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

CLADS Main 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

(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” was 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 of Japan can interact, to promote research/development and human resource development towards decommissioning by collaborative effort of academia-industry-government.

industry, and government.

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Cooperation with academia,

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

Collaborative Laboratories for Advanced Decommissioning Science

Sector of Fukushima Research and DevelopmentFukushima Research institute

Research Co-ordination and Promotion Office

Research Division for Potential Risk Reduction in Decommissioning

Waste Management Division

Accident Progression Evaluation and Fuel Debris Characterization Division

Remote System and Sensing Technology Division

20171001

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 International

Collaborative 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

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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 and practical use

Share on-site needs and information

Actual w

ork of decomm

issioning Create a basic research roadmap based on the 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 DevelopmentFukushima Research instituteCLADS (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

20171001 ③

Research Division for Potential Risk Reduction in Decommissioning

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

R&D on aging mechanism of fuel debris⇒Investigating aging mechanism of fuel debris to consider

methodologies of estimation on fuel debris characteristics at a certain 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 severe accident in order to develop severe accident simulation and estimation method of fission product distribution.

Analysis on Fuel Debris Behavior

Chemical reaction

Mechanical deformation

Biological effect

Coupling effect

Aging mechanism

Concept of aging mechanism

Coupling effect

Couplingeffect

Analysis of radioactive particles

SEM/EDS

Autoradiography system

Image of radioactive particle

Elemental identification (ex.)

On-siteOff-site

Sampling&

Analysis

Development of technology to ensure long-term safe storage of radioactive waste by analyzing hydrogen behavior in a waste storage vessel and by applying mitigation methods to suppress an increase in hydrogen concentration.

Development for Hydrogen Safety Engineering

Analyses of hydrogen behavior⇒To assess hydrogen safety in waste storage including such

behavior as diffusion and stratification while considering, through analysis technique, decay heat of wastes, buoyancy effects of hydrogen mixed gas, and combustion effects of pressure wave and flame radiation on storage vessel wall.

Mitigation method to suppress increase in hydrogen concentration

⇒ By using hydrogen recombination catalyst, a passive or non-powered mitigation method is to be developed and applied to enable long-term safe waste storage.

Hydrogen generation in waste storage vessel by water radiolysis of following moisture:・Aqueous ingredients

in wastes・Moisture transport of

residual water Influential factors to

hydrogen behavior:・Decay heat of wastes・Buoyancy effects in

hydrogen-air mixed gas

・Heat dissipation from outer wall of vessel

・Steam condensation

Storage vessel

Decayheat

Water radiolysis

Recombination catalyst

Diffusion

Residual water

Heat dissipation by convection and heat radiation

Radio-active waste

Condensedsteam

Moisture transport by capillary pressure etc.

Conceptual diagram of inner and outer conditions of storage vessel

Analyses:：・Estimation of

hydrogen concentration and temperature distributions

Combustion:・Propagation of

pressure wave and flame radiation to vessel wall

Mitigation:・Confirmation of

effectiveness of lightweight and compact recombination catalyst of ceramic monolith type

Risk of corrosion degradation for plant materials in 1F site have been increasing with time duration and/or environmental changes by decommissioning procedure. Preventing methods for these corrosion risks are developed based on corrosion mechanism.

Mechanism of Corrosion in Irradiated Condition⇒To build a database for estimating the degradation of corrosion in

irradiated condition, corrosion and radiolysis data will beaccumulated.

Evaluation of Corrosion Risk in Each Equipment ⇒Corrosion risk for individual equipment during decommissioning

process is analyzed by using investigation sheet.

Analysis of Corrosion Mechanism inSpecific Environment

• Corrosion degradation can bederived based on mechanismutilizing comprehensive studyof radiolysis analysis.

• Indicating corrosion mitigationmethod for high risk equipmentutilizing the investigation sheetfor corrosion risk.

Behavior analysis of radioactive micro-particles

Clarification of the mechanisms of generation, trans-portation and migration of the radioactive micro-particles

⇒ Clarify the behaviors of generation, transportation and migration ofthe radioactive micro-particles generated during debris removal.Provide the knowledge of its behavior at underwater / aerial, air-liquid interface and develop the in-situ measurement technology.

The strategy of confinement and dose evaluation⇒ Conduct the fundamental evaluations on the filter permeation of

wet dust, air dose rate due to nuclear reaction of radioactivemicro-particles, aim to provide knowledge on exposureassessment and criteria setting at the boundary.

Radioactive particle generation test by focusing heating.

Dissolution behavior test in flow field using electrochemical technique.

