却沸水快堆热工水力系统安全分析程序开发

Shiying Wei; Chenglong Wang; Guanghui Su; Wenxi Tian; Suizheng Qiu

doi:10.13832/j.jnpe.2018.04.0067

铅铋冷却沸水快堆热工水力系统安全分析程序开发

Shiying Wei
, Chenglong Wang
, Guanghui Su
, Wenxi Tian
, Suizheng 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

2 引用（Scopus）

摘要

In this paper, mathematical models are established for PBWFR coolant system, and a system analysis code of PBWFR SACOL is developed. The steady-state and transient thermal-hydraulic performance of PBWFR is calculated and analyzed, especially the unprotected transient of over power. Results show that PBWFR is safe under steady state. However, during UTOP transient, the rapidly increasing of power in a short time would lead to cladding failure.

投稿的翻译标题	Development of Analysis Code for Pb-Bi Cooled Direct-Contact-Boiling Water Fast Reactor System
源语言	繁体中文
页（从-至）	67-70
页数	4
期刊	Hedongli Gongcheng/Nuclear Power Engineering
卷	39
期	4
DOI	https://doi.org/10.13832/j.jnpe.2018.04.0067
出版状态	已出版 - 15 8月 2018

关键词

Lead-bismuth reactor
Pb-Bi cooled direct-contact-boiling water fast reactor (PBWFR)
System safety
Thermal-hydraulics

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10.13832/j.jnpe.2018.04.0067

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链接到 Scopus 的出版物

引用此

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title = "铅铋冷却沸水快堆热工水力系统安全分析程序开发",

abstract = "In this paper, mathematical models are established for PBWFR coolant system, and a system analysis code of PBWFR SACOL is developed. The steady-state and transient thermal-hydraulic performance of PBWFR is calculated and analyzed, especially the unprotected transient of over power. Results show that PBWFR is safe under steady state. However, during UTOP transient, the rapidly increasing of power in a short time would lead to cladding failure.",

keywords = "Lead-bismuth reactor, Pb-Bi cooled direct-contact-boiling water fast reactor (PBWFR), System safety, Thermal-hydraulics",

author = "Shiying Wei and Chenglong Wang and Guanghui Su and Wenxi Tian and Suizheng Qiu",

year = "2018",

month = aug,

day = "15",

doi = "10.13832/j.jnpe.2018.04.0067",

language = "繁体中文",

volume = "39",

pages = "67--70",

journal = "Hedongli Gongcheng/Nuclear Power Engineering",

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publisher = "Atomic Energy Press",

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TY - JOUR

T1 - 铅铋冷却沸水快堆热工水力系统安全分析程序开发

AU - Wei, Shiying

AU - Wang, Chenglong

AU - Su, Guanghui

AU - Tian, Wenxi

AU - Qiu, Suizheng

PY - 2018/8/15

Y1 - 2018/8/15

N2 - In this paper, mathematical models are established for PBWFR coolant system, and a system analysis code of PBWFR SACOL is developed. The steady-state and transient thermal-hydraulic performance of PBWFR is calculated and analyzed, especially the unprotected transient of over power. Results show that PBWFR is safe under steady state. However, during UTOP transient, the rapidly increasing of power in a short time would lead to cladding failure.

AB - In this paper, mathematical models are established for PBWFR coolant system, and a system analysis code of PBWFR SACOL is developed. The steady-state and transient thermal-hydraulic performance of PBWFR is calculated and analyzed, especially the unprotected transient of over power. Results show that PBWFR is safe under steady state. However, during UTOP transient, the rapidly increasing of power in a short time would lead to cladding failure.

KW - Lead-bismuth reactor

KW - Pb-Bi cooled direct-contact-boiling water fast reactor (PBWFR)

KW - System safety

KW - Thermal-hydraulics

UR - https://www.scopus.com/pages/publications/85056634113

U2 - 10.13832/j.jnpe.2018.04.0067

DO - 10.13832/j.jnpe.2018.04.0067

M3 - 文章

AN - SCOPUS:85056634113

SN - 0258-0926

VL - 39

SP - 67

EP - 70

JO - Hedongli Gongcheng/Nuclear Power Engineering

JF - Hedongli Gongcheng/Nuclear Power Engineering

IS - 4

ER -

铅铋冷却沸水快堆热工水力系统安全分析程序开发

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