On SCALE Validation for PBR Analysis
- ORNL
Studies were performed to assess the capabilities of the SCALE code system to provide accurate cross sections for analyses of pebble bed reactor configurations. The analyzed configurations are representative of fuel in the HTR-10 reactor in the first critical core and at full power operation conditions. Relevant parameters-multiplication constant, spectral indices, few-group cross sections-are calculated with SCALE for the considered configurations. The results are compared to results obtained with corresponding consistent MCNP models. The code-to-code comparison shows good agreement at both room and operating temperatures, indicating a good performance of SCALE for analysis of doubly heterogeneous fuel configurations. The development of advanced methods and computational tools for the analysis of pebble bed reactor (PBR) configurations has been a research area of renewed interest for the international community during recent decades. The PBR, which is a High Temperature Gas Cooled Reactor (HTGR) system, represents one of the potential candidates for future deployment throughout the world of reactor systems that would meet the increased requirements of efficiency, safety, and proliferation resistance and would support other applications such as hydrogen production or nuclear waste recycling. In the U.S, the pebble bed design is one of the two designs under consideration by the Next Generation Nuclear Plant (NGNP) Program.
- Research Organization:
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- AC05-00OR22725
- OSTI ID:
- 980709
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
CROSS SECTIONS
DESIGN
EFFICIENCY
FUELS
GAS COOLED REACTORS
HTR-10 REACTOR
HYDROGEN PRODUCTION
OPERATION
PEBBLE BED REACTORS
PERFORMANCE
PLANTS
POTENTIALS
POWER
PROLIFERATION
RADIOACTIVE WASTES
REACTORS
RECYCLING
SAFETY
SUPPORTS
TEMPERATURE RANGE 0400-1000 K
VALIDATION