ORLIB: a computer code that produces one-energy group, time- and spatially-averaged neutron cross sections
Description
Calculation of neutron activation of proposed fusion reactors requires a library of neutron-activation cross sections. One such library is ACTL, which is being updated and expanded by Howerton. If the energy-dependent neutron flux is also known as a function of location and time, the buildup and decay of activation products can be calculated. In practice, hand calculation is impractical without energy-averaged cross sections because of the large number of energy groups. A widely used activation computer code, ORIGEN2, also requires energy-averaged cross sections. Accordingly, we wrote the ORLIB code to collapse the ACTL library, using the flux as a weighting function. The ORLIB code runs on the LLNL Cray computer network. We have also modified ORIGEN2 to accept the expanded activation libraries produced by ORLIB
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A02/MF A01 as DE82016132.
Files
Additional details
Publishing Information
- Imprint Pagination
- 7 p.
- Report number
- UCRL--53262
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 14721989
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Descriptors DEI
- COMPUTER CODES; CROSS SECTIONS; NEUTRON REACTIONS; NEUTRON TRANSPORT; O CODES; THERMONUCLEAR REACTOR MATERIAL; THERMONUCLEAR REACTOR WALLS
- Descriptors DEC
- BARYON REACTIONS; HADRON REACTIONS; MATERIALS; NEUTRAL-PARTICLE TRANSPORT; NUCLEAR REACTIONS; NUCLEON REACTIONS; RADIATION TRANSPORT