Fukushima Environmental Safety Center

Utilization of results

【Tokyo Electric Power Company・IRID・NDF】

【Domestic and oversea universities, research institutes, and industries】

【Fukushima Prefecture, The Ministry of Environment】

Cooperation with Tokyo Electric Power Company, International Research Institute for Nuclear Decommissioning (IRID), NuclearDamage Compensation and Decommissioning Facilitation Corporation (NDF)

Cooperative course with the University of Tokyo, Tohoku University, Tokyo Institute of Technology, etc. Cooperative research andinformation exchange with international organizations, research institutes in USA, UK, France, etc., and private companies, etc.

Cooperation with Fukushima Prefectural Center for Environmental Creation, Fukushima Technology Center, etc.

Collaborative Laboratories for Advanced Decommissioning Science

Main efforts of the Collaborative Laboratories for Advanced Decommissioning Science

『From off-site to on-site』

福島研究開発部⾨

Naraha Remote TechnologyDevelopment Center

（(Partly started operation in September 2015)-Development of remote control instruments etc.-

Okuma Analysis and Research Center

(under designing, scheduled to open in 2017)-Analysis of radioactive nuclides, etc.-

Okuma Town, Fukushima Prefecture(next to the 1F site)

Naraha Town, Fukushima Prefecture

-A platform to collect the wisdom of experts from around the world-

Collaborative Laboratories for Advanced Decommissioning Science

International Collaborative Research Building

(near 1F, Tomioka Town, Fukushima Prefecture in April 2017)

Utilizing JAEA’s special facilities for handling nuclear fuels and radioactive materials, and irradiation facilities at Tokai and Oarai in Ibaraki Prefecture.

(I)Establishment of a platform to rally the wisdom of experts from around the world

●Inviting foreign researchers●Collaborative research with oversea research institutes●Forming a working group including external researchers and experts in the fields necessary to decommissioning.

※At present, the research and development are conducted using existing facilities in JAEA.

(II)Enhancement of in and outside Japan research on decommissioning

Fukushima Research Conference

●Organization established in April 2015 at Tokai Village, Ibaraki Prefecture

(III)Enhancement of human resource development in mid-and-long termIntegrating analysis technologies from various fields and developing human resources by opening cooperative course with institutions adopted for the “Decommissioning Basic Research: Human Resource Development Program” hosted by the Ministry ofeducation, Culture, Sports,In order to gather a variety of talented people, the cross-appointment system* are utilized

(IV)Establishment of an information dissemination function

In cooperating with the National Diet Library , JAEA arranges information released by the government and Tokyo Electric Power Company on the basis of IAEA’snuclear accident information categories and transmit the information as the “JAEA Archive”.Transmitting information on documents including JAEA’ original research results

As an international research and development base, “International Collaborative Research Building” will be constructed near the 1F as a core of the Collaborative Laboratories for Advanced Decommissioning Science. A network will be established, where competent people from universities, research institutes, and companies in and outside Japan can interact, to promote research/development and human resource development towards decommissioning by collaborative effort of academia-industry-government.

industry, and government.

1/2

Cooperation with academia,

Research and development on environmental dynamics, radiation monitoring, etc.

Collaborative Laboratories for Advanced Decommissioning Science

Sector of Fukushima Research and Development

Research Co-ordination and Promotion Office

Waste Management Division

Fuel Debris Handling and Analysis Division

Severe Accident Propagation Behavior Evaluation Division

Remote System and Sensing Technology Division

20170401

Sector of Fukushima Research and Development

①

Office for Tomioka Collaborative LaboratoriesOperation Management

applicationapplication

Activities as a platform for basic research on decommissioning projectsServe as a council for promotion of basic research toward decommissioning of 1F, jointly managed by JAEA

(CLADS) and the business operators who were publicly recruited and selected by MEXT for its human resource development (HRD) projects.

－The platform is widely open up to the world in order to involve as many researchers as possible in and outside Japan.

Have working meetings, joined by NDF, IRID, TEPCO, and other related organizations as observers.

Construct a mechanism of the platform for participating members to perform vigorous activities at InternationalCollaborative Research Building.

