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Chuyanov, V. A. (1960) Multigroup analysis of an atomic power plant reactor on the “strela” high-speed electronic computer. The Soviet Journal of Atomic Energy, 7 (1) 584-585 doi:10.1007/bf01683113

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Reference TypeJournal (article/letter/editorial)
TitleMultigroup analysis of an atomic power plant reactor on the “strela” high-speed electronic computer
JournalThe Soviet Journal of Atomic Energy
AuthorsChuyanov, V. A.Author
Year1960 (December)Volume7
Issue1
PublisherSpringer Science and Business Media LLC
DOIdoi:10.1007/bf01683113
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Mindat Ref. ID12896522Long-form Identifiermindat:1:5:12896522:3
GUID0
Full ReferenceChuyanov, V. A. (1960) Multigroup analysis of an atomic power plant reactor on the “strela” high-speed electronic computer. The Soviet Journal of Atomic Energy, 7 (1) 584-585 doi:10.1007/bf01683113
Plain TextChuyanov, V. A. (1960) Multigroup analysis of an atomic power plant reactor on the “strela” high-speed electronic computer. The Soviet Journal of Atomic Energy, 7 (1) 584-585 doi:10.1007/bf01683113
In(1960, December) The Soviet Journal of Atomic Energy Vol. 7 (1) Springer Science and Business Media LLC

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Pavlov, V. I., Simonov, V. D. (1978) Optimization of the cyclical operating regime of an atomic power plant reactor. Soviet Atomic Energy, 44. 404 doi:10.1007/bf01124422
Marchuk, G. I. (1956) Multigroup method of calculations used in the design of the reactor for the atomic electric power station. The Soviet Journal of Atomic Energy, 1 (2) 149-161 doi:10.1007/bf01506927
Voronkov, A. V., Chuyanov, V. A. (1973) Optimization of reactor reactivity behavior by burnable poisons. Soviet Atomic Energy, 34. 243-244 doi:10.1007/bf01154846
Chakhovskii, V. M., Bereza, Yu. S. (1973) Mathematical model for the optimization of the parameters of the power section of an atomic electric power plant with a fast sodium reactor. Soviet Atomic Energy, 34. 476-477 doi:10.1007/bf01163746
Smelov, V. V. (1960) On an approximate method for the homogenization of a heterogeneous reactor. The Soviet Journal of Atomic Energy, 6 (5) 396-403 doi:10.1007/bf01491376
Yu K, (1960) The Latvian research reactor. The Soviet Journal of Atomic Energy, 7 (1) 600-601 doi:10.1007/bf01683123
Makhutov, N. A., Samoilov, O. B., Burak, M. I., Zhukov, V. V., Kaidalov, V. B. (1991) Satisfying flow criteria in the reactor vessel of an atomic power plant. Soviet Atomic Energy, 71. 728-733 doi:10.1007/bf01123792
V. R., (1956) Design of a portable power reactor. The Soviet Journal of Atomic Energy, 1 (1) 119-120 doi:10.1007/bf01516324
Khromov, V. V., Kuz'min, A. M. (1966) Effective method of performing multigroup reactor calculations. Soviet Atomic Energy, 21. 1095-1097 doi:10.1007/bf01162221
Sidorenko, V. A. (1973) Soviet ? Swedish Symposium on Atomic Power Plant Safety. Soviet Atomic Energy, 35. 697-698 doi:10.1007/bf01143089
Il'ina, L. I., Nazaryan, V. G., Postnikov, V. V., Yurkin, G. V. (1989) Analysis of an algorithm for optimizing the power distribution in the core of a high-power channel reactor. Soviet Atomic Energy, 66. 200-205 doi:10.1007/bf01123686
 
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