Major Nuclear Safety Research Activities

(1)

Korea-German Cooperation Workshop on Nuclear Safety December 12, 2011, GRS, Cologne, Germany

Major Nuclear Safety Research Activities and Possible Cooperation with Germany

Won-Pil BAEK, Ph.D.

Vice President for Nuclear Safety Research Korea Atomic Energy Research Institute (KAERI)

wpbaek@kaeri.re.kr

(2)

 Background

 Korea’s Initiatives after Fukushima Accident

 Nuclear Safety Research at KAERI

 Selected R&D Topics & Achievements

 Possible Cooperation Activities

 Concluding Remarks

Outline

(3)

 Nuclear Power in Korea

 21 units in operation

− 17 PWRs and 4 PHWR-CANDUs

− 30~35% share of country’s electricity supply

 7 PWR units under construction

− 3 OPR1000’s and 4 APR1400’s

 4 additional APR1400 units by 2022

 Government plan of 2008: nuclear electricity share of

~59% in 2030

− Under revision process, reflecting a rapid growth of electricity demand, Fukushima accidents, etc.

 Cheapest source of electricity in Korea

− Generating cost in 2009 (Won/kWh): nuclear 35.6, coal 60.3, wind 107.3, oil 145.6, LNG 153.1, solar 647

Background ⁽¹⁾

(4)

Background ⁽²⁾

 NPP Construction in Korea

Wolsung 1 Kori 2

Kori 3 Kori 4

Yonggwang 1 Yonggwang 2

Ulchin 1 Ulchin 2

Wolsung 2 Wolsung 3

Wolsung 4

Shin-Kori 1 Shin-Kori 2

Shin-Wolsung 1 Shin-Kori 3

Shin-Kori 4 Shin-Wolsung 2

10 20

(5)

Background ⁽³⁾

 KAERI

 The Sole National Institute of Korea for Comprehensive R&D on Nuclear Technology

 Nuclear basic research

 New reactor technology development

 Fuel cycle technology development (front-end & back-end)

 Nuclear safety research

 Research reactor operation & utilization

 Radiations/radioisotopes applications

 Manpower training, policy study, etc.

 Founded in 1959 (the 1

^st

government-supported R&D institution in S&T area)

 Founder of many nuclear power related organizations, including KINS, KINAC, KEPCO-E&C and KEPCO-NF

 ~1800 staff (~1,200 regular staff)

(6)

Background ⁽⁴⁾

 KAERI – Mission

(7)

Background ⁽⁵⁾

 KAERI – R&D Organizations

President

Senior VP for

Strategic Programs Senior VP for R&D Programs

Future Nucl.

Energy Sys Research

Institute (VP)

Advanced Reactor Develop.

Advanced Radiation

Technol.

Nuclear Safety Research

Depart.

(VP: Baek)

Research Reactor Utilization

Depart.

(VP)

Nucl Fuel &

Material Develop.

Depart.

(VP)

Nucl. App.

Technol.

Develop.

Depart.

(VP)

Nuclear Policy Develop.

Depart.

(VP)

Integrated Safety Assessment Div.

Thermal

Hydraulics Safety Severe Accident &

HWR Safety Environmental Safety Research

SFR, Back-end FC,

HTR, Waste SMR, RR Adv. Fuel,

Materials

(8)

Background ⁽⁶⁾

 KAERI – Major Achievements

(9)

Background ⁽⁷⁾

 KAERI – Cradle of Korean Nuclear Organizations

(10)

 Fukushima Accident Asks Us:

 To Escape from Self Satisfaction on NPP Safety

 To Strengthen Countermeasures against External Events as well as Internal Equipment Failures

 Consider very low-likelihood natural events in design

 Prepare against prolonged loss of AC power

 To Strengthen Countermeasure against Severe Accidents

 Reliable measurement of plant parameters

 SA mitigation features including hydrogen control

 Consideration of severe accident in procedures and operator training

 Emergency planning and exercise against worst scenarios

 To Strengthen the Communication of Safety Information Severe accident-free 100 years with the proactive safety

Korea’s Initiatives after Fuku-Acc ⁽¹⁾

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 ROK’s Immediate Responses to Fukushima Accident

 Emergency Response Team

 Crisis Communication with Public and Media

 Strengthened Environmental Monitoring

 Special Safety Inspection on Operating Nuclear Facilities

 Others

 Establishment of a New Regulatory Body: Nuclear Safety and Security Commission (NSSC)