Attract potential research members by publicly informing R&D topics.・ Play a central role in promoting basic research toward decommissioning of 1F

・ Foster and employ human resources for R&D

・ Utilize International Collaborative Research Building

2/2

Nuclear Damage Compensation and Decommissioning Facilitation Corporation(NDF)

Platform for basic research on decommissioning project Plays as a council for promotion of basic research toward decommissioning of 1F JAEA (CLADS) and the business operators who

were publicly recruited and selected by MEXT for its human resource development (HRD) projects. The platform is widely open up to the world in order to involve as many researchers as possible in and outside Japan.“Bazaar” Approach Spell out the purpose of the platform, create a basic research roadmap based on the strategic plan, and update it in a timely manner. Have multiple players compete for the goal bringing together their expertise, technologies, and idea by Industry-academia collaboration. Realize dynamic mutual interaction among the basic research and the project and provide achievements on a timely manner. Actively participate in the consolidation and effective use of International Collaborative Research Building. Manage long-term risks by digging up unexposed issues. Set up research groups for R&D activities.

Integral management from basic to applied R&D

Basic Research Applied study Commercial-level technology

Universities ・Research Institutions

JAPAN ATOMIC ENERGY AGENCY （JAEA） International Research Institute for Nuclear Decommissioning（IRID）

TEPCO

Provide research resultsSupport applied study andpractical use

Share on-site needs andinformation

Actu

al wo

rk of d

ecom

missio

nin

g Create a basic research roadmap based onthe strategic plan, and update it

Two to three times per yearHolding of cooperative meetings for facilitating R&D on decommissioning

Platform for basic research on decommissioning project

Japan Atomic Energy AgencySector of Fukushima Research and DevelopmentCLADS (Collaborative Laboratories for Advanced Decommissioning Science)790-1 Motooka aza Ohtsuka, Tomioka-machi, Fukushima-ken, 979-1151TEL: +81-240-21-3530 FAX: +81-240-22-0100URL：http://www.jaea.go.jp/english/index.html

Positioning of the platform

②

Waste Management Division

FY2017 Basic concept of processing and disposal for solid radioactive waste*

FY2021 Prospects of a processing/disposal method and a technology related to its safety*

Purpose

*Mid-and-Long-Term Roadmap (revised June, 2015)

Analysis of various wastes

Evaluation of the amount and composition of radioactivity

Collection of physical/chemical data

Development of analysis method

Characterization

Radioactivity concentration of slurry generated from Multiple Radio-nuclides Removal SystemSampling of rubble

Soundness of stainless steel vessel used for cesium adsorption apparatus

Technology for safe storage of nuclear accident-derived wastes

Storage

Technology survey

Fundamental test of solidification

Technology selection

Processing

Understanding of the existing disposal concepts

Examination of disposal concept of accident-derived wastes

Examination of new disposal concept

Disposal

Example of safety assessment modelFull scale cesium adsorption vessel

R&D cooperation Information sharing

Collaboration with domestic and international research institutes

OECD/NEA RWMC [Expert Group on Fukushima Waste Management and Decommissioning R&D]

Colleges, Institutes, etc.

Integration

20170401 ③

Cement solidification

Geopolymersolidification

Vitrification

Peletization Sintered compact

Sampling of slurry

Rad

ioac

tivity

co

ncen

trat

ion(

Bq/

cm3 )

Iron Coprecipitation

Carbonate

Carbonate (from improved)

Studies on dose evaluation method and nuclear material accountancy for fuel debris with non-destructive assay (NDA) technique

Fuel Debris Handling and Analysis Division

Fundamental studies on aging mechanism of fuel debris and analysis of radio-active fine particles towards decommissioning after severe accidents

Estimation of the characteristics of fuel debris in the reactor using simulated fuel debris, and establish methods for handling and analysis of actual debris towards decommissioning work for the removal and storage of fuel debris. R&D on aging mechanism of fuel debris

⇒Investigating aging mechanism of fuel debris to considermethodologies of estimation on fuel debris characteristics at acertain time in long-term decommissioning work.

R&D on radioactive fine particles⇒Extracting various kinds of information and analysis results of

radioactive fine particles regarding actual progression of severeaccident in order to develop severe accident simulation andestimation method of fission product distribution.

●Collaboration with universities and industries in Japan

●Promotion of International Cooperation

Joint research and information exchange with

Evaluation of fuel debris characteristics in the reactor⇒Estimate the characteristics considering the idiosyncratic

reactions of 1F, and update with the latest information.⇒ Study the characteristics of MCCI product in conjunction with

CEA and ANL. R&D on analytical technologies for fuel debris⇒Establish analytical technologies and transportation method to

develop a system for early debris analysis.

