Radionuclide Inventory and Decay Heat Quantification Methodology for Severe Accident Simulations.
- Sandia National Laboratories (SNL), Albuquerque, NM, and Livermore, CA (United States)
The MELCOR and MACCS computer codes require inputs for radionuclide inventory and decay heat in order to simulate severe accident phenomenology, source term, and consequences. Therefore, Sandia National Laboratories ( SNL ) has developed accurate and automated methods using SCALE 6 in conjunction with automation scripts to directly generate MELCOR and MACCS input records for radionuclide inventories and decay heating. Consistent information between the two codes is essential for realistic modeling of severe nuclear accidents it is the radionuclide inventory and decay power that are the principal safety problems of any severe accident that assumes successful reactor shutdown. SNL plans to conduct best-estimate calculations and uncertainty analyses using MELCOR and MACCS for several reactors, including units 1 - 3 of Fukushima Daiichi, which entail accurate and technically-scrutable information for the input models. The SNL methodology for generating radionuclide and decay power inputs directly from SCALE6 calculations is mostly presented in the context of supporting Fukushima modeling efforts. Furthermore, certain historical assumptions used by MELCOR and MACCS in the abstraction of radionuclide classes and their properties are reviewed, and these assumptions are compared to modern code predictions by SCALE6.
- Research Organization:
- Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States)
- Sponsoring Organization:
- USDOE Office of Nuclear Energy (NE)
- DOE Contract Number:
- AC04-94AL85000
- OSTI ID:
- 1771263
- Report Number(s):
- SAND--2014-17667; 685532
- Country of Publication:
- United States
- Language:
- English
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