Two-dimensional cross-section sensitivity and uncertainty analysis for tritium production rate in fusion-oriented integral experiments
Journal Article
·
· Fusion Technol.; (United States)
OSTI ID:6823317
Several integral experiments on tritium breeding were jointly performed in connection with the U.S./JAERI Collaborative Program on Fusion Breeder Neutronics. Tritium production rates from /sup 6/Li (T/sub 6/) and /sup 7/Li(T/sub 7/) were measured at several locations in an Li/sub 2/O assembly embedded in the concrete wall of a 5- x 5- x 4.5-m room (reference experiment) in independent benchmark experiments with the Li/sub 2/O assembly located in a large room of negligible room-return neutrons. In the reference experiment, large discrepancies in T/sub 6/ were found at the front locations in the Li/sub 2/O assembly. At middle locations, the calculated-to-experimental (C/E) values for T/sub 6/ are -- 1.2 (U.S.) and -- l.1 (JAERI). The C/E values for T/sub 7/ are -- 1.18 (U.S.) and 1.05 (JAERI). To assess the contribution to the uncertainty is predicting T/sub 6/ and T/sub 7/ that results from the current uncertainties in the nuclear data base, an extensive two-dimensional cross-section sensitivity/uncertainty analysis was performed. For that purpose, the FORSS module, and the VIP and DOT 4.3 codes were used along with the PUFF-2 covariance code. Two systems were considered for the analysis: the benchmark system and the reference system. The models used simulate the geometrical details and source conditions for the experiments.
- Research Organization:
- Japan Atomic Energy Research Institute, Tokai Research Establishment, Dept. of Reactor Engineering, Tokai-mura, Ibaraki-ken 319-11 (JP)
- OSTI ID:
- 6823317
- Journal Information:
- Fusion Technol.; (United States), Journal Name: Fusion Technol.; (United States) Vol. 13:4; ISSN FUSTE
- Country of Publication:
- United States
- Language:
- English
Similar Records
Comparative analysis for Phase IIA and IIB experiments of the U. S. /JAERI collaborative program on fusion blanket neutronics
JAERI (Japan Atomic Energy Research Institute)/US calculational benchmarks for nuclear data and codes intercomparison
Methodology and analysis for effects of energy and angular distributions of secondary neutrons in fusion blankets and application to integral beryllium experiments
Conference
·
Tue Feb 28 23:00:00 EST 1989
· Fusion Technol.; (United States)
·
OSTI ID:6277155
JAERI (Japan Atomic Energy Research Institute)/US calculational benchmarks for nuclear data and codes intercomparison
Conference
·
Tue Dec 31 23:00:00 EST 1985
· Transactions of the American Nuclear Society; (USA)
·
OSTI ID:6799829
Methodology and analysis for effects of energy and angular distributions of secondary neutrons in fusion blankets and application to integral beryllium experiments
Thesis/Dissertation
·
Sun Dec 31 23:00:00 EST 1989
·
OSTI ID:6308345
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220400 -- Nuclear Reactor Technology-- Control Systems
220700* -- Nuclear Reactor Technology-- Plutonium & Isotope Production Reactors
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201 -- Fusion Power Plant Technology-- Blanket Engineering
700205 -- Fusion Power Plant Technology-- Fuel
Heating
& Injection Systems
ALKALI METAL COMPOUNDS
BENCHMARKS
BREEDING BLANKETS
BUILDING MATERIALS
CALCULATION METHODS
CHALCOGENIDES
COMPUTER CODES
CONCRETES
CROSS SECTIONS
DATA
DATA ANALYSIS
EQUATIONS
EXPERIMENTAL DATA
FIRST WALL
INFORMATION
INTEGRAL EQUATIONS
IRRADIATION REACTORS
JAERI
JAPANESE ORGANIZATIONS
LITHIUM COMPOUNDS
LITHIUM OXIDES
MATERIALS
NATIONAL ORGANIZATIONS
NUMBER CODES
NUMERICAL DATA
OXIDES
OXYGEN COMPOUNDS
P CODES
REACTOR COMPONENTS
REACTORS
THERMONUCLEAR REACTOR WALLS
TRITIUM PRODUCTION REACTORS
TWO-DIMENSIONAL CALCULATIONS
UNCERTAINTY PRINCIPLE
US DOT
US ORGANIZATIONS
V CODES
22 GENERAL STUDIES OF NUCLEAR REACTORS
220400 -- Nuclear Reactor Technology-- Control Systems
220700* -- Nuclear Reactor Technology-- Plutonium & Isotope Production Reactors
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201 -- Fusion Power Plant Technology-- Blanket Engineering
700205 -- Fusion Power Plant Technology-- Fuel
Heating
& Injection Systems
ALKALI METAL COMPOUNDS
BENCHMARKS
BREEDING BLANKETS
BUILDING MATERIALS
CALCULATION METHODS
CHALCOGENIDES
COMPUTER CODES
CONCRETES
CROSS SECTIONS
DATA
DATA ANALYSIS
EQUATIONS
EXPERIMENTAL DATA
FIRST WALL
INFORMATION
INTEGRAL EQUATIONS
IRRADIATION REACTORS
JAERI
JAPANESE ORGANIZATIONS
LITHIUM COMPOUNDS
LITHIUM OXIDES
MATERIALS
NATIONAL ORGANIZATIONS
NUMBER CODES
NUMERICAL DATA
OXIDES
OXYGEN COMPOUNDS
P CODES
REACTOR COMPONENTS
REACTORS
THERMONUCLEAR REACTOR WALLS
TRITIUM PRODUCTION REACTORS
TWO-DIMENSIONAL CALCULATIONS
UNCERTAINTY PRINCIPLE
US DOT
US ORGANIZATIONS
V CODES