R&D on evaluation of dose distribution based on computersimulation of accident, experiments and measured valuesin 1F plants⇒ optimization of decommissioning procedures

R&D on non-destructive assay (NDA) technique fornuclear material accountancy of fuel debris

⇒ most appropriate management of fuel debris

Joint study on engineering scale MCCI phenomenon and product properties with CEA

●Contribution to 1F decommissioning in collaboration withTEPCO, IRID, and NDF, etc.

Collaboration and Cooperation

Analysis on Fuel Debris Behavior

Dose Evaluation & Nuclear Material Accountancy

Fuel Debris Characterization and Condition Technology Development

Contribution

Prototype small ROV (Remotely-operated vehicle) with neutron and gamma detector (by Lancaster & Manchester Univ.)

MCCI Sample

SEM/EDSAnalysis

Surface of molten core concrete

reaction

CEA、INL、ANL、LANL、ORNL、LBNL、DOE、NRC、IAEA、ISP-NPP、KIT、ITU、IAEA、 Lancaster＆Manchester Univ. etc.

Chernobyl LFCM (LAVA) by ISP-NPP

Evaluation of dose rate distribution

・The University of Tokyo, Nagoya University: “Laser resonance ionization mass spectrometry”

・Kyoto University: Solution spectroscopic techniques by LIBS・The University of Tokushima: “LIBS basic property, resonance

absorption spectroscopy”・LIBS research group in Japan: “Advanced measuring techniques,

severe environment measuring techniques”

・Private sector: “Microwave assisted laser emission spectroscopy”・Nagaoka University of Technology and National Maritime Research

Institute: “Sonar technology to search submerged fuel debris”

Conceptual design of NDA system(An example of active neutron method)

NDA system for Uranium contaminated waste ＠

JAEA/Ningyo

Debris canister

Neutron generator

Accounting

access

Fast neutron detector

System image

20170401 ④

Reflection of available output of JAEA, TEPCO, IRID, OECD/NEA, etc.• Fuel burnup calculation,• Activation calculation,• Accident progression analysis,• PCV/RPV internal investigation,• FP behavior experiment,• Fuel debris characterization, etc

Calculation of 3D-dose rate distribution(Monte Carlo calculation code PHITS)

Micro-hardness of various phasesin the simulated fuel debris

Simulated MCCI product(JAEA-CEA collaboration)

Debris dissolution(by Alkaline fusion method)

Vickers hardness（SEM observation）

(1)(2)

Concreate Test Section

20160401 ⑤

〜R&D on BWR severe accident for the Decommissioning of Fukushima Daiichi NPP〜

Collaboration using developed apparatus and contribution todevelopment of human resourcefor decommissioning

Research institutes and universities

Elucidate melting and relocation behavior by SA code analysis and experiments for important phenomena

Evaluation of debris

distribution and

situation of residual

structures in

Fukushima Daii NPP

Large uncertainties in relocation behavior of core materials to lower plenum

Research on molten core relocation behavior【Objective】・・Elucidate melting and relocation behavior of fuel bundles in BWR severe accident which affect distribution of fuel debris and damage of in-vessel structures, utilizing information obtained from the inspection of Fukushima Daiichi NPP.【Main R&D theme】Evaluation of molten material relocation behavior, damage of core structure and MCCI behavior by Severe Analysis code and necessary experiments based on the plant data in 1F accident and inspection data of 1F.⇒ Contribution to evaluation of debris distribution and situation of residual structures

Control blade

Fuel bundle

Water level

Loss of water in core region

Preceding control blade melting/relocation

Estimated accident progression base on existing knowledge

Pool formation

residual core material

lower support structureheating of residual core materials and support

structure

Estimated accident progression in Fukushima Daiichi NPP

damage of support structure

penetration throughsupport structure

Estimation2

Estimation1

relocation of molten core materials to lower plenum in short duration

gradual relocation of solid core materials to lower plenum

Severe Accident Propagation BehaviorEvalulation Division

【Objective】・・Contributing to the comprehensive analysis of in-reactor status by providing fundamental knowledge and model for the chemical behavior of Cesium (Cs).【Main research theme】Fundamental study on the reaction between Cs and stainless steel (SS) under high temperature accidental condition; to contribute to evaluation of Cs localization and adhesion behaviors in 1F. Basic experiments are conducted by using non-radioactive Cs and SS samples for evaluation of dependence of Cs-adhesion onto SS on temperature, atmosphere, etc. Models are constructed based on the experimental results.

Evaluation of FP behavior

CsSiSEI

An example of Cs adhesion experiment：Elemental distribution in SS, indicating adhesion of Cs onto SS surface. Possibility of formation of Cs-Si-O compounds and intrusion into SS was shown.

