Neutronic implications of lead-lithium blankets

Conference · Sun Aug 01 00:00:00 EDT 1982

OSTI ID:6779257

Meier, W R

Lead-lithium alloys have been proposed for use in several conceptual blanket designs for both inertial and magnetic confinement fusion reactors. In most cases, Pb/sub 83/Li/sub 17/, a eutectic with a melting point of 235/sup 0/C, is the chosen composition. The primary reasons for using Pb/sub 83/Li/sub 17/ instead of Li as the tritium breeding material are the perceived safety advantages, low tritium solubility, and favorable neutronic characteristics. This paper describes the neutronic characteristics of Pb/sub 83/Li/sub 17/ blankets with emphasis on the enhanced neutron leakage through chamber ports and the degradation in blanket performance parameters that occurs as a result of the enhanced leakage.

• Research Organization: Lawrence Livermore National Lab., CA (USA)
• DOE Contract Number: W-7405-ENG-48
• OSTI ID: 6779257
• Report Number(s): UCRL-87499; CONF-820948-1; ON: DE82021629; TRN: 82-024345
• Resource Relation: Conference: 12. symposium on fusion technology, Juelich, F.R. Germany, 13 Sep 1982
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
BREEDING BLANKETS
DESIGN
NEUTRON TRANSPORT
LEAD ALLOYS
NEUTRON REACTIONS
LITHIUM ALLOYS
TRITIUM
BREEDING RATIO
SAFETY
SOLUBILITY
ALLOYS
BARYON REACTIONS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
CONVERSION RATIO
HADRON REACTIONS
HYDROGEN ISOTOPES
ISOTOPES
LIGHT NUCLEI
NEUTRAL-PARTICLE TRANSPORT
NUCLEAR REACTIONS
NUCLEI
NUCLEON REACTIONS
ODD-EVEN NUCLEI
RADIATION TRANSPORT
RADIOISOTOPES
REACTOR COMPONENTS
YEARS LIVING RADIOISOTOPES
700201* - Fusion Power Plant Technology- Blanket Engineering