Published 2004 | Version v1
Computer medium

Application of the generalized multigroup method for a continuous gamma spectrum source

  • 1. Univ. of Tennessee, Knoxville, Tennessee (United States)

Description

Treatment of energy in the solution of the transport equation has been dominated by the multigroup method. This method suffers from two disadvantages: the assumed spectrum becomes discontinuous at the energy boundaries, and it maintains its original shape within the group. These disadvantages reduce its accuracy. To mitigate these inefficiencies, a generalized multigroup method was developed. In this method, an arbitrary set of basis functions is defined that allow the spectrum to adapt within each energy group and be continuous at the boundaries. A linear form of the multigroup method was implemented on a continuous fission gamma spectrum to demonstrate its efficacy. (author)

Part of:
6. International conference on simulation methods in nuclear engineering

Additional details

Publishing Information

Publisher
Canadian Nuclear Society
Imprint Place
Toronto, Ontario (Canada)
ISBN
0-919784-80-1
Imprint Title
6. International conference on simulation methods in nuclear engineering
Imprint Pagination
119 Megabytes
Journal Page Range
[8 p.]

Conference

Title
6. international conference on simulation methods in nuclear engineering
Dates
12-15 Oct 2004
Place
Montreal, Quebec (Canada)

INIS

Country of Publication
Canada
Country of Input or Organization
Canada
INIS RN
36107454
Subject category
S73: NUCLEAR PHYSICS AND RADIATION PHYSICS; S99: GENERAL AND MISCELLANEOUS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
GAMMA SOURCES; GAMMA SPECTRA; MULTIGROUP THEORY; NEUTRON TRANSPORT THEORY; RADIATION TRANSPORT
Descriptors DEC
NEUTRON TRANSPORT THEORY; RADIATION SOURCES; SPECTRA; TRANSPORT THEORY

Optional Information

Notes
3 refs., 1 tab., 2 figs.