A Fusion Breeder Reactor Based on a Catalyzed D-D Spherical Torus.
Abstract
One of the potentially attractive applications of nuclear fusion is to breed fissile fuel for use in fission reactors. This thesis examines a novel non-power producing fusion reactor based on the spherical torus concept with a catalyzed deuterium-deuterium fuel cycle and aqueous self-cooled blanket for use as a fissile breeder. The breeding of fissile fuel is accomplished by dissolving a uranium salt, uranyl nitrite, in heavy water which flows through the first wall and blanket providing both cooling and fissile breeding. The need for tritium breeding is eliminated by the use of a catalyzed D-D fuel cycle. Analysis of this novel reactor concept indicates a fissile breeding ratio of 1.34 Pu-239/source neutron using a 15 CM beryllium moderator and 7 mo1% uranyl nitrite in the heavy water. A typical reactor using this blanket can produce more than 8000 KG/YR of plutonium at a cost of less than $40 per gram. This indicates the potential for a reactor which can provide fissile fuel at, or below, its current mined cost.
Document Details
- Document Type
- Technical Report
- Publication Date
- Aug 08, 1986
- Accession Number
- ADA173879
Entities
People
- Kenneth L. Wrisley Jr