References
A. I. Klemin, L. N. Polyanin, and M. M. Strigulin,Thermohydraulic Calculations and Heat-Engineering Reliability of Nuclear Reactors [in Russian], Atomizdat, Moscow (1980).
A. I. Klemin and M. M. Strigulin,Some Questions of the Reliability of Nuclear Reactors [in Russian], Atomizdat, Moscow (1968).
“APDA introduces statistical hot-spot factors,”Nucleonics, No. 8 (1959).
A. I. Klemin and E. F. Polyakov, “Probability methods in thermohydraulic calculations for reactors,”At. Tekh. za Rubezh., No. 10 (1970).
H. J. Reilly, J. D. Hansell, and G. L. Health, “Treatment of uncertainties in reactor heat transfer calculations,”Nucl. Sci. Eng.,38 (1969).
“Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants,”Report No. NUREG-0800, U.S. Nuclear Regulatory Commission (June 1987).
“Advanced Neutron Source (ANS),”Progress Report No. FY 1991, Oak Ridge National Laboratory, U.S.A.
N. A. Grosheva, G. A. Kirsanov, K. A. Konoplev, and D. V. Chmshkyan, “Statistical method for calculating the maximum permissible power of a VVR-M reactor,”Preprint No. PIYaF-2228 [in Russian] (1998).
N. A. Grosheva, G. A. Kirsanov, K. A. Konoplev, and D. V. Chmshkyan, “Calculation of safety factors for PIK reactor power using a statistical method,” in:Physics and Technology of Reactors [in Russian], St. Petersburg (1996).
L. G. Dedenko and V. V. Kerzhentsev,Mathematical Processing and Formulation of Experimental Results [in Russian], State University, Moscow (1977).
Additional information
Institute of Nuclear Physics, St. Petersburg, Russian Academy of Sciences. Translated from Atomnaya Énergiya, Vol. 85, No. 6, pp. 433–436, December, 1998.
Rights and permissions
About this article
Cite this article
Grosheva, N.A., Kirsanov, G.A., Konoplev, K.A. et al. Statistical method of calculating the maximum permissible power of a nuclear research reactor. At Energy 85, 860–862 (1998). https://doi.org/10.1007/BF02361114
Received:
Issue Date:
DOI: https://doi.org/10.1007/BF02361114