Radiation Shielding Information Center: a source of computer codes and data for fusion neutronics studies
Conference
·
OSTI ID:6821422
The Radiation Shielding Information Center (RSIC), established in 1962 to collect, package, analyze, and disseminate information, computer codes, and data in the area of radiation transport related to fission, is now being utilized to support fusion neutronics technology. The major activities include: (1) answering technical inquiries on radiation transport problems, (2) collecting, packaging, testing, and disseminating computing technology and data libraries, and (3) reviewing literature and operating a computer-based information retrieval system containing material pertinent to radiation transport analysis. The computer codes emphasize methods for solving the Boltzmann equation such as the discrete ordinates and Monte Carlo techniques, both of which are widely used in fusion neutronics. The data packages include multigroup coupled neutron-gamma-ray cross sections and kerma coefficients, other nuclear data, and radiation transport benchmark problem results.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 6821422
- Report Number(s):
- CONF-801011-14
- Country of Publication:
- United States
- Language:
- English
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Wed Dec 31 23:00:00 EST 1975
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Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
BARYON REACTIONS
COMPUTER CODES
DATA
DATA COMPILATION
HADRON REACTIONS
INFORMATION
INFORMATION CENTERS
INFORMATION SYSTEMS
MATERIALS
NEUTRON REACTIONS
NUCLEAR REACTIONS
NUCLEON REACTIONS
NUMERICAL DATA
SHIELDING
THERMONUCLEAR REACTOR MATERIALS
TRANSPORT THEORY
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
BARYON REACTIONS
COMPUTER CODES
DATA
DATA COMPILATION
HADRON REACTIONS
INFORMATION
INFORMATION CENTERS
INFORMATION SYSTEMS
MATERIALS
NEUTRON REACTIONS
NUCLEAR REACTIONS
NUCLEON REACTIONS
NUMERICAL DATA
SHIELDING
THERMONUCLEAR REACTOR MATERIALS
TRANSPORT THEORY