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Kyncl, Jan
On numerical solution to the problem of reactor kinetics with delayed neutrons by Monte Carlo method. (English). Applications of Mathematics, vol. 39 (1994), issue 4, pp. 269-286
MSC: 45K05, 65C05, 65R20, 82C70, 82C80 | MR 1284101 | Zbl 0812.65142
Keywords:
reactor kinetics; integral transport equation
Summary:

References:
[1] J. Mika, D. Obradovič, R. Stankiewicz: Spectral properties of a multigroup transport operator with delayed neutrons in plane geometry. Bulletin of the Boris Kidrič Institute of Nuclear Sciences 19 (1968).
[2] S. V. Shikhov: Problems of mathematical theory of reactors. Atomizdat, Moscow, 1973. (Russian)
[3] J. Kyncl: On Cauchy problem for the equations of reactor kinetics. Aplikace matematiky 34 (1989), 197–212. MR 0996896
[4] M. B. Emmett: The MORSE Monte Carlo Radiation Transport Code System. ORNL – 4972 (1975); also ORNL – 4972 – R1 (1983) and ORNL – 4972 – R2 (1984).
[5] M. Borysiewicz, J. Mika: Time behaviour of thermal neutrons in moderating media. J. Math. Anal. Appl 26 (1969), 461–478.
[6] M. M. R. Williams: The slowing down and thermalization of neutrons. North-Holland publishing company, Amsterdam, 1966.
[7] A. Weinberg and E. Winger: The Physical Theory of Neutron Chain Reactors. Chicago, 1958. MR 0113336
[8] G. V. Gnedenko: The theory of probability. Nauka, Moscow, 1973.
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