DB LIST

> DB LIST

VESTA (Verification of Ex-vessel Corium Stabilization)

Author
kaeri
Date
2019-05-09 15:45
Views
767
Details
Legal Name of Facility Verification of Ex-vessel Corium Stabilization
Abbreviated Name VESTA
Facility Type Radioactive Material Handling Facility, Severe Accident Research Facility
Reactor Design Reference OPR1000, APR1400, EU-APR1400
Application Nuclear Safety; Severe Accident
Current Purpose Investigation on the failure (or erosion) of various reactor materials such as sacrificial concrete of ex-vessel core catcher and penetration tubes at RPV lower head by using prototypic corium melt (max. ~ 300 kg)
Short Description Purpose & Design Features

- Resolution of various severe accident issues through interaction tests between corium melt and structural material

- Generation of massive corium melt (~300 kg) with various compositions by cold crucible induction heating technology

- Heater system operating at a power level of 450 kW and a frequency of 100 kHz

- World-class test facility with corium melt

R&D Status

- Construction in July 2010

- Jet impingement and sacrificial material interaction test for EU-APR1400 core catcher (2011 ~ 2013)

- Reactor lower vessel penetration (ICI) failure test under ERVC condition for APR1400 (2013 ~ 2016)

- Reactor lower vessel penetration (ICM-GT and CRGT) failure test for Fukushima Daiichi NPP (2014 ~ 2017)

- Ex-vessel particulate bed spreading and cooling test for operating Korean NPPs (2017 ~ 2021)

Outcomes & Perspectives

- Generation of valuable test data with corium melt

- Contribution to resolving severe accident issues

- Competent test facility for international program
Status Temporarily non-operational (under re-approval process)
Operating Organization Korea Atomic Energy Research Institute – Thermal Hydraulics and Severe Accident Research Division (KAERI - THSARD)
Operating Organization URL  
Homepage
Country Republic of Korea
Keywords Severe Accident, Prototypic Corium, Penetration Failure, Sacrificial Material Ablation
Local language Legal Name of Facility 노외 노심용융물 안정화 검증 실험장치
 

 
DB-List
Ablation Test of EU-APR1400 Sacrificial Concrete by Jet Impingement EU-APR1400_JI_SM_01 ZrO2 74 kg
EU-APR1400_JI_SM_02 ZrO2 70 kg
APR1400 ICI penetration Failure Test PW_01 Penetration weld failure with STS melt
PW_02 Penetration weld failure with metallic corium
APR1400_ICI_01 ICI Simulated Specimen, ZrO2, No ERVC, 0 barg
APR1400_ICI_02 ICI Simulated Specimen, ZrO2, No ERVC, 0 barg
APR1400_ICI_03 ICI Specimen, ZrO2, No ERVC, 1 barg
APR1400_ICI_04 ICI Specimen, ZrO2, No ERVC, 2.6 barg
APR1400_ICI_05 ICI Specimen, ZrO2_Delivery, No ERVC, 0 barg
APR1400_ICI_ERVC_01 ICI Specimen, UO2+ZrO2, ERVC, 1.8 barg
APR1400_ICI_ERVC_02 ICI Specimen, UO2+ZrO2, ERVC, 2.9 barg
BWR penetration Failure Test Fukushima_Corium_01 UO2 : Zr : ZrO2 : SUS304 : B4C = 60 : 10 : 15 : 14 : 1 (wt.%)
  Fukushima_Corium_02 UO2 : Zr : ZrO2 : SUS304 : B4C = 53 : 9 : 25 : 12 : 1 (wt.%)
  SRM/IRM UO2+ZrO2, Fukushima U1 SRM/IRM penetration
  LPRM UO2+ZrO2, Fukushima U1 LPRM penetration
  CRGT_01 UO2+ZrO2, Fukushima U1 CRGT penetration
  CRGT_02 UO2+ZrO2, Fukushima U1 CRGT penetration, reheating
 

 
Related Documents or Photo Files
File Name (Click to download) Description
File_1.pdf Introduction to PRESCO test facility
File_2.jpg Facility photo