 First IRRS Mission after Fukushima Accident

 Implementation of Action Items Identified from Special Safety Inspection

 Planning for Strengthened Nuclear Safety Research

Korea’s Initiatives after Fuku-Acc ⁽²⁾

(12)

 Special Safety Inspection by Regulatory Body

 March 23 ~ April 30, 2011; 73 Experts

 21 Operating NPPs, 1 Research Reactor, and Emergency Medical System

 Main Focus on Unlikely Worst Case Scenarios, including

 Extreme natural disaster (earthquake + tsunami)

 Loss of off-site power and failure of emergency DGs (SBO)

 Severe accident

 Objectives

 How well the NPPs are designed against natural disasters ?

 How well they can mitigate the severe accident ?

 How much effective the emergency response system are in place ?

Korea’s Initiatives after Fuku-Acc ⁽³⁾

(13)

 Outcomes of the Special Safety Inspection

 No Imminent Risks to Operating Nuclear Facilities

 50 Action Items to Further Strengthen the Defense- in-Depth Approach

 To minimize the impact of extreme natural disaster

 To make available emergency power and ultimate heat sink

 To ensure containment building integrity and emergency response capability

 Examples of Action Items

 Re-evaluation of seismic capability of safe shutdown system

 Installation of a mobile emergency generator and battery

 Installation of passive hydrogen removal equipment

 Modification of 'radiological emergency plan' considering multiple emergency, etc.

Korea’s Initiatives after Fuku-Acc ⁽⁴⁾

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Korea’s Initiatives after Fuku-Acc ⁽⁵⁾

Safety Improvement against Extreme Natural Disasters

Tidal Barrier

Mobile EDG

Water Proof EDG Flood

Safe Battery

Turbine

Pump Turbine

Steam Gen.

Pres- surizer

Containment PAR

Filtered Venting Control

Rods

Water Proof Pumps

Core

Sea

Reactor Vessel

(15)

 Nuclear Safety and Security Commission

Korea’s Initiatives after Fuku-Acc ⁽⁶⁾

President Prime Minister

MEST MKE Others

Secreteriat NSSC

KAERI

KEPCO KHNP

KINS KINAC

Advisory Committee on Nuclear Safety & Security

(ACNSS)

KINS

KINAC

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 Nuclear Safety Research

 Scientific investigation and technology development for assessment, verification & improvement of nuclear safety

Nuclear Safety Research at KAERI ⁽¹⁾

Nuclear Safety Research

Resolution of safety issues

Verification &

enhancement of oper.

reactor safety Development of adv.

& innovative design concepts

Effective & reliable regulation

Improved operation

Safe ^&

Economical Nuclear Technology

Utilization with Strong Public Support Knowledge

based Decision

Making Original

Knowledge Assessment

& verification infrastructure

Experts

(17)

 Structure of Nuclear Safety R&D in Korea

Nuclear Safety Research at KAERI ⁽²⁾

MEST’s Nuclear Tech.

R&D Program

MKE’s

NuTech-2012 Program

Industry Budget

KAERI

KINS ^KHNP-CRI^&

Industry

Some changes are expected owing to the establishment of

Universities

(18)

 National R&D Programs

Nuclear Safety Research at KAERI ⁽³⁾

Basic Infrastructure

Infra. Strengthening

& Core Technol.

Development

Outcome Maximization &

Tech. Leadership

(1992-1996) (1997-2006) (2007-2011)

MOST’s Nuclear Technology R&D

- Mid- & Long-term Nuclear R&D Program

MEST’s 5-year R&D Program for Nuclear

Technology

MKE’s Program for NPP Technology Advancement

(NuTech-2012)

• Adv. technology for assess. & verific. Of water reactor safety

• Safety research on Gen-IV nuclear systems

• Core technology for future LWRs

• Resolution of NPP safety issues

Global Leading Safety R&D

(2012-)

Fukushima Lessons

(19)

