Published October 1993 | Version v1
Journal article

Design of an indirect-cycle fast breeder reactor cooled by supercritical steam

  • 1. Nuclear Engineering Research Lab., Tokyo Univ., Tokai, Ibaraki (Japan)

Description

The neutronic feasbility of a large-sized FBR cooled by supercritical steam is assessed for finding the way to reduce the costs of FBR plants. A negative coolant void reactivity is realized without much deterioration in breeding capability, by our novel concept of inserting thin zirconium-hybride layers between the seed and blanket of the radially heterogeneous core. The gross electric power is 1040 MWe. The estimated equilibrium compound system doubling time is 16 years. The discharge burnup is 78.7 GWd/T and the refueling period is 1 year with a 77% load factor. Compared with the conventional steam cooled FBR, the pumping power fraction is reduced due to the high coolant density of supercritical water. Loeffler boilers for generating steam are not necessary. The reactor system is simplified and similar to a PWR. The thermal efficiency is 39.6%, improved 15% relatively from PWR's. The pressure vessel is 32.5 cm thick. (orig.)

Additional details

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
144
Journal Issue
2
Journal Page Range
p. 337-344.
ISSN
0029-5493
CODEN
NEDEAU