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Post-experiment analysis of natural circulation for Qinshan Nuclear Power Plant

Technical Report:

Abstract

The natural circulation ability of PWR (pressurized water reactor) coolant system is one of inherent safeties of this kind NPP (nuclear power plant). According to the procedures and measured parameters of the natural circulation testing in Qinshan NPP, a LWR transient analysis code RETRAN-02 was used to simulate and calculate the ability of natural cooling circulation under different reactor power. For evaluating the reliability of experimental results and the impact of equipment parameters on the calculation, the comparison of pre-experiment analysis, post-experiment analysis and experimental results is completed.
Authors:
Zhujiang, Zhang; [1]  Shoulu, Xu [2] 
  1. Research Inst. of Nuclear Power Operation, Wuhan (China)
  2. Shanghai Nuclear Engineering Research and Development Inst., SH (China)
Publication Date:
Dec 01, 1992
Product Type:
Technical Report
Report Number:
CNIC-00695; RINPO-0010.
Reference Number:
SCA: 210200; PA: AIX-25:003313; EDB-94:012309; ERA-19:003555; NTS-94:014074; SN: 93001120599
Resource Relation:
Other Information: PBD: Dec 1992
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; NATURAL CONVECTION; CALCULATION METHODS; QINSHAN REACTOR; DATA PROCESSING; ERRORS; EXPERIMENTAL DATA; NUCLEAR POWER PLANTS; R CODES; SAFETY; TRANSIENTS; 210200; POWER REACTORS, NONBREEDING, LIGHT-WATER MODERATED, NONBOILING WATER COOLED
OSTI ID:
10109646
Research Organizations:
China Nuclear Information Centre, Beijing, BJ (China)
Country of Origin:
China
Language:
Chinese
Other Identifying Numbers:
Other: ON: DE94609258; ISBN 7-5022-0808-9; TRN: CN9301217003313
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
INIS
Size:
10 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Zhujiang, Zhang, and Shoulu, Xu. Post-experiment analysis of natural circulation for Qinshan Nuclear Power Plant. China: N. p., 1992. Web.
Zhujiang, Zhang, & Shoulu, Xu. Post-experiment analysis of natural circulation for Qinshan Nuclear Power Plant. China.
Zhujiang, Zhang, and Shoulu, Xu. 1992. "Post-experiment analysis of natural circulation for Qinshan Nuclear Power Plant." China.
@misc{etde_10109646,
title = {Post-experiment analysis of natural circulation for Qinshan Nuclear Power Plant}
author = {Zhujiang, Zhang, and Shoulu, Xu}
abstractNote = {The natural circulation ability of PWR (pressurized water reactor) coolant system is one of inherent safeties of this kind NPP (nuclear power plant). According to the procedures and measured parameters of the natural circulation testing in Qinshan NPP, a LWR transient analysis code RETRAN-02 was used to simulate and calculate the ability of natural cooling circulation under different reactor power. For evaluating the reliability of experimental results and the impact of equipment parameters on the calculation, the comparison of pre-experiment analysis, post-experiment analysis and experimental results is completed.}
place = {China}
year = {1992}
month = {Dec}
}