Preliminary Benchmark Evaluation of Japan’s High Temperature Engineering Test Reactor
A benchmark model of the initial fully-loaded start-up core critical of Japan’s High Temperature Engineering Test Reactor (HTTR) was developed to provide data in support of ongoing validation efforts of the Very High Temperature Reactor Program using publicly available resources. The HTTR is a 30 MWt test reactor utilizing graphite moderation, helium coolant, and prismatic TRISO fuel. The benchmark was modeled using MCNP5 with various neutron cross-section libraries. An uncertainty evaluation was performed by perturbing the benchmark model and comparing the resultant eigenvalues. The calculated eigenvalues are approximately 2-3% greater than expected with an uncertainty of ±0.70%. The primary sources of uncertainty are the impurities in the core and reflector graphite. The release of additional HTTR data could effectively reduce the benchmark model uncertainties and bias. Sensitivity of the results to the graphite impurity content might imply that further evaluation of the graphite content could significantly improve calculated results. Proper characterization of graphite for future Next Generation Nuclear Power reactor designs will improve computational modeling capabilities. Current benchmarking activities include evaluation of the annular HTTR cores and assessment of the remaining start-up core physics experiments, including reactivity effects, reactivity coefficient, and reaction-rate distribution measurements. Long term benchmarking goals might include analyses of the hot zero-power critical, rise-to-power tests, and other irradiation, safety, and technical evaluations performed with the HTTR.
- Research Organization:
- Idaho National Lab. (INL), Idaho Falls, ID (United States)
- Sponsoring Organization:
- DOE - NE
- DOE Contract Number:
- DE-AC07-99ID-13727
- OSTI ID:
- 957537
- Report Number(s):
- INL/CON-08-14846; TRN: US1000629
- Resource Relation:
- Conference: 2009 International Conference on Mathematics, Computational Methods and Reactor Physics,The Saratoga Hotel & Conference Center, Saratoga Springs, New York, USA,05/03/2009,05/07/2009
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BENCHMARKS
EIGENVALUES
ETR REACTOR
GRAPHITE
HELIUM
HOTELS
IMPURITIES
IRRADIATION
NEUTRONS
NUCLEAR POWER
PHYSICS
REACTION KINETICS
REACTIVITY COEFFICIENTS
SAFETY
SENSITIVITY
START-UP
TEST REACTORS
VALIDATION
Benchmark
Graphite Reactor
HTTR
IRPhEP
Prismatic Fuel
TRISO