Published November 1980
| Version v1
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Once-through CANDU reactor models for the ORIGEN2 computer code
Description
Reactor physics calculations have led to the development of two CANDU reactor models for the ORIGEN2 computer code. The model CANDUs are based on (1) the existing once-through fuel cycle with feed comprised of natural uranium and (2) a projected slightly enriched (1.2 wt % 235U) fuel cycle. The reactor models are based on cross sections taken directly from the reactor physics codes. Descriptions of the reactor models, as well as values for the ORIGEN2 flux parameters THERM, RES, and FAST, are given
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A04/MF A01.
Files
Restricted
The record is publicly accessible, but files are restricted to users with access.
Additional details
Publishing Information
- Imprint Pagination
- 64 p.
- Report number
- ORNL/TM--7177
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 12589440
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Descriptors DEI
- BURNUP; CANDU TYPE REACTORS; CHEMICAL COMPOSITION; COMPUTER CODES; FUEL CYCLE; ISOTOPE RATIO; MULTIGROUP THEORY; O CODES; SPENT FUELS
- Descriptors DEC
- ENERGY SOURCES; FUELS; HEAVY WATER MODERATED REACTORS; NUCLEAR FUELS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR MATERIALS; REACTORS; THERMAL REACTORS; TRANSPORT THEORY