Thermal hydraulic transient study of 3MW TRIGA Mark-II research reactor of Bangladesh using the EUREKA-2/RR code-Reference-Cited by-同舟云学术

Thermal hydraulic transient study of 3MW TRIGA Mark-II research reactor of Bangladesh using the EUREKA-2/RR code

Published:2012-03 Issue: Volume:41 Page:40-47
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Badrun N.H.,Altaf M.H.,Khan M.J.H.,Mahmood M.S.,Motalab M.A.,Lyric Z.I.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference5 articles.

1. FSAR. 2006. Final Safety Analysis Report, Bangladesh Atomic Energy Commission.

2. Kaminaga, M., 2008. EUREKA-2/RR. A Computer Code for the Reactivity Accident Analyses in Research Reactors, Japan Atomic Energy Agency.

3. Kaminaga, M., 1991. Preliminary Reactivity Insertion Accidents Analysis of the Multi-Purpose Research Reactor RSG-GA Siwabessy Using EUREKA-2 Code, Japan Atomic Energy Research Institute, JAERI-memo, pp. 03–176.

4. Okumura, K., Kugo, T., Kaneko, K., Tsuchihashi, K., 2007. SRAC. A Comprehensive Neutronics Calculation Code System, Japan Atomic Energy Agency.

5. SAR. 2001. Safety Analysis Report, Bangladesh Atomic Energy Commission.

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