Thermal-hydraulic analysis of VVER-1000 residual heat removal system using RELAP5 code, an evaluation at the boundary of reactor repair mode-Reference-Cited by-同舟云学术

Thermal-hydraulic analysis of VVER-1000 residual heat removal system using RELAP5 code, an evaluation at the boundary of reactor repair mode

Published:2018-09 Issue:3 Volume:57 Page:1249-1259
ISSN:1110-0168
Container-title:Alexandria Engineering Journal
language:en
Short-container-title:Alexandria Engineering Journal

Author:

Tabadar Z.,Aghajanpour S.,Jabbari M.,Khaleghi M.,Hashemi-Tilehnoee M.

Publisher

Elsevier BV

Subject

General Engineering

Reference17 articles.

1. Research on the designed emergency passive residual heat removal system during the station blackout scenario for CPR1000;Wang;Ann. Nucl. Energy,2012

2. The comparison of designed water-cooled and air-cooled passive residual heat removal system for 300 MW nuclear power plant during the feed-water line break scenario;Wang;Ann. Nucl. Energy,2013

3. Analysis of the vent path through the pressurizer manway under the loss of residual heat removal (RHR) system during mid-loop operation in PWR;Ha;J. Kor. Nucl. Soc.,1995

4. Bushehr Final Safety Analysis Report (FSAR), Engineering Safety Features, 2005b (Chapter 6).

5. Analysis of the loss of heat sink transients in the secondary circuit of a VVER-1000 using RELAP5/MOD3.2;Abbasi;Ann. Nucl. Energy,2012

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