Plan KINS Research Status and

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KINS Research Status and Plan

December 12, 2011

Safety Research Division

SEUL, Kwang Won, Ph.D. (k240skw@kins.re.kr)

GRS-KINS WORKSHOP, Cologne, Germany

I. Background

II. Status of NPPs in Korea III. Research Circumstances

IV. Safety Regulatory Researches in SRD

1. Thermal-Hydraulic and Safety Analysis Research 2. Severe Accident Research

3. Engineering System Research 4. Radiation Protection Research 5. GEN IV Reactor Research

V. Interesting Areas for Cooperation

Research Objectives of Safety Research Division(SRD)

• To resolve safety and technical issues identified in reviewing the plant designs and managing the operating plants

• To establish regulatory infrastructure such as licensing procedures, regulatory requirements and guidance to the level of global safety standards

SRD Organization and Research Areas

• 5 Departments with 51 staff

① Technical Standard Department

② Thermal-Hydraulic Research Department

③ Engineering Research Department

④ Radiation Research Department

⑤ Future Reactor Research Department

 Safety Issue PM and Regulatory Audit PM

• Running over 20 R&D Projects a year

4 Nuclear Sites, 1 Radioactive Waste Repository Site

• KN/SKN(8), YGN(6), UJN/SUN(8), WSN/SWN(6), Kyongju RWRS

21 Units in Operation

• Over 30y operating plant : 1 unit

KN 1, Issued the Continued Operation license in 2009

• Over 20y operating plants : 8 units WN 1, 30y design life, others 40~60y

• Under 20y operating plants : 12 units

7 Units in Construction

• At the Operating License(OL) stage : 3 units (SKN 2, SWN 1/2)

• At the Construction Permit(CP) stage : 4 units (SKN 3/4, SUN 1/2)

4 Units in Planning

• At the Site Approval stage : 4 units, (SKN 5/6, SWN 3/4)

2 Designs in Review :

SMART at DC stage, APR+ at pre-review stage

Yong-gwang 6 units Kori 8 units Ulchin 8 units

Wolseong 6 units

In Operation

Under Construction

Radioactive Waste Disposal Facility

(Under construction)

Planning the 4

^th

Nuclear Technology R&D Program; 5Y Plan

• Finalizing the 3

^rd

NT R&D Program(‘07.3~’12.2) and planning the next 5 year Program(‘12.3~’17.2) in Safety Regulatory Research(SRR) sector

Environmental Changes in SRR Sector

• Received IAEA IRRS to Korea

 Conducted, July 10~22, 2011, 20 reviewers of 14 countries for 5 scopes ;

regulatory independence, transparency/openness, long-term operation, ageing management, and Fukushima issues

 Identified 15 Good Practices, 10 Recommendations, 12 Suggestions

• Performed Special Safety Inspection after Fukushima Accident

 Conducted , March 28~April 30, 2011, at plant sites, 73 experts for 6 areas:

design of SSCs, integrity of power/fire protection, severe accident measures, emergency responses, long-term cooling, research reactors

 Identified 50 short and long-term follow-up action items

• Established New Regulatory Authority, NSSC under the President

 Organized, Oct. 26, 2011, 9 commissioners and Secretariat office

 Planning the 1^st Nuclear Safety R&D Program, 5Y plan, independent plan from the 4^th NT R&D program

Action Items Identified from IAEA IRRS

• GP9 : Maintaining and utilizing internal capability for performing independent audit calculations (KINS-RETAS, KINS-REM, etc.)

• GP13 : Operation and continuous enhancement of AtomCARE is a good example

• R1 : The regulatory framework require decommissioning plans

• S9 : Establishing criteria for design extension conditions in licensing of new reactors

Follow-up Actions Recommended from SSI

• Ensuring protection from extreme earthquake and tsunami

• Securing electric power and reactor cooling capability including SFP

• Strengthening severe accident mitigation measures and response strategy

• Strengthening emergency preparedness capability against extreme accidents including multi-unit conditions

Consider NSSC Policy in the Next NS R&D Program

• NSSC R&D policy, mid and long-term directions, strategy, research scope and budget, etc. : NSSC-KINS joint work

Thermal-Hydraulic and Safety Analysis Research ;

TH phenomena and behavior analysis, Accident analysis and evaluation for DBA and Beyond DBA, Analysis code development and maintenance, etc.

Severe Accident Research ;

SA phenomena and behavior analysis, SA analysis and evaluation, Code maintenance, PSA, Severe Accident Management, etc.

Engineering System Research ;

Mechanical stress analysis, Aging management, Stress corrosion and thermal fatigue, Integrity of I&C, Impact on aircraft crash, Probabilistic seismic evaluation, Fire protection, RIPBR, etc.

Radiation Safety Research ;

Radiation protection, Radioactive Waste Management, Radiological Emergency Response System, etc.

