Design of an indirect-cycle fast breeder reactor cooled by supercritical steam
Creators
- 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
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 25044842
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COST; DESIGN; FBR TYPE REACTORS; FEASIBILITY STUDIES; HETEROGENEOUS REACTOR CORES; HYDRAULICS; MODIFICATIONS; REACTIVITY; SHAPE; STEAM COOLED REACTORS; SUPERCRITICAL STATE; THERMODYNAMICS
- Descriptors DEC
- BREEDER REACTORS; EPITHERMAL REACTORS; FAST REACTORS; GAS COOLED REACTORS; REACTOR COMPONENTS; REACTOR CORES; REACTORS