Published October 1993
| Version v1
Journal article
Decay heat rate of spent fuel in experimental fast reactor FFR
Description
The Calculated results including time-dependent decay heat from a spent fuel assembly discharged from the first experimental fast reactor (FFR) at burnup 50 GW · d/MTIHM are presented by using ORIGEN2, a point-depletion and radioactive-decay code, which was developed at the Oak Ridge National Laboratory (ORNL). the calculated values of spent fuel decay heat are also compared with the FFTF reactor of U.S.A
Additional details
Publishing Information
- Journal Title
- Nuclear Power Engineering
- Journal Volume
- 14
- Journal Issue
- 5
- Journal Page Range
- p. 469-472.
- ISSN
- 0258-0926
- CODEN
- HDGOE6
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 25050038
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Descriptors DEI
- AFTER-HEAT; FAST REACTORS; FUEL ASSEMBLIES; MATHEMATICAL MODELS; O CODES; SPENT FUEL ELEMENTS; TIME DEPENDENCE
- Descriptors DEC
- COMPUTER CODES; EPITHERMAL REACTORS; FUEL ELEMENTS; REACTOR COMPONENTS; REACTORS