On numerical solution to the problem of reactor kinetics with delayed neutrons by Monte Carlo method
Applications of Mathematics (1994)
- Volume: 39, Issue: 4, page 269-286
- ISSN: 0862-7940
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topKyncl, Jan. "On numerical solution to the problem of reactor kinetics with delayed neutrons by Monte Carlo method." Applications of Mathematics 39.4 (1994): 269-286. <http://eudml.org/doc/32883>.
@article{Kyncl1994,
abstract = {In this paper, the linear problem of reactor kinetics with delayed neutrons is studied whose formulation is based on the integral transport equation. Besides the proof of existence and uniqueness of the solution, a special random process and random variables for numerical elaboration of the problem by Monte Carlo method are presented. It is proved that these variables give an unbiased estimate of the solution and that their expectations and variances are finite.},
author = {Kyncl, Jan},
journal = {Applications of Mathematics},
keywords = {reactor kinetics; integral transport equation; Monte Carlo method; reactor kinetics; integral transport equation; Monte Carlo method},
language = {eng},
number = {4},
pages = {269-286},
publisher = {Institute of Mathematics, Academy of Sciences of the Czech Republic},
title = {On numerical solution to the problem of reactor kinetics with delayed neutrons by Monte Carlo method},
url = {http://eudml.org/doc/32883},
volume = {39},
year = {1994},
}
TY - JOUR
AU - Kyncl, Jan
TI - On numerical solution to the problem of reactor kinetics with delayed neutrons by Monte Carlo method
JO - Applications of Mathematics
PY - 1994
PB - Institute of Mathematics, Academy of Sciences of the Czech Republic
VL - 39
IS - 4
SP - 269
EP - 286
AB - In this paper, the linear problem of reactor kinetics with delayed neutrons is studied whose formulation is based on the integral transport equation. Besides the proof of existence and uniqueness of the solution, a special random process and random variables for numerical elaboration of the problem by Monte Carlo method are presented. It is proved that these variables give an unbiased estimate of the solution and that their expectations and variances are finite.
LA - eng
KW - reactor kinetics; integral transport equation; Monte Carlo method; reactor kinetics; integral transport equation; Monte Carlo method
UR - http://eudml.org/doc/32883
ER -
References
top- Spectral properties of a multigroup transport operator with delayed neutrons in plane geometry, Bulletin of the Boris Kidrič Institute of Nuclear Sciences 19 (1968). (1968)
- Problems of mathematical theory of reactors, Atomizdat, Moscow, 1973. (Russian) (1973)
- On Cauchy problem for the equations of reactor kinetics, Aplikace matematiky 34 (1989), 197–212. (1989) MR0996896
- The MORSE Monte Carlo Radiation Transport Code System, ORNL – 4972 (1975); also ORNL – 4972 – R1 (1983) and ORNL – 4972 – R2 (1984).
- 10.1016/0022-247X(69)90193-0, J. Math. Anal. Appl 26 (1969), 461–478. (1969) DOI10.1016/0022-247X(69)90193-0
- The slowing down and thermalization of neutrons, North-Holland publishing company, Amsterdam, 1966. (1966)
- The Physical Theory of Neutron Chain Reactors, Chicago, 1958. (1958) MR0113336
- The theory of probability, Nauka, Moscow, 1973. (1973)
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