Published 2004
| Version v1
Computer medium
Neutron beam and shielding design of MNR high-speed neutron radiography facility
- 1. McMaster Univ., Dept. of Engineering Physics, Hamilton, Ontario (Canada)
Description
Although transport of low energy neutron and scattering laws are extremely complicated, it is possible, sometimes, to calculate neutron flux by deterministic method. When the geometric structure is complicated, one is usually forced to rely on numerical techniques. Despite the advances in discrete ordinates and finite elements methods Monte-Carlo is still the most efficient way of solving difficult problems in the field of neutron and photon linear transport. (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
- [3 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
- 36107497
- Subject category
- S73: NUCLEAR PHYSICS AND RADIATION PHYSICS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- MONTE CARLO METHOD; NEUTRON TRANSPORT; NUMERICAL ANALYSIS; PHOTON TRANSPORT; SCATTERING
- Descriptors DEC
- CALCULATION METHODS; MATHEMATICS; NEUTRAL-PARTICLE TRANSPORT; RADIATION TRANSPORT
Optional Information
- Notes
- 8 refs., 2 figs.