Published December 1, 2010
| Version v1
Miscellaneous
Overview of Monte Carlo radiation transport codes
- 1. Oak Ridge National Laboratory, TN (United States)
Description
The Radiation Safety Information Computational Center (RSICC) is the designated central repository of the United States Department of Energy (DOE) for nuclear software in radiation transport, safety, and shielding. Since the center was established in the early 60's, there have been several Monte Carlo particle transport (MC) computer codes contributed by scientists from various countries. An overview of the neutron transport computer codes in the RSICC collection is presented.
Additional details
Publishing Information
- Imprint Pagination
- 10 p.
Conference
- Title
- 11. NEUTRON AND ION DOSIMETRY SYMPOSIUM (NEUDOS-11)
- Dates
- 12-16 Oct 2009
- Place
- Cape Town (South Africa)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 42070188
- Subject category
- S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- COMPUTER CODES; ION DOSIMETRY; NEUTRON TRANSPORT; NEUTRONS; RADIATION PROTECTION; RADIATION TRANSPORT; SAFETY; SHIELDING; TRANSPORT
- Descriptors DEC
- BARYONS; DOSIMETRY; ELEMENTARY PARTICLES; FERMIONS; HADRONS; NEUTRAL-PARTICLE TRANSPORT; NUCLEONS; RADIATION TRANSPORT
Optional Information
- Contract/Grant/Project number
- AT6010301; ERAT639; AC05-00OR22725
- Notes
- pages 1318-1322
- Funding organization
- SC USDOE - Office of Science (United States)