VTT, Finland

Elrick(Ar-H2O)Bowsher(Ar)Bowsher(Ar-4%H2)Bowsher(Ar-4%H2-H2O)

Visiting researcher Collaborative analysis

The institute of applied energy

Visiting researcher Collaboration on

analysis andmodellingExample of

Cs adhesion model

Contributing to

evaluation of FP

distribution in 1F

Collaboration on fundamental material science area: Thermodynamic study on Cs-compounds Evaluation of elemental behavior in SS

※IRID R&D

Tohoku Univ.TITECH

Osaka Univ. 20160401 ⑤

【Objective】 ・・ Contributing to progress in severaccident analysis and accident management byexperimental knowledge and detailed modeling forfundamental process in sever accident based onmaterial science【Main research theme】Experimental knowledge on fundamental processin sever accident using developed facilities incorroboration with institutes and universities, anddevelopment of detailed mechanistic modeling

Research on fundamental process in sever accident by material science

CameraTest piece

An example of facilities：Control blade degradation test facility

0.0125 g/s/rod 0.0417 g/s/rod

Visual data of in-situobservation obtained fordetailed mechanisticmodeling.

Oxidation behaviordepends on steel flowrate and tendency ofcontrol bladedegradation possibly hasthreshold condition.

Steam flow rate

Effect of steam flow rate on control blade degradation

Steam

20160401

燃料デブリ

Laser-besed in-core monitoring & analysis technology

Laser material diagnosis & process technology

Laser Induced Breakdown Spectroscopy (LIBS) using radiation resistant optical fiber.

Remote System and Sensing Technology Division

Remote Technology and Robotics Group

Radiation Imaging and Instrument Group

Remote Analytical Technology Group

Remote System and Sensing Technology Division

Radiation Imaging and Instrument Gr Remote Technology and Robotics Gr

Remote Analytical Technology Gr

R&D for sensing data collection andenvironmental data management technology,collecting environmental data of work for the promotion of the 1F decommissioning.

A prototype of sensor collection system

Environment Data Collection Technology (Simultaneous Localization and Mapping(SLAM)), etc.)

Environment Data Management Technology (Environment Model Construction, Relational Spatiotemporal Database)

Environment Data Utilization Technology (Integration with

Virtual Reality I/F and Simulators)

Mock-up stair measurement in the Naraha Remote Technology Development Center. RGB-D Camera measurement 3D point cloud data measurement

Development of Fiber-Type radiation detectorFiber-Type radiation detectors for measuringa position of radiation incidence under high dose-ratefields inside the FDNPS

PrototypePM T or M PPC

PM T or M PPC

Time-of-Flight circuit

M CA

Scin ti l lation photons

Radiation（ γ 、 β 、 neutron）

PSF

Electric pulse signals（ Start）

PA PA

Electric pulse signals（ Stop）

Conversion of time differenceto amplitude

Development of high energy gamma-ray CT

Sensor base

Signal process base

Multi-direction measurements

Silicon Strip Detector

Non-destructive imaging system by measuring high-energygamma rays emitted from fission products and/or spontaneousfission nuclides for 3-D reconstruction of nuclear fuel debris.

Ultrasonic waves are introduced into a concrete block by an Nd:YAG impact laser. The waves propagating in block are detected with a laser Doppler vibrometer (LDV) using a He-Ne laser.

Remote and non-contact operation of drilling and cutting of a concrete for sampling.

Diagnosis technology Process technology

Remote radiation imaging systemRemote radiation imaging system consisting of a Compton camera and amulticopter-type drone to remotely measure the distribution of radioactivecontaminations inside the site of Fukushima Dai-ichi Nuclear Power Station.

Remote radiation imaging systemusing a compact Compton cameramounted on a multicopter drone

The drone system with the Compton camera succeeded in remote observation of dense hotspots from the sky.

Performance evaluation test in the Hamadori region of Fukushima

Radiationsource

Scatterer Absorber

Compton Camera

Gamma-ray sensor

Compton cone

3D model created by a laser scanner

Reconstruction imageof radiation

Remote radiation monitoring using a drone

Compton Cam.

SLAM

3D distribution mapof the contamination

The radiation image is observed on theposition of the 137Cs-radioactive source.

Compton camera

137Cs-radioactive source

Optical Fiber LIBS Probe(Several tens of seconds)

（Extremely high dose-rate environment）