You need JavaScript to view this

A New Method for Predicting the Penetration and Slowing-Down of Neutrons in Reactor Shields

Abstract

A new approach is presented in the formulation of removal-diffusion theory. The 'removal cross-section' is redefined and the slowing-down between the multigroup diffusion equations is treated with a complete energy transfer matrix rather than in an age theory approximation. The method, based on the new approach contains an adjustable parameter. Examples of neutron spectra and thermal flux penetrations are given in a number of differing shield configurations and the results compare favorably with experiments and Moments Method calculations.
Publication Date:
May 15, 1965
Product Type:
Technical Report
Report Number:
AE-185
Resource Relation:
Other Information: 16 refs., 5 figs.
Subject:
73 NUCLEAR PHYSICS AND RADIATION PHYSICS; 22 GENERAL STUDIES OF NUCLEAR REACTORS; SHIELDING; SLOWING-DOWN; NEUTRONS; PENETRATION DEPTH; DIFFUSION EQUATIONS
OSTI ID:
20949555
Research Organizations:
AB Atomenergi, Nykoeping (Sweden)
Country of Origin:
Sweden
Language:
English
Other Identifying Numbers:
TRN: SE0708527
Availability:
Commercial reproduction prohibited; OSTI as DE20949555
Submitting Site:
SWDN
Size:
28 pages
Announcement Date:
Dec 15, 2007

Citation Formats

Hjaerne, L, and Leimdoerfer, M. A New Method for Predicting the Penetration and Slowing-Down of Neutrons in Reactor Shields. Sweden: N. p., 1965. Web.
Hjaerne, L, & Leimdoerfer, M. A New Method for Predicting the Penetration and Slowing-Down of Neutrons in Reactor Shields. Sweden.
Hjaerne, L, and Leimdoerfer, M. 1965. "A New Method for Predicting the Penetration and Slowing-Down of Neutrons in Reactor Shields." Sweden.
@misc{etde_20949555,
title = {A New Method for Predicting the Penetration and Slowing-Down of Neutrons in Reactor Shields}
author = {Hjaerne, L, and Leimdoerfer, M}
abstractNote = {A new approach is presented in the formulation of removal-diffusion theory. The 'removal cross-section' is redefined and the slowing-down between the multigroup diffusion equations is treated with a complete energy transfer matrix rather than in an age theory approximation. The method, based on the new approach contains an adjustable parameter. Examples of neutron spectra and thermal flux penetrations are given in a number of differing shield configurations and the results compare favorably with experiments and Moments Method calculations.}
place = {Sweden}
year = {1965}
month = {May}
}