JAERI (Japan Atomic Energy Research Institute)/US calculational benchmarks for nuclear data and codes intercomparison
Conference
·
· Transactions of the American Nuclear Society; (USA)
OSTI ID:6799829
Prior to analyzing the integral experiments performed at the Fast Neutron Source Facility at the Japan Atomic Energy Research Institute (JAERI), both U.S. and JAERI analysts have agreed on four calculational benchmark problems proposed by JAERI to intercompare results based on various codes and data bases used independently by both countries. To compare codes, the same data base is used (ENDF/B-IV). To compare nuclear data libraries, common codes were applied. The first benchmark problem is a closed Li{sub 2}O spherical geometry surrounding a fusion isotropic point source. A graphite zone and a stainless steel reflector followed the Li{sub 2}O zone. The second benchmark is a series of infinite slab geometries of various thicknesses consisting of natural lithium, Type 316 stainless steel, beryllium, oxygen, lead, and carbon considered individually in the analysis. For each case, an external monodirectional fusion source, incident perpendicularly on the left side of the slab, was considered. An isotropic point source incident on one side of a pseudocylindrical Li{sub 2}O assembly located in a vacuum was used in the third and fourth benchmark problems. Items selected for the intercomparison at various locations in problem 1 are the reaction rates {sup 6}Li(n,{alpha})t (T{sub 6}) and {sup 7}Li(n,n{prime}{alpha})t (T{sub 7}), the fission rate in {sup 235}U, {sup 238}U, {sup 232}Th, and {sup 237}Nb, and the neutron spectrum. The same items were considered in problem 3 and 4. 1 ref., 2 tabs.
- OSTI ID:
- 6799829
- Report Number(s):
- CONF-860610--Summs.
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society; (USA) Journal Volume: 52
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700200* -- Fusion Energy-- Fusion Power Plant Technology
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
990300 -- Information Handling
ALKALI METAL COMPOUNDS
ALKALINE EARTH METALS
ALLOYS
BARYON REACTIONS
BENCHMARKS
BERYLLIUM
CARBON
CHALCOGENIDES
COMPARATIVE EVALUATIONS
COMPUTER CODES
COOPERATION
DATA
ELEMENTS
EVALUATED DATA
FIRST WALL
FISSION
HADRON REACTIONS
HIGH ALLOY STEELS
INFORMATION
INTERNATIONAL COOPERATION
IRON ALLOYS
IRON BASE ALLOYS
JAERI
JAPANESE ORGANIZATIONS
LEAD
LITHIUM COMPOUNDS
LITHIUM OXIDES
METALS
NATIONAL ORGANIZATIONS
NEUTRAL-PARTICLE TRANSPORT
NEUTRON REACTIONS
NEUTRON SPECTRA
NEUTRON TRANSPORT
NONMETALS
NORTH AMERICA
NUCLEAR DATA COLLECTIONS
NUCLEAR REACTIONS
NUCLEON REACTIONS
NUMERICAL DATA
OXIDES
OXYGEN
OXYGEN COMPOUNDS
RADIATION TRANSPORT
SPECIFICATIONS
SPECTRA
STAINLESS STEELS
STEELS
THERMONUCLEAR REACTOR WALLS
THERMONUCLEAR REACTORS
USA
700200* -- Fusion Energy-- Fusion Power Plant Technology
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
990300 -- Information Handling
ALKALI METAL COMPOUNDS
ALKALINE EARTH METALS
ALLOYS
BARYON REACTIONS
BENCHMARKS
BERYLLIUM
CARBON
CHALCOGENIDES
COMPARATIVE EVALUATIONS
COMPUTER CODES
COOPERATION
DATA
ELEMENTS
EVALUATED DATA
FIRST WALL
FISSION
HADRON REACTIONS
HIGH ALLOY STEELS
INFORMATION
INTERNATIONAL COOPERATION
IRON ALLOYS
IRON BASE ALLOYS
JAERI
JAPANESE ORGANIZATIONS
LEAD
LITHIUM COMPOUNDS
LITHIUM OXIDES
METALS
NATIONAL ORGANIZATIONS
NEUTRAL-PARTICLE TRANSPORT
NEUTRON REACTIONS
NEUTRON SPECTRA
NEUTRON TRANSPORT
NONMETALS
NORTH AMERICA
NUCLEAR DATA COLLECTIONS
NUCLEAR REACTIONS
NUCLEON REACTIONS
NUMERICAL DATA
OXIDES
OXYGEN
OXYGEN COMPOUNDS
RADIATION TRANSPORT
SPECIFICATIONS
SPECTRA
STAINLESS STEELS
STEELS
THERMONUCLEAR REACTOR WALLS
THERMONUCLEAR REACTORS
USA