This is a preview of subscription content, log in via an institution to check access.
References
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).
“Analysis of thermal behavior of two rods of precharacterized assembly 13624637 by code calculations,” Lo-2-K 919-0078 (1991).
LOVIISA-2. Fuel, Irradiation History of the Precharacterized Fuel Assembly 13624638 during the II-th Cycle 1990–1991, Lo-2-K 919-0094 (1991).
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.
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.
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.
Additional information
Russian Science Center “Kurchatov Institute.” Translated from Atomnaya Énergiya, Vol. 83, No. 3, pp. 159–164, September, 1997.
Rights and permissions
About this article
Cite this article
Tutnov, A.A., Tutnov, A.A., Dubrovin, K.P. et al. Comparison of experimental data and PULSAR-2 calculations for different fuel assemblies and reactors. At Energy 83, 627–632 (1997). https://doi.org/10.1007/BF02415242
Received:
Issue Date:
DOI: https://doi.org/10.1007/BF02415242