Design analyses of self-cooled liquid metal blankets

Technical Report · Mon Dec 01 04:00:00 EST 1986

DOI:https://doi.org/10.2172/6722183· OSTI ID:6722183

Gohar, Y

A trade-off study of liquid metal self-cooled blankets was carried out to define the performance of these blankets and to determine the potential to operate at the maximum possible values of the performance parameters. The main parameters considered during the course of the study were the tritium breeding ratio (TBR), the blanket energy multiplication factor, the energy fraction lost to the shield, the lithium-6 enrichment in the breeder material, the total blanket thickness, the reflector material selection, and the compositions of the different blanket zones. Also, a study was carried out to assess the impact of different reactor design choices on the reactor performance parameters. The design choices include the impurity control system (limiter or divertor), the material choice for the limiter, the elimination of tritium breeding from the inboard section of tokamak reactors, and the coolant choice for the nonbreeding inboard blanket. In addition, tritium breeding benchmark calculations were performed using different transport codes and nuclear data libraries. The importance of the TBR in the blanket design motivated the benchmark calculations.

• Research Organization: Argonne National Lab., IL (USA)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 6722183
• Report Number(s): ANL/FPP/TM-208; ON: DE87005583
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201* -- Fusion Power Plant Technology-- Blanket Engineering
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BREEDING BLANKETS
BREEDING RATIO
CONVERSION RATIO
DESIGN
ELEMENTS
ENERGY LOSSES
FLUIDS
HYDROGEN ISOTOPES
ISOTOPES
LIGHT NUCLEI
LIQUID METALS
LIQUIDS
LOSSES
METALS
NUCLEI
ODD-EVEN NUCLEI
PARAMETRIC ANALYSIS
PERFORMANCE
RADIOISOTOPES
REACTOR COMPONENTS
SHIELDING
TRITIUM
YEARS LIVING RADIOISOTOPES