Laser Observation and Numerical Simulation for radioactive micro-particles at air-liquid interface

Gas bubble with particles

Aerosols(Max 3kW)

Xenon Lamp Hemispherereflector

(water cooled)

Crystal chamber

Test piece Holder (fine movement)Motor

controller

Lampcontroller

Gas Ref. rod

Potentiostat

Liquid

TargetUO2

ControlPt

NaOH etc.Concrete dissolved material

Clarify the microscopic behavior of radioactivemicro-particles produced during the retrieval of fueldebris to ensure confinement.

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

Colleges, Institutes, etc.

Integration

20170401 ④

Cement solidification

Geopolymersolidification

Vitrification

Peletization Sintered compact

Sampling of slurry

Rad

ioac

tivity

co

ncen

tratio

n(B

q/cm

3 )

Iron Coprecipitation

Carbonate

Carbonate (from improved)

～Toward Decommissioning of Fukushima Daiichi NPS～

Accident Progression Evaluation and Fuel Debris Characterization Division

se

【Objective】・・Contributing to progress in sever accident analysis andaccident management by experimental knowledge and detailedmodeling for fundamental process in sever accident based onmaterial science.【Main research themes】(1)Control blade degradation test Experimental knowledge on fundamental process of control blade degradation using developed facilities in corroboration with institutes and universities, and development of detailed mechanistic modeling.

(2) Solidification in molten corium test Experimental knowledge on fundamentalprocess of solidification in molten coriumfor lower cooling rate , and developmentof detailed mechanistic modeling.

1F Accident Progression Evaluation Fuel Degradation Modelling

FP Chemistry Dose Evaluation& Material Accountancy【Objective】・・Contributing to the

analysis of in-reactor status by providing fundamental knowledge and model for the chemical behavior of Cesium (Cs).【Main research theme】(1) Cs chemisorption modelingFundamental study on the reaction between Cs and stainless steel (SS) under high temperature accidental condition 1F (basic experiments and model construction); to contribute to evaluation of Cs localization and adhesion behaviors in.

CsSiSEI

Nagaoka university of technology

(2) Advanced surface analysis technologyHard X-ray photoelectron spectroscopy for direct determination of chemical state of chemisorbed Cs

An example of Cs adhesion experimentPossibility of formation of Cs-Si-O compounds and intrusion into SS up to several tens μmwas observed.

VTT, Finland

The institute of applied energy

Visiting researcher Collaboration on

analysis and experiment

Example of Cs adhesion model

(2) Analysis and evaluation of １F-accident progression behaviorConduct 1F-accident analysis andevaluation flecting above-mentionedexperiments in the light of plant data andinspection so that BWR-specific accidentprogression and resultant reactorcondition can be clarified contributing 1Fdecommissioning and safetyresearches.

【Objective】・・Contribute to 1F decommissioning providing information ofpost-accident reactor condition with model simulation and experimentsfor accident progression through comparison with plant data andinspection. The obtained knowledge will be reflected to safety researches.

【Main research themes】(1) Experimental study focusing on core melting with BWR designObserve core material melting/relocation with BWR design simulatingaccident conditions with high-temperature plasma-heating technology.

0.0125 g/s/rod 0.0417 g/s/rodSteam flow rate

Elucidation of threshold condition for control blade degradation, depending on steam flow rate

Camera

Test piece

Camera

Control blade degradation test facility

Heater

Steam

Fuel Debris Characterization 【Objective】・・Estimation of the characteristics of fueldebris in the reactor using simulated fuel debris, andestablish methods for handling and analysis of actualdebris towards decommissioning work for the removaland storage of fuel debris.【Main research theme】(1) Evaluation of fuel debris characteristics in the reactorEstimate 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.(2) Analytical technologies for fuel debrisEstablish analytical technologies and transportation method to develop a system for early debris analysis.

Micro-hardness of various phases in the simulated fuel debris

Simulated MCCI product(JAEA-CEA collaboration)

Debris dissolution(by Alkaline fusion method)

Vickers hardness（SEM observation）

(1)

(2)

【Objective】 ・ ・ Contributing to theoptimization of 1F decommissioningprocedures and to nuclear materialaccountancy of retrieved fuel debris.【Main research themes】(1) Evaluation of dose distributionEvaluation of the dose rate distribution in PCV of 1F based on simulation of accident, experiments and measured values in internal investigations.

(2) Non-destructive assay (NDA) technique for nuclear material accountancy of fuel debris Most appropriate management of 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

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)

Evaluation of dose rate distribution in PCV

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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 la tion 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）

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