Safety analysis code (Virtual Nuclear Power Plant)

> Research & Development > R&D Activities > Safety analysis code

Component-Scale Safety Analysis Code: CUPID

Safety-analysis-code2
Safety-analysis-code3

Objectives

  • Development of CUPID for steady state or transient analysis of single- and two-phase flows in nuclear reactors in component- or CFD-scale
  • Three-dimensional two-fluid and three-field model is applied
  • FVM (Finite Volume Method) with unstructured grid for complicated geometry
  • Parallel computing for a large scale calculation
  • Development of multi-scale and multi-physics analysis code based on CUPID
  • Multi-scale analysis of system and component scales
  • Multi-physics analysis of thermal hydraulics and core kinetics

R&D Status

  • 1st phase (2007~2011)
  • Development of a numerical method for 3-dimensional two-fluid model with unstructured grid
  • Verification of the numerical method
  • 2nd phase (2012~2017)
  • Implementation of physical models and validation
  • Application to safety issues where multi-dimensional effects are important

Outcomes & Perspectives

  • CUPID: 3-dimensional two-phase flow analysis code in component- or CFD-scale
  • CUPID/MARS: Coupled code of system TH code (MARS) and component scale analysis code (CUPID)
  • CUPID/MASTER, CUPID/DeCART: Coupled code of CUPID and neutronics codes (MASTER and DeCART)
  • CUPID-SG: PWR steam generator analysis code based on CUPID
  • 3-dimensional reactor core TH safety and containment analysis technologies are now being developed using CUPID
  • CUPID will be used as a base code for the multi-scale and physics analysis of PWRs
cupid_img3
cupid_img
cupid_img2

Multi-Field System Code Development : SPACE

Safety-analysis-code1

Objectives

  • To replace the outdated foreign vendor codes, SPACE code development program was launched in 2006 and has been successfully preceded since then to develop a best-estimate thermal-hydraulics system analysis code for a licensing application of pressurized water reactors.
  • The developmental requirements for the SPACE code are:
  • Adoption of two-fluid, three-field governing equation. A dispersed liquid phase treated as a separate field.
  • One-dimensional and multi-dimensional flow simulation capability
  • Programming language : C++ language
  • To reach the goal, the Several research and industrial organizations in Korea are participated in the collaboration of the SPACE code development program.

R&D Status

  • The SPACE code has been developed and validated successfully until 2013 and the topical report with complete set of manuals was submitted to regulatory body for licensing review in late 2013. Since then, SPACE code developers and the reviewers are exchanging the questions and answers concerning to the topical reports. Finally, licensing approval for the SPACE code was obtained in March, 2017.
  • The project to extend SPACE analysis capability to design extension condition (DEC) is started. As a part of project, FRAPTRAN code will be integrated into SPACE code to predict fuel deformation during the LOCA, SBO, etc.
Safety-analysis-code6

Topical Reports

Safety-analysis-code4

Licensing Approval Document

Safety-analysis-code5

Schematics of Integrated SPACE

Outcomes & Perspectives

  • The licensed version of SPACE code will be used in new PWR reactor design.
  • The efforts to improve the calculation fidelity and time will continue to satisfy the new regulatory requirements, safety issue, etc. Our Current effort is to extend the SPACE application range to design extension condition (DEC).

SPACE-SFR/RR

Objectives

  • Development of unified safety analysis code for Sodium-cooled Fast Reactor (SFR) and Research Reactor (RR) based on the SPACE code

R&D Status

SPACE_chart-en

Outcomes & Perspectives

  • Korea own safety analysis code with analysis capability for the PWR, SFR and RR
  • Basic platform for unified safety analysis code for various type of reactors (SMR, maritime reactors, etc)
  • Code validation matrix and data base for SFR and RR
  • Performance evaluation report which will be used for licensing activities

SFR-BEPU

Objectives

  • Extension of the best-estimated plus uncertainty analysis methodology for the PGSFR design extension condition scenarios

R&D Status

  • Quantifying the uncertainty of ULOF and UTOP scenarios of PGSFR
Safety-analysis-code_img1
Safety-analysis-code_img2

Outcomes & Perspectives

  • PAPIRUS program suitable to the uncertainty quantification process
  • MIRT table for the PGSFR DEC scenarios including the model parameter uncertainty distribution band
  • Provide the platform of the BEPU of the PGSFR DEC