Development of the "kristall" program system for design calculations of reactors

G. F. Liman, L. V. Maiorov, and M. S. Yudkevich., The MCU Program Package for Solving Problems of Radiation Transfer in Reactors with the Aid of the Monte-Carlo Method, Problems of Atomic Science and Technology, Series Physics and Technology of Nuclear Reactors [in Russian], No. 7, 27 (1985).Google Scholar

N. I. Laletin, On the Equation of the Heterogeneous Reactor, Problems of Atomic Science and Technology, Series Physcis and Technology of Nuclear Reactors [in Russian], No. 5(18), 31 (1981).Google Scholar

N. I. Laletin and A. V. El'shin, "Improving the Method of Homogenization of the Heterogeneous Reactor," At. Énerg.,43, No. 3, 247 (1975).Google Scholar

V. F. Tsibul'skii and V. S. Malkov, The Multigroup DOP Diffusion Program for Calculatting Neutron Fields in Two-Dimensional Reactors with Cavities, Problems of Atomic Science and Technology, Series Atom-Hydrogen Power Generation and Technology [in Russian], No. 3(16), 29 (1983).Google Scholar

G. V. Kompaniets, V. I. Nosov, and R. P. Petrushenko, Method and PNK Program for Calculating Reactors Containing Cylindrical Blocks, Making Use of Albedo-Type Boundary Conditions, Series Physics and Technology of Nuclear Reactors [in Russian], No. 4(33), 42 (1983).Google Scholar

G. I. Marchuk and V. I. Lebedev, Numerical Methods in the Theory of Neutron Transfer [in Russian], Atomizdat, Moscow (1981).Google Scholar

r. Schulten, "High-temperature gas-cooled reactors," in: Proc. Technical Committee Meeting Gas-Cooled Reactors and Their Applications, A2, October 20–23, 1986, Jülich, FRG.Google Scholar

I. S. Slesarev and A. M. Sirotkin, Variational-Difference Schemes in the Theory of Neutron Transfer [in Russian], Atomizdat, Moscow (1978).Google Scholar

N. I. Laletin, "Distribution of thermal neutrons in a cylindrical cell," in: Methods of Calculating the Fields of Thermal Neutrons in Reactor Grids [in Russian], Ya. V. Shevelev (ed.), Atomizdat, Moscow (1974), p. 205.Google Scholar