Nuclear Safety Research at KAERI ⁽⁴⁾

 Major NSR Topics at KAERI

Plant Mimic Indicators

• 사용 가능한 Indicator 종류 Plant Mimic

Indicators

• 사용 가능한 Indicator 종류

PT inside kH O2

ConvectionPT-CT RadiationFS-PT

hCT

RadiationFS-FS hBP/PThPT/CT CC

FS kH O2

ConvectionPT-CT RadiationFS-PT

hCT

RadiationFS-FS hBP/PThPT/CT CC

FS

Oxide pool

DIV. A GC-1

DIV. A GC-3 DIV. A GC-2 F/E F/E F/E F/E

F/E RMS-A FHEVAS F/E RMS-B FHEVAS 분배기 분배기 분배기 분배기

분배기 분배기

DIV. A LC-1 Primary DIV. A LC-1 Standby DIV. A LC-2 Primary DIV. A LC-2 Standby

DIV. A LC-12 Primary DIV. A LC-12 Standby 2/3

Logic

I/O I/O I/O

FIELD COMPONENTS/SENSOR Primary NET Standby NET DIV. A GC-1

DIV. A GC-3 DIV. A GC-2 F/E F/E F/E F/E

F/E RMS-A FHEVAS F/E RMS-B FHEVAS 분배기 분배기 분배기 분배기

분배기 분배기

DIV. A LC-1 Primary DIV. A LC-1 Standby DIV. A LC-2 Primary DIV. A LC-2 Standby

DIV. A LC-12 Primary DIV. A LC-12 Standby 2/3

Logic

I/O I/O I/O

FIELD COMPONENTS/SENSOR Primary NET Standby NET

Physical Integrity System Behavior Risk Management Environmental

Protection

-100 0 100

0 50 100 150 200 250 300

<PCVN data>

validity Material: TO (^oC)

VCD-1(-60) VCDA (-73) SKA-1(-80) JFL (-98) JRQ (-62) Irr.JRQ(66) Median 5%, 95%

1% lower

KJC - adjusted to 1T (MPa-m0.5)

T test - T

O (oC)

Terrestrial Radioecology Radionuclide dispersion/

Dose Assess.

Environ.l Monitoring Technology

Radiation Biology

mutat. DNA

Mat. Degradation Assessment for NPP Comp’ts NDE Tech. &

Computational Material Sci.

Advanced Materials Development Comp. Integrity Monitoring &

Diagnostics Corrosion &

Water Chem.

Optimization

ATLAS – T/H IET for PWRs T/H SETs for Reactor Core

& System Exp. & Anal. of Severe Acc.

Phenom.

Adv. Safety Anal. Codes &

Applic.

CANDU Safety Tech.

Develop. of Adv.

Risk

Management Tools

Digital I&C PSA

Human Factor Assessment Seismic Risk Assessment Integrated Risk/Perform.

Model

(20)

Nuclear Safety Research at KAERI ⁽⁵⁾

 Major Achievements in Recent Years

 World-class infrastructure for safety assessment and verification, including ATLAS, TROI, etc.

 Experimental verification of new design features of APR1400

 Development and application of safety analysis tools, in the areas of thermal hydraulics, PSA, and environmental safety

 Several codes provided to KINS and industry

 Technical Background for Extended Operation of NPPs

 Leadership in international cooperation

 OECD/NEA SERENA Project with the TROI facility

 ORCD/NEA ISP-50 with the ATLAS facility

 Export of safety analysis tools: FTREX, VISA

 Key role in establishing core technology for commercial

(21)

Nuclear Safety Research at KAERI ⁽⁶⁾

 Future Directions

 Emphasis on advanced simulation and integrated approach

 Incorporation of lessons from Fukushima-I accidents

 Collaboration with global-leading institutions

Theory

&

Modelin g

Large-Scale Tests

Theory &

Modeling

High Resolution

Tests

Advanced Simulation (Predictive) Simulation

(Interpretive)

Paradigm Shift

separate  Integrated System  Multi-scale

(22)

Nuclear Safety Research at KAERI ⁽⁷⁾

 Possible R&D Topics after Fukushima Accident

 Re-establishment of safety standards & design req’ts

 Severe accident prevention by better protection against extreme external events, enhancing passive safety and securing electricity

 Better mitigation of severe accident to practically eliminate the possibility of large early radioactivity release

 Incorporation of risk information in design, operation and accident management

 Management of materials/equipment aging issues

 Advancement of assessment technology for radioactivity dispersion and its health effects

 Safe handling of spent fuels

 Advanced modeling & simulation technology for integrated

assessment of safety

(23)

Selected R&D Topics & Achievements ⁽¹⁾

 Thermal Hydraulic Safety Research

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Selected R&D Topics & Achievements ⁽²⁾

 Tests & Evaluation of APR1400

– Direct Vessel Injection (DVI)

