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

Translated title of the contribution: Development of Analysis Code for Pb-Bi Cooled Direct-Contact-Boiling Water Fast Reactor System

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

School of Energy and Power Engineering

Xi'an Jiaotong University

Research output: Contribution to journal › Article › peer-review

2 Scopus citations

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.

Translated title of the contribution	Development of Analysis Code for Pb-Bi Cooled Direct-Contact-Boiling Water Fast Reactor System
Original language	Chinese (Traditional)
Pages (from-to)	67-70
Number of pages	4
Journal	Hedongli Gongcheng/Nuclear Power Engineering
Volume	39
Issue number	4
DOIs	https://doi.org/10.13832/j.jnpe.2018.04.0067
State	Published - 15 Aug 2018

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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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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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