Application of three-dimensional transport code to the analysis of the neutron streaming experiment
Conference
·
OSTI ID:6492768
This paper summarized the calculational results of neutron streaming through a Clinch River Breeder Reactor (CRBR) Prototype coolant pipe chaseway. Particular emphasis is placed on results at bends in the chaseway. Calculations were performed with three three-dimensional codes: the discrete ordinates radiation transport code TORT and Monte Carlo radiation transport code MORSE, which were developed by Oak Ridge National Laboratory (ORNL), and the discrete ordinates code ENSEMBLE, which was developed in Japan. The purpose of the calculations is not only to compare the calculational results with the experimental results, but also to compare the results of TORT and MORSE with those of ENSEMBLE. In the TORT calculations, two types of difference methods, weighted-difference method was applied in ENSEMBLE calculation. Both TORT and ENSEMBLE produced nearly the same calculational results, but differed in the number of iterations required for converging each neutron group. Also, the two types of difference methods in the TORT calculations showed no appreciable variance in the number of iterations required. However, a noticeable disparity in the computer times and some variation in the calculational results did occur. The comparisons of the calculational results with the experimental results, showed for the epithermal neutron flux generally good agreement in the first and second legs and at the first bend where the two-dimensional modeling might be difficult. Results were fair to poor along the centerline of the first leg near the opening to the second leg because of discrete ordinates ray effects. Additionally, the agreement was good throughout the first and second legs for the thermal neutron region. Calculations with MORSE were made. These calculational results and comparisons are described also. 8 refs., 4 figs.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- Sponsoring Organization:
- DOE/NE
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 6492768
- Report Number(s):
- CONF-901101-49; ON: DE91004400
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
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22 GENERAL STUDIES OF NUCLEAR REACTORS
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99 GENERAL AND MISCELLANEOUS
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BREEDER REACTORS
CLINCH RIVER BREEDER REACTOR
COMPARATIVE EVALUATIONS
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EPITHERMAL REACTORS
FAST REACTORS
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LIQUID METAL COOLED REACTORS
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NEUTRAL-PARTICLE TRANSPORT
NEUTRON FLUX
NEUTRON TRANSPORT
PIPES
POWER REACTORS
RADIATION FLUX
RADIATION TRANSPORT
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
SHIELDING
SODIUM COOLED REACTORS
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THREE-DIMENSIONAL CALCULATIONS
210500* -- Power Reactors
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22 GENERAL STUDIES OF NUCLEAR REACTORS
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99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
BREEDER REACTORS
CLINCH RIVER BREEDER REACTOR
COMPARATIVE EVALUATIONS
COMPUTER CALCULATIONS
COMPUTER CODES
COOLING SYSTEMS
E CODES
ENERGY SYSTEMS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
M CODES
NEUTRAL-PARTICLE TRANSPORT
NEUTRON FLUX
NEUTRON TRANSPORT
PIPES
POWER REACTORS
RADIATION FLUX
RADIATION TRANSPORT
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
SHIELDING
SODIUM COOLED REACTORS
T CODES
THREE-DIMENSIONAL CALCULATIONS