A Preliminary Study of a Hybrid Fusion Reactor at Moderate Temperature.
Abstract
A hybrid fission-fusion system is investigated which operates in a moderate temperature range. The fuel is LiD which is a solid at room temperature. The fusion reaction is maintained by a neutron source from a fission reactor. For a spherically concentric system with interface radius equal to 5m, and a fission neutron flux of 10 to the 13th power/sq cm sec, tge output power due to fusion is estimated to be 10 kw. The direct heating of the lattice owing to Li6 neutron capture for these same dimensions is estimated to be 23 Mw and it is concluded that the system is inefficient as a fusion device. (Author)
Document Details
- Document Type
- Technical Report
- Publication Date
- Jul 21, 1976
- Accession Number
- ADA027196
Entities
People
- Richard L. Liboff
Organizations
- Cornell University