Comparison of experimental data and PULSAR-2 calculations for different fuel assemblies and reactors
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KeywordsExperimental Data Fuel Assembly
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- 1.A. A. Tutnov, An. A. Tutnov, and A. I. Ul'yanov, “Mathematical modeling of thermophysical and thermomechanical processes in reactor fuel elements,” At. Énerg.,76, No. 5, 411–417 (1994).Google Scholar
- 2.“Analysis of thermal behavior of two rods of precharacterized assembly 13624637 by code calculations,” Lo-2-K 919-0078 (1991).Google Scholar
- 3.LOVIISA-2. Fuel, Irradiation History of the Precharacterized Fuel Assembly 13624638 during the II-th Cycle 1990–1991, Lo-2-K 919-0094 (1991).Google Scholar
- 4.A. V. Smirnov, V. I. Kusmin, V. P. Smirnov, et al., “VVÉR-1000 and VVÉR-440 fuel operation experience,” in: Proceedings of International Topical Meeting on Light Water Reactor Fuel Performance,-USA, 1994, pp. 31–44.Google Scholar
- 5.A. Smirnov, V. Ivanov, A. Panyushkin, et al., “Experimental support of VVÉR-440 fuel reliability and serviceability at high burnup,” in: Proceedings of International Seminar on VVÉR Reactor: Fuel Performance, Modeling, and Experimental Support, Varna, Bulgaria, November 7–11, 1994, pp. 141–146.Google Scholar
- 6.P. Strijov, V. Yakovlev, K. Dubrovin, et al., “The improved version of the PIN code and its verification,” in: Technical Committee Meeting on Water Reactor Fuel Element Computer Modeling in Steady-State, Transient, and Accident Conditions, Preston, England, September 19–22, 1988.Google Scholar
© Plenum Publishing Corporation 1998