The Monte Carlo codes MCNP and MCU for RBMK criticality calculations

Nuclear Engineering and Design

Volumn 183, Issue 3, 1998, Pages 287-302

  Alexeev, N ^a   Behrens, D ^b,d   Davydova, G ^a   Donderer, R ^c   Von Ehrenstein, D ^b   Krayushkin, A ^a   Meyer, S ^c   Schumacher, O ^c  

^a KURCHATOV INSTITUTE   (Russian Federation)

^b UNIVERSITY OF BREMEN   (Germany)

^c Physics Consultants Bremen   (Germany)

^d c/o Physikerburo Bremen ^*  (Germany)

Author keywords

[No Author keywords available]

Indexed keywords

EID: 0010748688     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/s0029-5493(98)00163-0     Document Type: Article

References (10)

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2. Behrens, D., Donderer, R., von Ehrenstein, D., 1994. RBMK void reactivity effects. Final report. Kooperationsstelle 'Kerntechnik und Energie' an der Universität Bremen.
3. Behrens, D., Meyer, S., von Ehrenstein, D., 1996. Validation of MCNP for RBMK criticality calculations. Nucl. Technol. 114, 1-11.
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.
6. MacFarlane, R.E., Muir, D.W., 1993. The NJOY nuclear data processing system, version 91.0. Los Alamos National Laboratory, LA-12625.
7. RBMK Safety Review Project, 1994. Final report of topic group 3: core physics (Appendix 13 of RBMK/CMC/ FR) western topic group 3 members RBMK/CMC/FR, Issue 1, Vol. 4. RBMK/TG3/FR Issue 1.
8. Roshdestvensky, M.I., Davydov, V.K., Tocheny, L.V., 1989. Testrechnungen von zweidimensionalen Polygittern für RBMK-Reaktoren unter Benutzung der Monte-Carlo Methode. Research and Development Institute of Power Engineering (RDIPE), Moscow (German translation).
9. Sosedov, V.P. (Ed.), 1984. Properties of Carbon-based Structure Materials. Metallurgia, Moscow (in Russian).
10. Stenbock, I.A., Rhoshdestvensky, M.I., Podlazov, L.N., 1991. Methodology and code to calculate two-group macro cross-sections in RBMK reactor polycells. Research and Development Institute of Power Engineering (RDIPE), Moscow, ET-91/03.