III. PWR steam generator response to a scram at 50% load and an open grid transient (bugey-4 nuclear power plant)-Reference-Cited by-同舟云学术

III. PWR steam generator response to a scram at 50% load and an open grid transient (bugey-4 nuclear power plant)

Published:1982-06 Issue:2 Volume:70 Page:173-186
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

de Penguern L.,David J.,Procaccia H.,Wazzan A.R.

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference12 articles.

1. Analysis of a PWR cooldown using RETRAN;Smith;Trans. Am. Nucl. Soc.,1981

2. RETRAN—a program for one-dimensional transient thermal-hydraulic analysis of complex fluid flow systems;Moore,1978

3. PWR transient pressurizer pressure behavior;Bonaca;Trans. Am. Nucl. Soc.,1981

4. The application of RETRAN-01 to assess the impact of hardware modifications on plant response to an SLR;Guimond;Trans. Am. Nucl. Soc.,1981

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