Simulation of boiling water reactor one-pump trip transient by SIMULATE-3K-Reference-Cited by-同舟云学术

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Simulation of boiling water reactor one-pump trip transient by SIMULATE-3K

Published:2013-11 Issue: Volume:264 Page:146-152
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Nozaki Kenichiro,Hotta Akithoshi,Kosaka Sinya,Suehiro Shoichi,Fujiwara Daisuke,Mizokami Sinya

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

Reference13 articles.

1. Atomic Energy Society of Japan, 2009. Standard method for safety evaluation using best estimate code based on uncertainty and scaling analyses with statistical approach. AESJ-SC-S001.

2. A three-dimensional transient analysis capability for SIMULATE-3;Borkowski;Trans. Am. Nucl. Soc.,1994

3. SIMULATE-3K: The Transient Analysis Module for the Studsvik CMS;Borkowski,1997

4. The RETRAN-3D code; pressurized water reactor multidimensional neutron kinetics applications;Gose;Nucl. Technol.,1998

5. Validation of the CASMO-4 transport solution;Knott,1986

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