Coupled neutronic thermal–hydraulic transient analysis of accidents in PWRs-Reference-Cited by-同舟云学术

Coupled neutronic thermal–hydraulic transient analysis of accidents in PWRs

Published:2012-12 Issue: Volume:50 Page:158-166
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Aghaie M.,Zolfaghari A.,Minuchehr A.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference31 articles.

1. A general description of lattice code WIMSD4;Askew;J. Br. Nucl. Energy Soc.,1966

2. Borkowski, J.A., Wade, N.L., 1992. TRAC-BF1: An Advanced Best-Estimate Computer Program for BWR Accident Analysis: Model Description, vol. 1. NUREG: CR-4356, EGG-2626.

3. Axial offset control of PWR nuclear reactor core using intelligent techniques;Boroushaki;Nucl. Eng. Des.,2004

4. PARCS n2.7 US NRC Core Neutronics Simulator;Downar,2006

5. Citation-LDI2 Nuclear Reactor Core Analysis System. CCC-643;Fowler,1999

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