Neutron Behavior in Cluster-Type Fuel Lattices, (II)

Autor:	Kunitoshi Kurihara, Kazuko Yamamoto, Masayoshi Ishida, J. Tsunetaka Wajima, Kenichi Matsuoka
Rok vydání:	1972
Předmět:	Nuclear and High Energy Physics Uranium dioxide Nuclear data Computational physics Coolant Nuclear physics chemistry.chemical_compound Nuclear Energy and Engineering chemistry Neutron flux Lattice (order) Cluster (physics) Neutron Convection–diffusion equation
Zdroj:	Journal of Nuclear Science and Technology. 9:705-715
ISSN:	1881-1248 0022-3131
DOI:	10.1080/18811248.1972.9734930
Popis:	A multigroup method of calculation is presented for describing the neutron behavior in a cluster- type fuel lattice. It solves the integral transport equation by a semi-analytical method proposed in a previous paper for calculating collision probabilities in the lattice of a clustered fuel element. Using only fundamental nuclear data, it gives space and energy dependent neutron flux. The method has been programmed for HITAC-5020F (computer code named CLUSTER-N). The accuracy of the method has been tested by comparing the calculation with the experiment described in Part (I) of this paper. The lattices are 28-pin clusters of UO, or PuO,+UO, fuel pins, with heavy. or light-water moderators and with light-water coolant containing varying void ratios. The quantities studied are micro-parameters, reaction distributions in energy and space, thermal disadvantage factors and the multiplication factors. It is found that the calculated results are generally in good agreement with experiment, typically within 10%6 for micro-parameters and thermal disadvantage factor, and within 1% for the multiplication factor.
Databáze:	OpenAIRE
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