Modeling & Analysis of Core Debris Recriticality During Hypothetical Severe Accidents in the Advanced Neutron Source Reactor
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
This paper discusses salient aspects of severe-accident-related recriticality modeling and analysis in the Advanced Neutron Source (ANS) reactor. The development of an analytical capability using the KENO5A-SCALE system is described including evaluation of suitable nuclear cross-section sets to account for the effects of system geometry, mixture temperature, material dispersion and other thermal-hydraulic conditions. Benchmarking and validation efforts conducted with KENO5-SCALE and other neutronic codes against critical experiment data are described. Potential deviations and biases resulting from use of the 16-group Hansen-Roach library is shown. A comprehensive test matrix of calculations to evaluate the threat of a criticality event in the ANS is described. Strong dependencies on geometry, material constituents, and thermal-hydraulic conditions are described. The introduction of designed mitigative features is described.
- Research Organization:
- Oak Ridge National Lab. (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:
- 10183463
- Report Number(s):
- CONF-9303103-2; ON: DE94018939; TRN: 94:018986
- Resource Relation:
- Conference: 2. Japan Society of Mechanical Engineers (JSME)/American Society of Mechanical Engineers (ASME) Joint International Conference on Nuclear Engineering (ICONE-2), San Francisco, CA (United States), 22-24 Mar 1993; Other Information: PBD: Oct 1992
- Country of Publication:
- United States
- Language:
- English
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Modeling and analysis of core-debris recriticality during hypothetical severe accidents in the advanced neutron source reactor
Modeling and analysis of core debris recriticality during hypothetical severe accidents in the Advanced Neutron Source Reactor
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