Refueling studies in radial blanket of large fast breeder reactor
Journal Article
·
· J. Nucl. Sci. Technol. (Tokyo), v. 10, no. 10, pp. 598-606
Refueling schemes in the radial blanket of the large fast breeder reactor are discussed. The reactor adopted for these studies is a 1,000 MW(e) sodium cooled, mixed plutoniumuranium oxide fuel unit with a thermal rating of 2,400 MW. Burnup calculations, combined with different refueling schemes are carried out to determine its characteristics. From the results obtained on power distribution, the coolant flow rates in the core and in the different blanket layers are calculated under the condition of limited cladding temperature. The different refueling schemes are then compared mainly from the standpoint of the thermal performance of the reactor. (auth)
- Research Organization:
- Fuji Electric Co. Ltd., Tokyo
- NSA Number:
- NSA-29-020098
- OSTI ID:
- 4330823
- Journal Information:
- J. Nucl. Sci. Technol. (Tokyo), v. 10, no. 10, pp. 598-606, Journal Name: J. Nucl. Sci. Technol. (Tokyo), v. 10, no. 10, pp. 598-606; ISSN JNSTA
- Country of Publication:
- Japan
- Language:
- English
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