GEN IV Research ;

Regulatory systems and Requirements for future-type reactors such as SFR, HTGR

Research Purpose

• To develop the highly reliable, predictable reactor transient analysis code systems

• To apply for resolution of safety issues and independent audit calculations

Finished or Ongoing Tasks(‘07-’11)

• Analysis Code Development;

TH system analysis code (MARS-KS), Kinetics analysis code (COREDAX) and code coupling technology

• TH Model Improvements;

LBLOCA reflood model, Upper plenum entrainment model,

condensation with NC gas, CANDU specific component models(channel, pump), etc.

• Analysis Methodology;

Korean REM for LOCA, Safety margin analysis method, etc.

• Plant Application;

DBA analysis of New Plant Designs, Performance analysis of new

components and systems (SIT with FD, ECCS DVI), Reevaluation of DBA by SG replacement and design changes, review of Topical

Report(methodology changes), etc.

RETAS Workbench Rod Performance

Code: FROBA Containment :

CONTAIN

T-H System Code:

MARS-KS

Break flow

(M/E) Back

Pressure

Core flow &

enthalpy Local power Fuel rod performance

data Enthalpy &

pressure, HTC, Temp.

Dose Calculation Code: RDE

Containment Leakage/

Bypass Leakage

Graphic User Interface

3D Kinetics:

PARCS/COREDAX

Rod power

Σ Gen. :

ENDF HELIOS

Graphic Input Editor

Model

Output Acquisition

& Display

• Italic: Developing

• Blue colored: USNRC owned

• Green colored: PWR only

• Red Colored: CANDU only

3D Kinetics:

SCAN

< Improved Reflood model Calculation >

< RETAS for Regulatory Audit Calculation >

Future R&D Directions

• Additional to Current R&D tasks, reflecting IRRS action items, SSI Follow-up actions, Lessons learn from Fukushima accident

• Improve the system analysis code, extend it to beyond DBA, apply CFD technology to nuclear safety regulation, etc.

Future Tasks of TH Area(‘12-’16)

• TH Evaluation for New Plant Designs and Technology;

TH code performance improvements, Analyses of APR+ PAFS, SMART PRHR, New Design Codes(SPACE, etc.), IAEA ICSP on NC, USNRC CAMP

• Application of CFD to Nuclear Safety;

High predictability in component level and local phenomena, Analysis method and user guide, etc.

• Multiple Failure Evaluation and Long term Cooling Capability;

Analysis of SBO, TLOFW, Evaluation of Accident management, SFP cooling capability, etc.

• ECCS Rule Changes

; Analysis of USNRC ECCS rule changes, LOCA analysis with changed conditions,

Impact on regulatory practices

p D/2

d

< Assesment Table for Code Verification >

< Helical Tube TH Analysis, CFD >

< APR+ PAFS nodalization >

Ongoing or Future Tasks of Severe Accident

• Participating International Cooperation Project;

 OECD/NEA, ThAI, experiment and assessment on hydrogen behavior, using MELCORE

 OECD/NEA, SFP, experiment and assessment on flame characteristics in SFA, MELCORE, CFD code

 OECD/NEA, SERENA, experiment and assessment on FCI, molten core behavior

 OECD/NEA STEM, IRSN ISTP, EU SARNET2, experiment and assessment on radiological source terms like Iodine behavior (RAIM)

 USNRC CSARP, MELCORE improvements, SA behavior like Steam explosion, Hydrogen explosion

• Plant Application ;

 Evaluation of SAM Strategy in PHWR, hydrogen behavior analysis, MELCORE, for PAR installation

 FA/DDT possibility in APR1400(DEFEND)

 Accident management against extreme natural disaster, multi-unit site, Response measures against total loss of power, Long-term cooling capability

 Safety Management Guidance(SMG) : Re-evaluation of AOP, EOP, SAMG and EDMG

 PSA Models for extended accident scenarios

< ThAi Experiment Assessment >

< Iodine analysis model, RAIM >

< FA Analysis, DEFEND >

Research Purpose

• To resolve the safety and regulatory Issues and ensure the safety of long-term operating plants

Ongoing or Future Tasks

• Evaluation for PWSCC, Thermal Fatigue and Aging;

PWSCC analysis(size, leak) and relief measures(weld overlay), Branch/Mixing T TF, Integrated aging management(R-Aging), DMW inspection technique, Power cable aging

• Structural Behavior by Intentional Aircraft Crash;

Containment Impact and load(LS-DYNA, ABAQUS), Local damage analysis, OECD/NEA project

• Plant Application;

AMP(Fatigue, Leaks, FAC monitoring) and TLAA(Thermal stratification and cycling), Fatigue life of materials for WN 1

Continued Operation(W1-FDMS), etc.

• Assessment of Design Earthquake and Surface Deformation in Plant Sites

• Fire Hazard Analysis Method, Fire Dynamic Simulation

< Fluid Temp. > < Pipe Temp >

< High freq. TF : Stress and K_I >

< Aircraft Impact Analysis >

Research Purpose

• To ensure public safety and high quality of life, establishing international level of radiation

protection

Ongoing or Future Tasks

• Evaluation of Radiation Risk;

ICRP 103 issued in 2007, Management of radioactive source(DB by use, risk), Transportation and storage, Natural radioactivity(National Radon Potential Map), etc.

