Evaluation of HEU-Beryllium Benchmark Experiments to Improve Computational Analysis of Space Reactors

Conference · Tue Feb 08 04:00:00 EST 2011

OSTI ID:1013707

Bess, John D. ^[1]; Bledsoe, Keith C. ^[2]; Rearden, Bradley T. ^[2]

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1. Idaho National Laboratory (INL), Idaho Falls, ID (United States)
2. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

An assessment was previously performed to evaluate modeling capabilities and quantify preliminary biases and uncertainties associated with the modeling methods and data utilized in designing a nuclear reactor such as a beryllium-reflected, highly-enriched-uranium (HEU)-O₂ fission surface power (FSP) system for space nuclear power. The conclusion of the previous study was that current capabilities could preclude the necessity of a cold critical test of the FSP; however, additional testing would reduce uncertainties in the beryllium and uranium cross-section data and the overall uncertainty in the computational models. A series of critical experiments using HEU metal were performed in the 1960s and 1970s in support of criticality safety operations at the Y-12 Plant. Of the hundreds of experiments, three were identified as fast-fission configurations reflected by beryllium metal. These experiments have been evaluated as benchmarks for inclusion in the International Handbook of Evaluated Criticality Safety Benchmark Experiments (IHECSBE). Further evaluation of the benchmark experiments was performed using the sensitivity and uncertainty analysis capabilities of SCALE 6. The data adjustment methods of SCALE 6 have been employed in the validation of an example FSP design model to reduce the uncertainty due to the beryllium cross section data.

• Research Organization: Idaho National Laboratory (INL), Idaho Falls, ID (United States); 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: AC07-05ID14517
• OSTI ID: 1013707
• Report Number(s): INL/CON-10-19815
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
97 MATHEMATICS AND COMPUTING
BENCHMARKS
BERYLLIUM
CRITICALITY
CROSS SECTIONS
DESIGN
EVALUATION
FAST FISSION
FISSION
HEU
HIGHLY ENRICHED URANIUM
MANUALS
NUCLEAR POWER
Nuclear Criticality Safety Program (NCSP)
REACTORS
SAFETY
SCALE
SENSITIVITY
TESTING
TSUNAMI
URANIUM
VALIDATION
Y-12 PLANT
benchmark
beryllium
fission surface power