Molten salt blanket calculations for a tokamak fusion-fission hybrid reactor

Technical Report · Thu Apr 01 04:00:00 EST 1976

DOI:https://doi.org/10.2172/7348608· OSTI ID:7348608

Chapin, D. L.

Several possible blanket designs for use in a tokamak fusion-fission hybrid reactor are investigated. The main constituent of the blanket is a molten salt, possibly with a separate convertor region for multiplication of the source neutrons. Both the thorium and uranium fuel cycles are analyzed subject to constraints on the blanket performance such as high blanket energy multiplication and sufficient breeding of tritium and fissile fuel. It is found that the behavior depends strongly on the salt composition through the ratios of fertile material to fissile material and lithium to fissile material. It is also very important to have multiplication of the high energy source neutrons in a convertor zone between the plasma and the salt. Ways of optimizing this neutron multiplication through variations in the convertor zone composition and thickness are investigated.

• Research Organization: Princeton Univ., NJ (USA). Plasma Physics Lab.
• Sponsoring Organization: US Energy Research and Development Administration (ERDA)
• OSTI ID: 7348608
• Report Number(s): MATT-1236
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700202* -- Fusion Power Plant Technology-- Magnet Coils & Fields
ACTINIDES
ALKALI METALS
BARYON REACTIONS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BREEDING BLANKETS
CLOSED PLASMA DEVICES
ELEMENTS
FISSION
HADRON REACTIONS
HYBRID REACTORS
HYBRID SYSTEMS
HYDROGEN ISOTOPES
ISOTOPES
LIGHT NUCLEI
LITHIUM
METALS
MOLTEN SALTS
NEUTRON REACTIONS
NUCLEAR REACTIONS
NUCLEI
NUCLEON REACTIONS
ODD-EVEN NUCLEI
RADIOISOTOPES
REACTOR COMPONENTS
SALTS
THERMONUCLEAR DEVICES
THORIUM
TOKAMAK DEVICES
TRITIUM
URANIUM
YEARS LIVING RADIOISOTOPES