CORCON-MOD3: An integrated computer model for analysis of molten core-concrete interactions. User`s manual
- Sandia National Labs., Albuquerque, NM (United States)
The CORCON-Mod3 computer code was developed to mechanistically model the important core-concrete interaction phenomena, including those phenomena relevant to the assessment of containment failure and radionuclide release. The code can be applied to a wide range of severe accident scenarios and reactor plants. The code represents the current state of the art for simulating core debris interactions with concrete. This document comprises the user`s manual and gives a brief description of the models and the assumptions and limitations in the code. Also discussed are the input parameters and the code output. Two sample problems are also given.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Research; Sandia National Labs., Albuquerque, NM (United States)
- Sponsoring Organization:
- Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC04-94AL85000
- OSTI ID:
- 10195017
- Report Number(s):
- NUREG/CR--5843; SAND--92-0167; ON: TI94003134
- Country of Publication:
- United States
- Language:
- English
Similar Records
CORCON-MOD3 validation study
CORCON-MOD2: a computer program for analysis of molton-core concrete interactions
CORCON: molten-fuel/concrete interactions code
Conference
·
Thu Dec 31 23:00:00 EST 1992
· Transactions of the American Nuclear Society; (United States)
·
OSTI ID:7128858
CORCON-MOD2: a computer program for analysis of molton-core concrete interactions
Technical Report
·
Wed Aug 01 00:00:00 EDT 1984
·
OSTI ID:6330314
CORCON: molten-fuel/concrete interactions code
Conference
·
Thu Dec 31 23:00:00 EST 1981
·
OSTI ID:6756645
Related Subjects
050700
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220100
99 GENERAL AND MISCELLANEOUS
990200
C CODES
COMPUTERIZED SIMULATION
CONTAINMENT
CORIUM
FUEL-CLADDING INTERACTIONS
FUELS PRODUCTION AND PROPERTIES
MANUALS
MATHEMATICS AND COMPUTERS
MELTDOWN
THEORY AND CALCULATION
WATER COOLED REACTORS
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220100
99 GENERAL AND MISCELLANEOUS
990200
C CODES
COMPUTERIZED SIMULATION
CONTAINMENT
CORIUM
FUEL-CLADDING INTERACTIONS
FUELS PRODUCTION AND PROPERTIES
MANUALS
MATHEMATICS AND COMPUTERS
MELTDOWN
THEORY AND CALCULATION
WATER COOLED REACTORS