Nuclear performance optimization of the molten-salt fusion breeder

Conference · Thu Jun 05 00:00:00 EDT 1986

OSTI ID:5564457

Lee, J D; Bandini, B R

Improved nuclear analysis, including the treatment of resonance and spatial self-shielding, coupled with an optimization procedure, has resulted in an improved performance estimate for the molten salt blanket. Net U-233 breeding ratio ranges between 0.58 and 0.63, and blanket energy multiplication ranges between 1.8 and 1.9.

• Research Organization: Lawrence Livermore National Lab., CA (USA); Pennsylvania State Univ., University Park (USA)
• DOE Contract Number: W-7405-ENG-48
• OSTI ID: 5564457
• Report Number(s): UCRL-94037; CONF-860652-17; ON: DE86013897
• Resource Relation: Conference: 7. topical meeting on the technology of fusion energy, Reno, NV, USA, 15 Jun 1986
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
BREEDING BLANKETS
BREEDING RATIO
URANIUM 233
BERYLLIUM FLUORIDES
LITHIUM FLUORIDES
MOLTEN SALTS
MULTIPLICATION FACTORS
OPTIMIZATION
RESONANCE
SHIELDING
THORIUM FLUORIDES
ACTINIDE COMPOUNDS
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALKALI METAL COMPOUNDS
ALKALINE EARTH METAL COMPOUNDS
ALPHA DECAY RADIOISOTOPES
BERYLLIUM COMPOUNDS
CONVERSION RATIO
EVEN-ODD NUCLEI
FLUORIDES
FLUORINE COMPOUNDS
HALIDES
HALOGEN COMPOUNDS
HEAVY NUCLEI
ISOTOPES
LITHIUM COMPOUNDS
LITHIUM HALIDES
NUCLEI
RADIOISOTOPES
REACTOR COMPONENTS
SALTS
THORIUM COMPOUNDS
URANIUM ISOTOPES
YEARS LIVING RADIOISOTOPES
700201* - Fusion Power Plant Technology- Blanket Engineering