The Monte Carlo codes MCNP and MCU for RBMK criticality calculations-Reference-Cited by-同舟云学术

The Monte Carlo codes MCNP and MCU for RBMK criticality calculations

Published:1998-07 Issue:3 Volume:183 Page:287-302
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Alexeev N,Behrens D,Davydova G,Donderer R,von Ehrenstein D,Krayushkin A,Meyer S,Schumacher O

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

Reference10 articles.

1. Abagyan L., Alexeev, N., Bryzgalov, V., Glushkov, A., Gomin, E., Gurevich, M., Kalugin, M., Maiorov, L., Marin, S., Yudkevich, M., 1994. MCU Monte Carlo code for nuclear reactor calculations, verification. Russian Research Center ‘Kurchatov Institute’, Moscow, IAE-5751/5.

2. Behrens, D., Donderer, R., von Ehrenstein, D., 1994. RBMK void reactivity effects. Final report. Kooperationsstelle ‘Kerntechnik und Energie’ an der Universität Bremen.

3. Validation of MCNP for RBMK criticality calculations;Behrens;Nucl. Technol.,1996

4. Briesmeister, J.F., 1993. MCNP 4A-Monte Carlo n-particle transport code system. Los Alamos National Laboratory, LA-12625-M.

5. Kuzmin, A.N., 1993. Some experimental data obtained in the RBMK critical test facilitiy. Russian Research Center ‘Kurchatov Institute’, Moscow.

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