A simulation of a steam generator tube rupture in a VVER-1000 plant-Reference-Cited by-同舟云学术

A simulation of a steam generator tube rupture in a VVER-1000 plant

Published:2008-07 Issue:7 Volume:49 Page:1972-1980
ISSN:0196-8904
Container-title:Energy Conversion and Management
language:en
Short-container-title:Energy Conversion and Management

Author:

Nematollahi M.R.,Zare A.

Publisher

Elsevier BV

Subject

Energy Engineering and Power Technology,Fuel Technology,Nuclear Energy and Engineering,Renewable Energy, Sustainability and the Environment

Reference4 articles.

1. Federal Agency on Nuclear Energy of Russia. Final safety analysis report for BNPP, chapter 15, accident analysis, book 4, Revision 0, Moscow; 2005.

2. Steam generator tube rupture (SGTR) scenarios;Auvinen;J Nucl Eng Des,2004

3. Kuroda T, Watanabe T. Break flow modeling for a steam generator tube rupture (SGTR) incident in a pressurized water reactor (PWR), Japan Atomic Energy Research Institute; 1993.

4. RELAP5/MOD3.2 investigation of primary-to-secondary reactor coolant leakage in VVER-440;Groudev;J Nucl Eng Des,2004

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