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reactor kinetics; integral transport equation; Monte Carlo method

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. DOI 10.1016/0022-247X(69)90193-0

[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.