Measurement of tritium production-rate distribution in a 60 cm-thick Li/sub 2/O slab assembly and its analysis
Conference
·
· Fusion Technol.; (United States)
OSTI ID:5793082
Tritium production-rate (TPR) distributions were measured in a Li/sub 2/O slab assembly using the FNS. The size of assembly was 31.5 cm in equivalent radius and 61.0 cm in thickness. Enriched /sup 6/Li and /sup 7/Li sintered pellets of Li/sub 2/O were adopted to measure the TPRs of /sup 6/Li and /sup 7/Li, separately. After irradiated pellets were treated chemically, tritium produced in the pellets was measured by a liquid scintillation counting system. Measured TPR distributions have been analyzed by using the three transport codes, DOT3.5, MORSE-DD and BERMUDA-2DN with ENDF/B-4 and JENDL-3PR1 nuclear data files. The JENDL-3PR1 improves the accuracy of calculated TPR very well for both /sup 6/Li and /sup 7/Li.
- Research Organization:
- Japan Atomic Energy Research Institute Tokai-mura, Ibaraki-ken
- OSTI ID:
- 5793082
- Report Number(s):
- CONF-850310-
- Conference Information:
- Journal Name: Fusion Technol.; (United States) Journal Volume: 8:1
- Country of Publication:
- United States
- Language:
- English
Similar Records
Tritium production-rate distributions in a Be-sandwich lithium-oxide cylindrical assembly
Experiment and analysis of the behavior of 14-MeV neutrons in a large cavity
Measurements of angular flux on surface of Li/sub 2/O slab assemblies and their analysis by a direct integration transport code ''BERMUDA''
Conference
·
Tue Feb 28 23:00:00 EST 1989
· Fusion Technol.; (United States)
·
OSTI ID:6244216
Experiment and analysis of the behavior of 14-MeV neutrons in a large cavity
Journal Article
·
Tue Oct 31 23:00:00 EST 1989
· Fusion Technology; (United States)
·
OSTI ID:5857157
Measurements of angular flux on surface of Li/sub 2/O slab assemblies and their analysis by a direct integration transport code ''BERMUDA''
Conference
·
Thu Sep 01 00:00:00 EDT 1983
· Nucl. Technol./Fusion; (United States)
·
OSTI ID:6203731
Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700205* -- Fusion Power Plant Technology-- Fuel
Heating
& Injection Systems
700209 -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALKALI METAL COMPOUNDS
ALKALI METAL ISOTOPES
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BREEDING
BREEDING BLANKETS
BREEDING PELLETS
CHALCOGENIDES
COMPUTERIZED SIMULATION
COUNTING TECHNIQUES
HYDROGEN ISOTOPES
ISOTOPES
LIGHT NUCLEI
LIQUID SCINTILLATION DETECTORS
LITHIUM 6
LITHIUM 7
LITHIUM COMPOUNDS
LITHIUM ISOTOPES
LITHIUM OXIDES
MATERIALS
MEASURING INSTRUMENTS
NEUTRAL-PARTICLE TRANSPORT
NEUTRON SOURCE FACILITIES
NEUTRON TRANSPORT
NUCLEAR DATA COLLECTIONS
NUCLEAR FUEL CONVERSION
NUCLEI
ODD-EVEN NUCLEI
ODD-ODD NUCLEI
OXIDES
OXYGEN COMPOUNDS
PRODUCTION
RADIATION DETECTORS
RADIATION TRANSPORT
RADIOISOTOPES
REACTOR COMPONENTS
SCINTILLATION COUNTERS
SCINTILLATION COUNTING
SIMULATION
SINTERED MATERIALS
STABLE ISOTOPES
THERMONUCLEAR REACTOR MATERIALS
TRITIUM
YEARS LIVING RADIOISOTOPES
700205* -- Fusion Power Plant Technology-- Fuel
Heating
& Injection Systems
700209 -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALKALI METAL COMPOUNDS
ALKALI METAL ISOTOPES
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BREEDING
BREEDING BLANKETS
BREEDING PELLETS
CHALCOGENIDES
COMPUTERIZED SIMULATION
COUNTING TECHNIQUES
HYDROGEN ISOTOPES
ISOTOPES
LIGHT NUCLEI
LIQUID SCINTILLATION DETECTORS
LITHIUM 6
LITHIUM 7
LITHIUM COMPOUNDS
LITHIUM ISOTOPES
LITHIUM OXIDES
MATERIALS
MEASURING INSTRUMENTS
NEUTRAL-PARTICLE TRANSPORT
NEUTRON SOURCE FACILITIES
NEUTRON TRANSPORT
NUCLEAR DATA COLLECTIONS
NUCLEAR FUEL CONVERSION
NUCLEI
ODD-EVEN NUCLEI
ODD-ODD NUCLEI
OXIDES
OXYGEN COMPOUNDS
PRODUCTION
RADIATION DETECTORS
RADIATION TRANSPORT
RADIOISOTOPES
REACTOR COMPONENTS
SCINTILLATION COUNTERS
SCINTILLATION COUNTING
SIMULATION
SINTERED MATERIALS
STABLE ISOTOPES
THERMONUCLEAR REACTOR MATERIALS
TRITIUM
YEARS LIVING RADIOISOTOPES