• Unique TH phenomena for DVI of ECC water

• ECCS bypass and downcomer boiling during LBLOCA

– Fluidic Device (FD) Tests

• Devel. & prototypic test of the the Fluidic Device in SITs

– IRWST Sparger Tests

• Hydrodynamic loads on the structures on SDVS actuation

• TH mixing in the water pool

– IVR-ERVC Tests

• Establishment of natural circulation flow

• Heat removal limits

• Heat load on the RV head

M

S/G

RPV RCP

RCP

SDVS SIT

Sparger

Core

FD Pzr

IRWST A

B C

D

A: DVI Tests

B: Fluidic Device Tests C: IRWST Sparger Tests

(25)

Selected R&D Topics & Achievements ⁽³⁾

 ATLAS Integral Effect Test Program

 Tests for safety issues and/or interests of APR1400, OPR1000 and APR+

 Simulation of APR1400/OPR1000 transients & accidents for assessment & validation of system analysis codes

• Reference NPP: APR1400

• Geometric Scale:

– 1/2 H, 1/144 A, 1/288 V to APR1400

• Loop Configuration:

– 2 Hot Legs & 4 Cold Legs – Integrated Annular DC

• Operating Conditions:

– Full Press./Temp.

– Max. 10% of Scaled Power

• Measurements: 1,250

• Safety injection systems for APR & OPR

(26)

Selected R&D Topics & Achievements ⁽⁴⁾

 ATLAS: Application & On-going Projects

 Verification of safety concerns for APR1400

 Validation of regulatory & industrial safety analysis codes:

• MARS, SPACE Codes

 Domestic cooperative programs

• DSP

• DOOSAN: FLB

 Int’l cooperative programs

• OECD/NEA ISP-50:

– DVI-Line Break

• Counterpart tests:

– LSTF, PKL, etc.

 Support of future safety

research needs

^ISP_-50

(SPACE) (RETAS)

(27)

Selected R&D Topics & Achievements ⁽⁵⁾

 T/H Safety Analysis Code Development

Development of TASS

NPP Analyzer ViSA Basic

Technology

Best-Estimate System Analysis Code

Reg./Ind. Codes Advanced Tools

(1992-1996) (1997-2006) (2007-2011)

Cooperation with Industry For Ind. Safety Anal. Code

SPACE

Multi-scale, Multi-physics, Integrated Codes

(2012-)

Development of

MARS

Component-scale TH module

CUPID

Cooperation with KINS

for RETAS

MARS-GCR, MARS-LMR

Research Reactor Analysis (JRTR, FTL)

Advancement of RETAS

High-resolution Integrated Safety Analysis Technol.

SPACE Advancement

• TASS: Transients and Setpoints Simulation

• MARS: Multi-dimensional Analysis of Reactor Safety

• ViSA: Visual System Analyzer

• SPACE: Safety and Performance Analysis Code

• CUPID: Component Unstructured Program for Interfacing Dynamics

Probabilistic Safety Analysis

(28)

Selected R&D Topics & Achievements ⁽⁶⁾

 Regulatory Code System with MARS

(29)

Selected R&D Topics & Achievements ⁽⁷⁾

 TROI Steam Explosion Tests

 TROI: Test for Real cOrium Interaction with water

• Use real material, UO₂, ZrO₂, (Zr, SS)

• Low pressure up to 0.5 MPa

• 20 kg, 5-10 cm dia. jet, big water pool

• Triggered, spontaneous

• Use of advanced instrumentation

 Major Milestone

• ‘99.4- ‘00.6: Construct Test Facility

• ‘00.7- ‘01.3: Preliminary test using ZrO₂

• ‘01.4- ‘02.3: Tests using real material (UO₂+ZrO₂)

– Does it lead to energetic steam explosion ? – Use 5 kg of corium: Conversion efficiency

• ’02.4 -’07.2: Tests using real material up to 20 kg

– Detailed physics with advanced instrument

• ’08~’12 OECD-SERENA Project

(30)

Selected R&D Topics & Achievements ⁽⁸⁾

 TROI Steam Explosion Tests

0.5 0.6 0.7 0.8 0.9 1.0 1.1

-0.05 0.00 0.05 0.10 0.15 0.20 0.25 0.30 0.35 0.40

Void Fraction

Time (s) TS-4 VFDP 101(0.2-0.4m) VFDP 102(0.4-0.6m) VFDP 103(0.6-0.8m)

O. Separate verification Tests - DP, level swell meter and

level swell from high speed camera

(31)

