Severe accident analysis

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Severe Accident Analysis Code Development

Research Objectives

  • To develop an integrated severe accident analysis code system with domestic technology
  • To have competiveness against other well known global computer codes
  • To have technical self-reliance for export without obligations

R&D Status

  • The “Development of Severe Accident Analysis Code and Methodology” project launched in 2011.7, and finished in 2017.6 under the frame of 2 phases of 3 years each.
  • KHNP manages the overall project and KAERI and FNC joined the project as participating organizations. KAERI and FNC are in charge of model development in the RCS and in the containment, respectively. KAERI also developed the fission product analysis module in the nuclear power. FNC integrates all modules into the single code package

Major Outcomes

  • 1) CSPACE:
  • Models severe accident phenomena in the reactor coolant system
  • Consists of COMPASS for the core degradation and SPACE for the system thermal hydraulics
  • 2) SIRIUS
  • Models fission product behavior in the reactor coolant system as well as in the containment
  • 3) CINEMA
  • Integrates CSPAE, SACAP (for the containment) and SIRIUS into a single code package
  • Can calculate the severe accident scenarios from the steady state, core degradation and RPV failure, to the containment failure with fission product distribution information in a single frame
Severe-accident1

Major components of CINEMA

Severe-accident2

Major components of CINEMA

Future Outlook

  • To be used as a reservoir or a platform for collection of all kinds domestic technologies including data for the Korean specific plant features for severe accident management
  • To be applied for the actual plant analysis including SMART and CANDU plants along with model improvement and new model addition.

Severe Accident Analysis for SMART-PPE

Objectives

  • Technology Development on Severe Accident Analysis in SMART (System Integrated Modular Advanced ReacTor)-PPE (Pre-Project Engineering)
  • Computer Code Development of CINEMA-SMART for Severe Accident Sequence Analysis
  • Severe Accident Sequence Analysis using MELCOR and CINEMA (Code for INtegrated severe accidEnt Management Analysis)-SMART
  • Analysis of Severe Accident Issues
  • Write-up PSAR Section 19.2 for SMART
  • UCB (Human Capability Buildup) for K.A. CARE Engineers of Saudi Arabia

R&D Status

  • Computer Code Development for Severe Accident Sequence Analysis
  • Development of CINEMA-SMART
  • Preparation of SMART Plant Model for Severe Accident Analysis
  • Severe Accident Sequence Analysis using MELCOR and CINEMA-SMART
  • Station Blackout (SBO)
  • Total Loss Of Feed Water (TLOFW)
  • Small break Loss Of Coolant Accident (SLOCA) without safety injection
  • Analysis of Severe Accident Issues
  • In-Vessel corium Retention through External Reactor Vessel Cooling (IVR-ERVC)
  • In-Vessel Depressurization to prevent High Pressure Melt Ejection (HPME)
  • Direct Containment Heating (DCH) by HPME
  • In-Vessel and Ex-Vessel Steam Explosions
  • Molten Core Concrete Interaction (MCCI) in Reactor Cavity
  • Hydrogen Distribution and Burning in Containment

Outcomes & Perspectives

  • CINEMA-SMART Development for Severe Accident Sequence Analysis in SMART
  • PSAR Section 19.2 for SMART
  • Resolution of Severe Accident Issues in SMART
  • Contribution for International Design Certification of SMART

Computer Codes for Severe Accident Analysis in SMART

Title Computer Code
SMART330 SSAR SMART-PPE
Severe Accident Sequence Analysis MELCOR MELCOR and CINEMA-SMART
IVR-ERVC ATOP(In-Vessel), ANSYS(Vessel), RELAP5(Ex-Vessel) SIMPLE, ANSYS, SPACE
DCH and In-Vessel Depressurization Analysis TCE(DCH), MELCOR(RCS Dep.) Modified TCE/LHS, CINEMA-SMART
Hydrogen Distribution & Burning Analysis in Containment MELCOR CINEMA-SMART, OpenFOAM
Steam Explosion Analysis TEXAS-V(SE), ABAQUS (Structure Integrity) TEXAS-V, ANSYS
MCCI Analysis MELCOR, Meltspread CINEMA-SMART