Progress in MELCOR development and assessment
- Sandia National Labs., Albuquerque, NM (United States). Modeling and Analysis Dept.
MELCOR models the progression of severe accidents in light water reactor nuclear power plants. Recent efforts in MELCOR development to incorporate CORCON-Mod3 models for core-concrete interactions, new models for advanced reactors, and improvements to several other existing models have resulted in release of MELCOR 1.8.3. In addition, continuing efforts to expand the code assessment database have filled in many of the gaps in phenomenological coverage. Efforts are now under way to develop models for chemical interactions of fission products with structural surfaces and for reactions of iodine in the presence of water, and work is also in progress to improve models for the scrubbing of fission products by water pools, the chemical reactions of boron carbide with steam, and the coupling of flow blockages with the hydrodynamics. Several code assessment analyses are in progress, and more are planned.
- Research Organization:
- Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States); Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC04-94AL85000
- OSTI ID:
- 46599
- Report Number(s):
- SAND-95-0561C; CONF-941074-2; ON: DE95009590; TRN: 95:010987
- Resource Relation:
- Conference: 21. water reactor safety information meeting, Washington, DC (United States), 25-27 Oct 1994; Other Information: PBD: [1995]
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS
99 MATHEMATICS
COMPUTERS
INFORMATION SCIENCE
MANAGEMENT
LAW
MISCELLANEOUS
WATER COOLED REACTORS
REACTOR ACCIDENTS
M CODES
MODIFICATIONS
COMPUTERIZED SIMULATION
C CODES
REACTOR CORES
CHEMICAL REACTIONS
FISSION PRODUCTS
IODINE
BORON CARBIDES
WATER TREATMENT
NUCLEAR FUELS
CONTAINMENT SPRAY SYSTEMS
LOSS OF COOLANT
S CODES