A MONTE CARLO STUDY OF THERMAL UTILIZATION FACTOR AND DIFFUSION AREA : GAS- COOLED GRAPHITE-MODERATED LATTICES

Author: Schaefer, G. W
Published: [Place of publication not identified] : [publisher not identified], 1959.
[Oak Ridge, Tennessee] : [U.S. Atomic Energy Commission], 1959.
Physical Description: microopaque : positive ; 8 x 13 cm
Additional Creators: Parkyn, D. M.

Availability

Finding items...

Summary

An attempt is made to explain the results from thermal flux in gas- cooled graphite-moderated uranium lattices experiments by solving the one-energy- group transport equation by the Monte Carlo method, using fundamental cross sections. The experiments of Campbell et al. and the theory of Amouyal et al. are compared with the Monte Carlo results. A survey of diffusion areas and asymmetries was carried out, using a number of mathematical models. The results are compared with theory and experiment. The survey is restricted to cylindrical fuel rods in circular channels and square pitches. (W.D.M.)

Report Numbers

A/CONF.15/P/310

Other Subject(s)

Collection

U.S. Atomic Energy Commission depository collection.

Note

NSA number: NSA-13-007227
OSTI Identifier 4262706
Research organization: English Electric Co., Ltd., Whetstone, Leics, Eng.

View MARC record | catkey: 38045745