Published May 1998
| Version v1
Miscellaneous
Core analysis during transition from 37-element fuel to CANFLEX-NU fuel in CANDU 6
Description
An 1200-day time-dependent fuel-management for the transition from 37-element fuel to CANFLEX-NU fuel in a CANDU 6 reactor has been simulated to show the compatibility of the CANFLEX-NU fuel with the reactor operation. The simulation calculations were carried out with the RFSP code, provided by cell averaged fuel properties obtained from the POWDERPUFS-V code. The refueling scheme for both fuels was an eight bundle shift at a time. The simulation results show that the maximum channel and bundle powers were maintained below the license limit of the CANDU 6. This indicates that the CANFLEX-NU fuel bundle is compatible with the CANDU 6 reactor operation during the transition period
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Taejon (Korea, Republic of)
- Imprint Title
- Proceedings of the Korean Nuclear Society spring meeting Vol. 1
- Imprint Pagination
- 905 p.
- Journal Page Range
- p. 169-174
Conference
- Title
- 1998 spring meeting of the Korean Nuclear Society
- Dates
- 29-30 May 1998
- Place
- Seoul (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 33056751
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CANDU TYPE REACTORS; COMPUTER CALCULATIONS; FUEL ELEMENT CLUSTERS; FUEL ELEMENTS; NUCLEAR FUELS; P CODES; R CODES; REACTOR CORES; REACTOR OPERATION; SIMULATION
- Descriptors DEC
- COMPUTER CODES; ENERGY SOURCES; FUEL ASSEMBLIES; FUELS; HEAVY WATER MODERATED REACTORS; MATERIALS; OPERATION; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; THERMAL REACTORS
Optional Information
- Notes
- 3 refs, 2 figs, 1 tab