Selected R&D Topics & Achievements ⁽⁹⁾

 Corium-Structure Interaction Tests: VESTA

VESTA facility

- Jet Impingement Test

- Capacity: ~ 400 kg of corium

Small Scale Facility

- Corium/Structure Interaction at various composition

- Capacity: ~ 10 kg

(32)

Selected R&D Topics & Achievements ⁽¹⁰⁾

 Other SA Research Areas

 IVR through external reactor vessel cooling

 Natural circulation of cooling water

 Molten pool stratification

 Hydrogen distribution & combustion inside containment

 Use of CFD codes and GASFLOW

 Fission product behavior

 Development of improved modules on foreign codes

 Experimental data from international programs

 Severe accident code development (new; cooperation with KHNP)

 KAERI-Industry-Academia collaboration under the auspices of

MKE

(33)

Department of Nuclear Safety Research

Selected R&D Topics & Achievements ⁽¹¹⁾

33

 Severe Accident Research after Fukushima

stack

corium-concrete interaction containment energy

evacuation

sump

Controlled Filtered Venting

auxiliary building

reactor

building containment spray

containment leakage core

melt steam explosion induced

breaks

direct containment heating

S/G

RPV

hydrogen combustion

RPV rupture

venting systems loss of containment integrity

FP Transport &

Release into

Environment (ST) SA Management

(34)

Selected R&D Topics & Achievements ⁽¹²⁾

 Major Achievement in PSA Technology

 Integration of Internal &

External PSA Model

 Automatic Generation of External PSA Model from Internal Model (AIMS)

 New Quantification Algorithm for External PSA Model

 FTREX: BDD features

 Exported to 3 countries

 Used in more than 50% of NPP in USA

 Regulatory Support

 MPSA: PSA Model for Regulation

 VIPEX: Risk-informed Physical Protection

Supporting Tool, Used for the IAEA Training

 Enhancing Human Performance

 OPERA DB

 video taped >100 cases of operator training at simulator

 Complexity Measure: TACOM

 Springer

 Digital I&C PSA

 DI&C Induced Initiating Event

 Rel. Analysis Methods for HW/SW

 HRA for Digitalized MCR

 Seismic PSA

 Korean Specific Hazard Curve

 Shaking Table Exp for Digital MCC

(35)

Selected R&D Topics & Achievements ⁽¹³⁾

 FTREX

 Overview

 Based on the ZBDD (Zero-suppressed Binary Decision Diagram) algorithm

 Calculate Minimal Cut Sets (MCSs) and Minimal Path Sets (MPSs)

 The fastest and most accurate fault tree solver in the world

 Work with world major Probabilistic Safety Assessment (PSA) tools

 Commercialization

 Successfully commercialized in 2006

 Exported by worldwide sales agent US EPRI

 The most popular fault tree solver in Northern America nuclear industry

 Exported to electric power utilities in USA (70%), Canada (100%), Switzerland, and Spain

CAFTA/EOOS (EPRI, USA)

1 Million $ exports

(36)

Selected R&D Topics & Achievements ⁽¹⁴⁾

 Environmental Safety Research

- Research about resistance-related functional genomics - Low dose effect of radiation, H-3 biological effect - Development of useful genetic resources for

- Assessment of radiation impact to human and biota and environmental transport of radionuclides

: ECOREA, ECOREA-H, K-BIOTA code development

- Development of urban atmospheric dispersion model and radiological impact assessment

- Decision-making support against a radiological emergency

: FADAS, METRO-K code development

-Evaluation of radionuclides behavior in surface, ocean and atmosphere in long-range area

: LADAS, LORAS code development

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Selected R&D Topics & Achievements ⁽¹⁵⁾

 Some Results of LADAS

(38)

Selected R&D Topics & Achievements ⁽¹⁶⁾

 Nuclear Material Degradation Research

Proactive technology for nuclear materials safety Prediction technology of extended plant lifetime

Material Degradation Evaluation for Commercial PWRs

Materials evaluation for research reactors & SMART

Technical Support

for Current Materials Issue

(39)

Selected R&D Topics & Achievements ⁽¹⁷⁾

Research area

Corrosion research Fracture-mechanical

integrity Radiation damage

Nondestructive evaluation SG inspection Water chemistry

• Characterization of SCC crack for mechanistic understanding on SCC

• Investigation on SCC crack incubation, initiation and propagation with ECN

• Examination of advanced fracture mechanics methodology

• Establishment of database under high-fluence neutron irradiation on RPV materials

