Thermal-hydraulic process modeling in risk analysis: an assessment of the relevant systems, structures, and phenomena
The MELCOR project is developing a new generation of risk assessment computer programs for analysis of severe accidents at nuclear power plants. This document details the findings in the thermal-hydraulic areas for PWRs and areas common to both PWRs and BWRs. The study was performed by specialists from each of the various nuclear plant design or analysis areas where thermal-hydraulics is important. The study found that the current level of thermal-hydraulic modeling that exists for performing risk assessments is typified by the modeling in the MARCH code. This level of modeling was found to be inadequate for MELCOR because of inconsistent or nonexistent modeling of important phenomena, particularly invessel phenomena, systems, and structures. Pressurized water reactor modeling was found to be more complete than modeling for boiling water reactor designs, particularly in containment. Finally, although reactor cavity modeling was considered essential for risk assessments, the lack of adequate modeling found for the cavity was identified as a serious impediment to the development of second-generation risk codes.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (USA)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 6060951
- Report Number(s):
- NUREG/CR-3986; SAND-84-1219; ON: TI85003989
- Country of Publication:
- United States
- Language:
- English
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