Published 2004
| Version v1
Computer medium
Application of the generalized multigroup method for a continuous gamma spectrum source
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)
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.