• Simulating materials behavior by developing computer codes

• Characterizing radiation-induced defects (electron microscopy, positron annihilation)

• Nondestructive characterization techniques for detection of materials degradation

• PEC, NRUS & Long-range guided wave technique

• Optimization of the probe design and performance for inspecting 3D S/G tube

• Development of S/W for eddy current data analysis

• Development of water chemistry technology to control fouling & crevice corrosion

Current R&D

Objective

Develop techniques for ensuring integrity of NPP materials / components

(40)

Selected R&D Topics & Achievements ⁽¹⁸⁾

• Monitor & Evaluate RPV steel embrittlement due to neutron irradiation

• Mechanical property test/Neutron dosimetry analysis/Neutron transport calculation

• Development of Ex-vessel neutron dosimetry

• Design and evaluation of materials for research reactors

• Guidelines for reactor materials’ selection & Preparation of materials specifications

• Irradiation test of core materials in HANARO

• Evaluation of property of advanced FM steels, Ni-base superalloys and ODS alloys

• Development of key technologies for evaluation of advanced nuclear materials

• Damage mechanisms and irradiation effect on reactor material for VHTR

Research area

RPV surveillance test

Materials for research reactors

Materials for future systems

Solve current materials issues for the application to nuclear reactors (Research reactor, commercial NPP)

Current R&D

Objective

(41)

 Status

 Active collaboration through international projects or programs

− PKL, THAI (Germany)

− SERENA, ISP-50 (Korea)

− Other projects/programs organized by third countries

 Use of German codes for safety research

− GASFLOW for hydrogen behavior analysis

 Use of UPTF data in validating KAERI experiment for APR1400

 Manpower/information exchange

 Limited bi-lateral collaboration activities in general

Possible Cooperation in NSR ⁽¹⁾

(42)

 Thermal Hydraulics

 Continuous support & participation to OECD projects

− PKL-3

− New program development with ATLAS

− Counterpart tests between PKL and ATLAS

 Cooperation for Advanced Modeling

− Advanced instrumentation

− High-resolution experiment on multi-dimensional TH phenomena

− CFD benchmark on rod bundle TH underway (org. by KAERI)

− CFD4NRS Workshop in September 2012 (org. by KAERI)

 KAERI is willing to provide TH experimental data to Germany if requested

− Recognizing the great contribution of the UPTF data in APR1400 tests

Possible Cooperation in NSR ⁽²⁾

(43)

 Severe Accident

 In-depth discussion at KAERI in November

 Hydrogen safety

− OECD THAI-2 project

− Use of KIT codes in Korean nuclear community: GASFLOW, COM3D, DET3D

− Tests and analyses on PAR performance

 Severe accident code development

− Exchange of information on in-vessel/ex-vessel phenomena

− GRS’s consultation on KAERI’s code development

 Exchange of information on filtered venting, measurement technology, etc.

 GRS support to OECD project development of KAERI

− Possible projects with TROI and/or BESTA facilities

Possible Cooperation in NSR ⁽³⁾

(44)

Possible Cooperation in NSR ⁽⁴⁾

 Environmental Safety Research

 Radionuclide Transport Assessment

- Atmospheric and Marine Dispersion Modeling

- Source-Term Estimation Technology on Nuclear Accident - Validation Study of Dispersion Models

 Development of Dose Assessment Technology

- Off-site Radiological Dose Assessment in Routine Releases - Radiological Dose Assessment in an Urban Environment - Radiological Emergency Response Plans and Preparedness

 Environmental Transport and Radioecology

- Human Ingestion Dose Assessment

- Non-human Species Dose Assessment

- Uptake of Radionuclide in Agricultural Plant(Biological Remediation) - Radioecological Parameters Measurement

 Radiation Biology

- Radiation resistance related genes and proteins

- Natural and functional materials for radiation and drug sensitization - Sene manipulation for radionuclide absorbent plant and microbial cells

(45)

Possible Cooperation in NSR ⁽⁵⁾

 Materials Safety Research

Items

Concluding Remarks

 Good safety research cooperation between Korea and Germany in general

 Limited bilateral cooperative programs: slower than expected

 Stronger cooperation is desirable for NPP safety of both countries and the world

 Mutual access to experimental data

 Collaboration in analysis models (codes) development

 Regular information exchange workshop

 Use of German codes in Korea

 Cooperation in international projects/programs

 Cooperative projects/programs in some areas

Major Nuclear Safety Research Activities