An assessment of the CORCON-MOD3 code. Part 1: Thermal-hydraulic calculations
- Russian Academy of Sciences, Moscow (Russian Federation). Inst. of Nuclear Safety
- Russian Research Center, Moscow (Russian Federation). Kurchatov Inst.
This report deals with the subject of CORCON-Mod3 code validation (thermal-hydraulic modeling capability only) based on MCCI (molten core concrete interaction) experiments conducted under different programs in the past decade. Thermal-hydraulic calculations (i.e., concrete ablation, melt temperature, melt energy, concrete temperature, and condensible and non-condensible gas generation) were performed with the code, and compared with the data from 15 experiments, conducted at different scales using both simulant (metallic and oxidic) and prototypic melt materials, using different concrete types, and with and without an overlying water pool. Sensitivity studies were performed in a few cases involving, for example, heat transfer from melt to concrete, condensed phase chemistry, etc. Further, special analysis was performed using the ACE L8 experimental data to illustrate the differences between the experimental and the reactor conditions, and to demonstrate that with proper corrections made to the code, the calculated results were in better agreement with the experimental data. Generally, in the case of dry cavity and metallic melts, CORCON-Mod3 thermal-hydraulic calculations were in good agreement with the test data. For oxidic melts in a dry cavity, uncertainties in heat transfer models played an important role for two melt configurations--a stratified geometry with segregated metal and oxide layers, and a heterogeneous mixture. Some discrepancies in the gas release data were noted in a few cases.
- Research Organization:
- US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Office of Nuclear Regulatory Research
- Sponsoring Organization:
- Nuclear Regulatory Commission, Washington, DC (United States)
- OSTI ID:
- 383656
- Report Number(s):
- NUREG/IA-0129-Pt.1; ON: TI97000274; TRN: 96:029122
- Resource Relation:
- Other Information: DN: International Agreement Report; PBD: Sep 1996
- Country of Publication:
- United States
- Language:
- English
Similar Records
OECD MCCI project final report, February 28, 2006.
OECD/MCCI 2-D Core Concrete Interaction (CCI) tests : final report February 28, 2006.
Related Subjects
COMPUTERS
INFORMATION SCIENCE
MANAGEMENT
LAW
MISCELLANEOUS
22 NUCLEAR REACTOR TECHNOLOGY
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS
MELTDOWN
C CODES
WATER COOLED REACTORS
CORIUM
NUCLEAR POWER PLANTS
HYDRAULICS
COMPARATIVE EVALUATIONS
REACTOR SAFETY EXPERIMENTS
SENSITIVITY ANALYSIS
CHEMICAL REACTIONS
MODIFICATIONS
DATA