Design Feasible Area on Water Cooled Thorium Breeder Reactor in Equilibrium States
Conference
·
OSTI ID:20995595
- Tokyo Institute of Technology, 2-12-1 Ookayama, Meguro-ku, Tokyo 152-8550 (Japan)
Thorium as supplied fuel has good candidate for fuel material if it is converted into fissile material {sup 233}U which shows superior characteristics in the thermal region. The Shippingport reactor used {sup 233}U-Th fuel system, and the molten salt breeder reactor (MSBR) project showed that breeding is possible in a thermal spectrum. In the present study, feasibility of water cooled thorium breeder reactor is investigated. The key properties such as flux, {eta} value, criticality and breeding performances are evaluated for different moderator to fuel ratios (MFR) and burn-ups. The results show the feasibility of breeding for different MFR and burn-ups. The required {sup 233}U enrichment is about 2% - 9% as charge fuel. The lower MFR and the higher enrichment of {sup 233}U are preferable to improve the average burn-up; however the design feasible window is shrunk. This core shows the design feasible window especially in relation to MFR with negative void reactivity coefficient. (authors)
- Research Organization:
- The ASME Foundation, Inc., Three Park Avenue, New York, NY 10016-5990 (United States)
- OSTI ID:
- 20995595
- Country of Publication:
- United States
- Language:
- English
Similar Records
Cell configuration effect on feasibility of water cooled thorium breeder reactor
Feasibility of Water Cooled Thorium Breeder Reactor Based on LWR Technology
Feasibility study on the thorium fueled boiling water breeder reactor
Conference
·
Sat Jul 01 00:00:00 EDT 2006
·
OSTI ID:22039668
Feasibility of Water Cooled Thorium Breeder Reactor Based on LWR Technology
Conference
·
Sun Jul 01 00:00:00 EDT 2007
·
OSTI ID:20979761
Feasibility study on the thorium fueled boiling water breeder reactor
Conference
·
Sun Jul 01 00:00:00 EDT 2012
·
OSTI ID:22106035