Thermohydraulic processes in the hermozone and behavior of fission products. Analysis of the spread of the melt and its interaction with concrete.
(The program is also used coupled with ATHLET or ATHLET-CD)
Experience in using computer programs, verification and validation
Specialized computer programs are the main tool in performing the main tasks of ENPRO CONSULT. The company has acquired the necessary computer systems and codes. Highly professional IT specialists maintain the operating systems (MS Windows and Linux) and maintain the security of information resources in the local network.
If necessary, Version Control System (VCS) is widely used.
Extensive experience has been accumulated in the field of modeling, verification and validation of models, including documentation and archiving.
Based on ATHLET and the ATLAS visualization system, an analysis simulator for units 5 and 6 at Kozloduy NPP has been developed. It is a powerful tool for verification of emergency instructions. The simulator includes models of the VVER-1000 control systems and provides the opportunity for interactive control.
Below is a brief description of the computer programs used for safety design and analysis.
COCOSYS
COCOSYS
Thermohydraulic processes in the hermozone and behavior of fission products. Analysis of the spread of the melt and its interaction with concrete.
(The program is also used coupled with ATHLET or ATHLET-CD)
COSYMA, GENII
COSYMA, GENII
Assessment of radiation consequences
DYN3D
DYN3D
3-D neutron kinetics with thermohydraulics
KWUROHR, FRACTURE SEARCH
KWUROHR, FRACTURE SEARCH
Estimation of the residual resource
MCNP
MCNP
Neutron-physical code (Monte Carlo method)
MELCOR, ATHLET-CD
MELCOR, ATHLET-CD
Analysis of severe accidents
RELAP, ATHLET, TRACE
RELAP, ATHLET, TRACE
System thermohydraulic programs for the analysis of transient processes and accidents for the assessment of the safety of nuclear power plants
SAP2000, PIPEPLUS, PIPESTRESS CAESAR, ANSYS
SAP2000, PIPEPLUS, PIPESTRESS CAESAR, ANSYS
Design and calculation of structures and pipelines
SCALE 6.2
SCALE 6.2
Complex of neutron-physical codes
SUSA
SUSA
Assessment of the uncertainty and sensitivity of the results of calculations
UHS
UHS
Analysis of the capacity and efficiency of spray pools
VISIPLAN, MICROSHIELD
VISIPLAN, MICROSHIELD
Calculation and optimization of dose load
COCOSYS
COCOSYS
Thermohydraulic processes in the hermozone and behavior of fission products. Analysis of the spread of the melt and its interaction with concrete.
(The program is also used coupled with ATHLET or ATHLET-CD)
COSYMA, GENII
COSYMA, GENII
Assessment of radiation consequences
DYN3D
DYN3D
3-D neutron kinetics with thermohydraulics
KWUROHR, FRACTURE SEARCH
KWUROHR, FRACTURE SEARCH
Estimation of the residual resource
MCNP
MCNP
Neutron-physical code (Monte Carlo method)
MELCOR, ATHLET-CD
MELCOR, ATHLET-CD
Analysis of severe accidents
RELAP, ATHLET, TRACE
RELAP, ATHLET, TRACE
System thermohydraulic programs for the analysis of transient processes and accidents for the assessment of the safety of nuclear power plants
SAP2000, PIPEPLUS, PIPESTRESS CAESAR, ANSYS
SAP2000, PIPEPLUS, PIPESTRESS CAESAR, ANSYS
Design and calculation of structures and pipelines
SCALE 6.2
SCALE 6.2
Complex of neutron-physical codes
SUSA
SUSA
Assessment of the uncertainty and sensitivity of the results of calculations
UHS
UHS
Analysis of the capacity and efficiency of spray pools
VISIPLAN, MICROSHIELD
VISIPLAN, MICROSHIELD
Calculation and optimization of dose load
Assessment of radiation consequences
3-D neutron kinetics with thermohydraulics
Estimation of the residual resource
Neutron-physical code (Monte Carlo method)
Analysis of severe accidents
System thermohydraulic programs for the analysis of transient processes and accidents for the assessment of the safety of nuclear power plants
Design and calculation of structures and pipelines
Complex of neutron-physical codes
Assessment of the uncertainty and sensitivity of the results of calculations
Analysis of the capacity and efficiency of spray pools
Calculation and optimization of dose load
The input data packages for the various computer codes are constantly updated, during which strict verification is performed. Comparative analyses with different programs are often carried out in order to verify the models. Validation by comparison with measured data at the plant and records of operational events is also performed when necessary.