• Efficient Radiation Management System;

Improvement of RASIS including RADLOT

• Regulatory Framework for Safety

Management of Radioactive Wastes and Decommissioning;

Prior-disposal management, Interim storage of spent fuel, Disposal Facility,

licensing procedures/ requirements for plant decommissioning, Advanced Fuel Cycle Facility

• Advanced Establishment of Radiological Emergency Response System

; AtomCARE system, Aerial radiological monitoring system, Cooperation system with neighboring countries

0

< Real time Radiation Dose Analysis for Worker >

< Aerial Monitoring Equipmqnt >

Research Purpose

• To prepare for licensing to future type reactors, Demo-plant SFR and HTGR

• To provide regulatory guides to utility in the development stage

Ongoing or Future Tasks

• Licensing Procedures and Safety Requirements;

Establishment of licensing framework for Demo-plants, Design specific requirements, guidelines, etc.

• Approaches to Resolve the Licensing and Technical Safety Issues;

Identified issues different from current PWR licensing

• Safety Analysis Tool Developments;

System performance and accident analysis code and methods for safety review

• Evaluation Methodology to New Features;

TRISO fuel, containment function of HTGR, sodium cooling performance, new material, etc.

안전철학

일반안전기준

• 원자로 시설 등의 기술기준에 관핚 규칙

상세안전목표

• 일반안전목표의 세부사항 (정량적 목표제시 가능)

일반안전목표

• 최상위 안전목표

일반안전원칙 기술안전원칙

• 안전목표를 달성하기 위핚 기술적인 주요사항

• 일반안전기준을 포괄하는 상위개념의 원칙

• 안전목표 달성을 위해 적용되는 일반적인 사항

• 사업자의 책임 등 원자력 이용 전반에 적용되는 원칙

Nuclear Safety Act

Enforcement Decree of the Act Regulation of the Act (Ministerial Ordinance)

Notice of NSSC

Regulatory Guides (Standard, Guide, Guideline)

Technical Cooperation between KINS and GRS (Severe Accident)

• Containment vent system for severe accidents

– Operation Status of venting systems in Europe

– Important views in terms of design & performance

• Steam Explosion

– Phenomenological understanding of SE

– Methodology of explosion force calculation

• Hydrogen Explosion

– Phenomenological understanding of HE

– Definition and criteria of FA(Flame Acceleration) and

DDT(Deflagration to Detonation Transition)

Technical Cooperation between KINS and GRS (Decommissioning)

• Decommissioning Plan, Practice and Experience

– Decommissioning Plan and Strategy

– Verification of the Evaluation of Radiation Doses

– Verification of Measurement of Residual Radioactivity for the Site and the Radioactive wastes such as Huge Metal Equipment

– Lessons Learned on Decommissioning

• Regulatory Frame for Decommissioning

– Bases for the Decision-making for Criteria, Standard and Guidelines

– Specific Roles and Function of Regulatory Bodies and

Legal Bases for their Functions

ABBREVATIONS

• SRD : Safety Research Division

• NSSC : Nuclear Safety and Safeguard Commission

• IRRS : Integrated Regulatory Review Service

• SSI : Special Safety Inspection

• RETAS : Reactor Transient Analysis System

• REM : Realistic Evaluation Methodology

• MARS-KS : Multi-dimensional Analysis of Reactor Safety-KINS Standard for Regulatory Audit Calculation

• SPACE : Safety and Performance Analysis Code : Utility Safety Analysis Code

• CAMP : Thermal-hydraulic Code Application and Maintenance Program

• CSARP : USNRC Cooperative Severe Accident Research Program

• FCI : Fuel Coolant Interaction

• FA/DDT : Flame Acceleration/Deflagration to Detonation Transition

• RIPBR : Risk-Informed and Performance-Based Regulation

• AMP : Ageing Management Program

• PWSCC : Primary Water Stress Corrosion Cracking

• TLAA : Time Limited Aging Assessment

• FAC : Flow Acceleration Corrosion

• W1-FDMS : Wolseong Unit 1 Fatigue Damage Monitoring System

• DMW : Dissimilar Metal Weld

• AtomCARE : Computerized technical Advisory system for Radiological Emergency ; Real-time collection and monitoring of plant safety data, update every ~ 20 s

• IRRS : Integrated Regulatory Review Service

• NSSC : Nuclear Safety and Safeguard Commission

• RASIS : Radiation Safety Information System : Integrated management system of radiation safety activities, used by KINS and over 4,600 radiation/RI users, 6 sub-systems

• RADLOT : Radiation Source Location Tracking System

• SMART : System Integrated Multi-purpose Advanced Reactor

• SFR : Sodium-cooled Fast Reactor

• HTGR : High Temperature Gas-cooled Reactor

• APT+ : Advanced Power Plant +

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