Adaptive Nodal Transport Methods for Reactor Transient Analysis
Develop methods for adaptively treating the angular, spatial, and time dependence of the neutron flux in reactor transient analysis. These methods were demonstrated in the DOE transport nodal code VARIANT and the US NRC spatial kinetics code, PARCS.
- Research Organization:
- Purdue Univ., West Lafayette, IN (United States)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- FG07-01ID14106
- OSTI ID:
- 850366
- Report Number(s):
- DOE/ID/14106
- Country of Publication:
- United States
- Language:
- English
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