Validation Studies Using Joint USDOE/PNC Critical Experiments
Conference
·
OSTI ID:7026755
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Validation studies have been performed in the United States and Japan using the SCALE-2 computer code system with benchmark data obtained from 46 critical experiments. The experiments spanned the range of neutron spectra from a very undermoderated condition (H/Pu ratio = 22) to a very overmoderated condition (H/Pu ratio = 2220). The experiments are divided into four sets: (1) heterogeneous mixed-oxide fuel pin arrays moderated by organic and aqueous solutions, (2) limiting critical concentration experiments, (3) basic cylinder and slab geometries with various reflection conditions, and (4) annular cylinder with various fixed-geometry poisons. Based on computations performed at the Oak Ridge National Laboratory (ORNL) with the KENO code and a 27 energy-group cross-section library, the average calculated k-effective for the 46 experiments was found to be 1.004. Calculated k-effectives ranged from 0.991 to 1.018, and the standard deviation of these results was 0.006. The Power Reactor and Nuclear Fuel Development Corporation (PNC) staff have obtained similar k-effective results in their validation studies. The good agreement between experiment and calculation gives confidence that the calculation methods and cross-section data can be applied to similar plant conditions.
- Research Organization:
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 7026755
- Report Number(s):
- CONF-871045-14; ON: DE89001873
- Country of Publication:
- United States
- Language:
- English
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LIQUID METAL COOLED REACTORS
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COMPUTER CALCULATIONS
COMPUTER CODES
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CRITICALITY
CROSS SECTIONS
Calculation Methods
DATA
ENERGY SOURCES
EPITHERMAL REACTORS
EXPERIMENTAL DATA
FAST REACTORS
FBR TYPE REACTORS
FUEL ELEMENTS
FUEL PINS
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JAPANESE ORGANIZATIONS
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LIQUID METAL COOLED REACTORS
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MATERIALS
MODERATORS
NATIONAL ORGANIZATIONS
NUCLEAR FUELS
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REACTOR COMPONENTS
REACTOR MATERIALS
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RESEARCH PROGRAMS
S CODES
SCALE-2 Computer Code System
SPENT FUELS
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US DOE
US ORGANIZATIONS
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