Published 1991
| Version v1
Book
FFR core fuel management
Description
This paper briefly describes the zonewise scattered multiple batch refueling scheme for FFR core fuel management in the concept design consideration. Two computer codes, 1DX and FUMA, were used to support the analysis. The calculation results indicate that the average discharge burnup is 33,000 MWD/t under the limitations of the maximum nominal linear power 430W/cm and the maximum discharge burnup 50,000 MWD/t. (author)
Additional details
Publishing Information
- Publisher
- Atomic Energy Society of Japan.
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- International conference on fast reactors and related fuel cycles
- Imprint Pagination
- [2900 p.].
- Journal Page Range
- v. 3 p. 1.12/1-1.12/3.
Conference
- Title
- International conference on fast reactors and related fuel cycles.
- Dates
- 28 Oct - 1 Nov 1991.
- Place
- Kyoto (Japan).
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 24033588
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; CHINA; COMPUTER CALCULATIONS; CONTROL ELEMENTS; F CODES; FEASIBILITY STUDIES; FUEL ASSEMBLIES; FUEL MANAGEMENT; LMFBR TYPE REACTORS; POWER RANGE 10-100 MW; REACTOR CORES
- Descriptors DEC
- ASIA; BREEDER REACTORS; COMPUTER CODES; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; MANAGEMENT; MEGAWATT POWER RANGE; NUCLEAR MATERIALS MANAGEMENT; POWER RANGE; REACTOR COMPONENTS; REACTORS
Optional Information
- Notes
- Imprint:Composed of four volumes.