Conclusions
We have described the basic features of the step-by-step method of obtaining the finite-difference equations describing the neutron distribution in a heterogeneous reactor.
It is proposed to devote further study to an analysis of the approximation to which the method should be limited in most actual situations, what further microdistributions of neutrons within a reactor cell should be found, and what accuracy is required in their calculation.
Similar content being viewed by others
Literature Cited
A. D. Kalanin, Thermal Reactor Theory, Pergamon, New York (1960).
A. Weinberg and E. Wigner, Physical Theory of Neutron Chain Reactors, Univ. Chicago (1958).
Ya. V. Shevelev, At. Energ.,2, 224 (1957).
L. Trlifai, At. Energ.,2, 231 (1957).
N. M. Laletin, in: Proceedings of the Second Geneva Conference,16, 601 (1958).
P. Benoist, J. Nucl. Energy,13, 97 (1961).
D. Leslie, J. Nucl. Energy,16, 1 (1962).
G. Ya. Rumyantsev, At. Energ.,13, 556 (1962).
V. V. Smelov, At. Energ.,6, 546 (1959).
V. D. Sidorenko, Kernenergie,12, 5 (1969).
I. S. Grigor'ev and V. M. Novikov, Diffusion of Neutrons in Heterogeneous Media [in Russian], Atomizdat, Moscow (1968).
R. Bonalumi, Energia Nucleare,18, 295 (1971).
S. S. Gorodkov, Preprint IAÉ-2251 (1973).
R. Bonalumi, Energia Nucleare,21, 231 (1974).
A. V. El'shin and N. I. Laletin, Preprint IAÉ-2721 (1976).
Yu. A. Anan'ev and G. A. Bogachev, Preprint IAÉ-2417 (1974).
N. V. Sultanov, Preprint IAÉ-2143, 2144 (1971).
N. I. Laletin, in: Problems of the Physics of Reactor Shielding [in Russian], Gosatomizdat, Moscow (1963).
Additional information
Translated from Atomnaya Énergiya, Vol. 43, No. 4, pp. 247–253, October, 1977.
Rights and permissions
About this article
Cite this article
Laletin, N.I., El'shin, A.V. Refinement of the method of homogenization of a heterogeneous reactor. At Energy 43, 879–886 (1977). https://doi.org/10.1007/BF01117990
Received:
Issue Date:
DOI: https://doi.org/10.1007/BF01117990