Analysis of large liquid-metal fast breeder reactor critical experiments by improved methods
Journal Article
·
· Nucl. Sci. Eng.; (United States)
OSTI ID:6049195
To solve the problems encountered in the analysis of the large homogeneous and heterogeneous fast critical assemblies, Zero-Power Plutonium Reactor (ZPPR) 9, 10, and 13, the authors have revisited the analysis using improved methods. Two-dimensional cell calculations, cell calculations using multidrawer cell models, and three-dimensional transport theory core calculations were introduced. Using these methods, the discrepancies in the calculation-to-experiment (C/E) values of kappa/sub eff/ for the fast critical assemblies was reduced. The use of the multidrawer model reduced the C/E spatial dependency of the control rod worths in the ZPPR-10 cores. To investigate the remaining problems of the spatial dependence of the C/E values of reaction rate distribution and control rod worth, the authors have adjusted a cross-section set obtained from the JENDL-2 library using the integral experiments. The cross-section changes, particularly for the diffusion coefficient, /sup 238/U scattering and capture, and /sup 239/Pu fission cross sections, have corrected the spatial dependence, as well as the overestimation of the /sup 239/U capture to /sup 239/Pu fission rate ratio and sodium void worth.
- Research Organization:
- Osaka Univ., Dept. of Nuclear Engineering, Osaka (JP); Power Reactor and Nuclear Fuel Development Corp., Tokyo (JP)
- OSTI ID:
- 6049195
- Journal Information:
- Nucl. Sci. Eng.; (United States), Journal Name: Nucl. Sci. Eng.; (United States) Vol. 100:4; ISSN NSENA
- Country of Publication:
- United States
- Language:
- English
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALPHA DECAY RADIOISOTOPES
BREEDER REACTORS
CHARGED-PARTICLE TRANSPORT THEORY
CHEMICAL ANALYSIS
CROSS SECTIONS
DIFFUSION
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RADIATION SCATTERING ANALYSIS
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REACTOR CORES
REACTOR SAFETY EXPERIMENTS
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THREE-DIMENSIONAL CALCULATIONS
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210500 -- Power Reactors
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22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220700 -- Nuclear Reactor Technology-- Plutonium & Isotope Production Reactors
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ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALPHA DECAY RADIOISOTOPES
BREEDER REACTORS
CHARGED-PARTICLE TRANSPORT THEORY
CHEMICAL ANALYSIS
CROSS SECTIONS
DIFFUSION
EPITHERMAL REACTORS
EVEN-EVEN NUCLEI
EVEN-ODD NUCLEI
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FISSION RATIO
FUEL ASSEMBLIES
HEAVY NUCLEI
ISOTOPES
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
NONDESTRUCTIVE ANALYSIS
NUCLEI
PLUTONIUM 239
PLUTONIUM ISOTOPES
PLUTONIUM REACTORS
RADIATION SCATTERING ANALYSIS
RADIOISOTOPES
REACTOR COMPONENTS
REACTOR CORES
REACTOR SAFETY EXPERIMENTS
REACTORS
RESEARCH AND TEST REACTORS
THREE-DIMENSIONAL CALCULATIONS
TRANSPORT THEORY
TWO-DIMENSIONAL CALCULATIONS
URANIUM 238
URANIUM ISOTOPES
YEARS LIVING RADIOISOTOPES
ZERO POWER REACTORS