Published 1992
| Version v1
Report
A comparison of the reactor physics predictions for CANFLEX fuel using the codes MCNP, WIMS-AECL, and LATREP
Description
The lattice codes WIMS-AECL and LATREP have been used to calculate fundamental reactor physics parameters for Atomic Energy of Canada Ltd.'s (AECL's) new CANFLEX fuel bundles, and an MCNP model was devised to check these results. An intercomparison of predictions from these codes is given, showing a reasonable agreement in the values of most parameters, but also highlighting a few inadequacies that require further refinement
Additional details
Publishing Information
- Imprint Title
- Proceedings of the 1992 topical meeting on advances in reactor physics. Volume 1
- Imprint Pagination
- 536 p.
- Journal Page Range
- p. 1.39-1.48.
- Report number
- CONF-920308--Vol.1
Conference
- Title
- American Nuclear Society (ANS) topical meeting on advances in reactor physics.
- Dates
- 8-11 Mar 1992.
- Place
- Charleston, SC (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23067959
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCURACY; ATOMIC ENERGY OF CANADA LTD; CANDU TYPE REACTORS; COMPUTER CODES; COMPUTERIZED SIMULATION; FUEL ELEMENT CLUSTERS; L CODES; M CODES; MONTE CARLO METHOD; REACTOR PHYSICS; RESONANCE INTEGRALS; URANIUM 238; W CODES
- Descriptors DEC
- ACTINIDE NUCLEI; ALPHA DECAY RADIOISOTOPES; CALCULATION METHODS; CANADIAN ORGANIZATIONS; EVEN-EVEN NUCLEI; FUEL ASSEMBLIES; HEAVY NUCLEI; HEAVY WATER MODERATED REACTORS; INTEGRALS; ISOTOPES; NATIONAL ORGANIZATIONS; NUCLEI; POWER REACTORS; PRESSURE TUBE REACTORS; RADIOISOTOPES; REACTORS; SIMULATION; SPONTANEOUS FISSION RADIOISOTO; THERMAL REACTORS; URANIUM ISOTOPES; YEARS LIVING RADIOISOTOPES