Experimental study of the large-scale axially heterogeneous liquid-metal fast breeder reactor at the fast critical assembly: Power distribution measurements and their analyses
- 1. Japan Atomic Energy Research Institute, Tokai-mura, Ibaraki-ken (Japan)
- 2. Energy Research Lab., Hitachi, Ltd., Moriyama-cho, Hitachi-shi, Ibaraki-ken (Japan)
Description
Power distributions of the large-scale axially heterogeneous liquid-metal fast breeder reactor were studied by using the experiment results of fast critical assemblies XI, XII, and XIII and the results of their analyses. The power distributions were examined by the gamma-scanning method and fission rate measurements using /sup 239/Pu and /sup 238/U fission counters and the foil irradiation method. In addition to the measurements in the reference core, the power distributions were measured in the core with a control rod inserted and in a modified core where the shape of the internal blanket was determined by the radial boundary. The calculation was made by using JENDL-2 and the Japan Atomic Energy Research Institute's standard calculation system for fast reactor neutronics. The power flattening trend, caused by the decrease of the fast neutron flux, was observed in the axial and radial power distributions. The effect of the radial boundary shape of the internal blanket on the power distribution was determined in the core. The thickness of the internal blanket was reduced at its radial boundary. The influence of the internal blanket was observed in the power distributions in the core with a control rod inserted. The calculation predicted the neutron spectrum harder in the internal blanket. In the radial distributions of /sup 239/Pu fission rates, the space dependency of the calculated-to-experiment values was found at the active core close to the internal blanket
Additional details
Publishing Information
- Journal Title
- Nuclear Science and Engineering
- Journal Volume
- 100
- Journal Issue
- 4
- Series
- Nucl. Sci. Eng.
- Journal Page Range
- 496-506
- ISSN
- 0029-5639
- CODEN
- NSENA
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 20057400
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- ALGORITHMS; CRITICALITY; EDUCATIONAL FACILITIES; EXPERIMENTAL DATA; FISSION RATIO; FUEL ASSEMBLIES; FUEL RODS; GAMMA DETECTION; JAPAN; LMFBR TYPE REACTORS; NEUTRON FLUX; PLUTONIUM 239; POWER DISTRIBUTION; REACTOR CORES; REACTOR SAFETY EXPERIMENTS; RESEARCH PROGRAMS; URANIUM 238
- Descriptors DEC
- ACTINIDE NUCLEI; ALPHA DECAY RADIOISOTOPES; ASIA; BREEDER REACTORS; DATA; DETECTION; DEVELOPED COUNTRIES; DISTRIBUTION; EPITHERMAL REACTORS; EVEN-EVEN NUCLEI; EVEN-ODD NUCLEI; FAST REACTORS; FBR TYPE REACTORS; FUEL ELEMENTS; HEAVY NUCLEI; INFORMATION; ISOTOPES; LIQUID METAL COOLED REACTORS; NUCLEI; NUMERICAL DATA; PLUTONIUM ISOTOPES; RADIATION DETECTION; RADIATION FLUX; RADIOISOTOPES; REACTOR COMPONENTS; REACTORS; SPATIAL DISTRIBUTION; SPONTANEOUS FISSION RADIOISOTO; URANIUM ISOTOPES; YEARS LIVING RADIOISOTOPES