Overview and Activities ofInternational Research Institute for
Nuclear Decommissioning (IRID)
May 14, 2014

Kazuhiro Suzuki
Executive Director
International Research Institute for Nuclear Decommissioning
無断複製・転載禁止 技術研究組合 国際廃炉研究開発機構©International Research Institute for Nuclear Decommissioning

Revision of Mid-and-Long-Term Roadmap and Background of Establishment of IRID
Overview of revised Mid-and-Long Term Roadmap(Council for the Decommissioning on June 27, 2013)
1. Acceleration of the schedule for each unit corresponding to the respective condition.
 Multiple plans were developed aiming at the fuel debris retrieval for initial unit to be conducted
ten years later to be flexible with each unit.
2. Enhance communication with local community
 Establish “Fukushima Advisory Board (tentative name)” Provide opportunity to find the corporation in Fukushima in order to collaborate fordecommissioning work, and revitalize regional economy by encouraging local corporations
supplying equipment/tools.
3. Full scale maintenance of structure to gather knowledge and ideas from around the world.
 Establish R&D organization and arrange system to receive advice from overseas experts.
 Enhance collaboration with IAEA review mission, and proactive promotion of international joint
research.
In addition to the above, following items will be stipulated and addressed in the Mid-and-Long Term
Roadmap.
 Reports the countermeasures on control of groundwater inflow by “Contaminated Water
Treatment Committee.” Secure safety of ”Specified Reactor Facility” and measures on regulations, such as ofarrangement of new standards. (improve reliability of equipment and facilities, and operation
safety for operator and radiation safety etc.)©International Research Institute for Nuclear Decommissioning１

Process of Establishment and Role
Establishment
・August 1, 2013: Approved by Mr. Motegi, the Minister of Economy, Tradeand Industry, according to the Research & Development Consortium Act ofJapan.
・August 8, 2013: General Meeting and the Board of Directors were held tostart the consortium. Launched as the International Research Institute for
Nuclear Decommissioning.
Basic Role
・Fully committing to technology R&D that helps the decommissioning projectof Fukushima Daiichi NPS as an urgent subject, based on which enhancing
the technological basis for nuclear decommissioning for the future.

©International Research Institute for Nuclear Decommissioning２

Technical Research InstituteTechnical research association is an organization for mutual support where themembers conduct joint research on the technologies used for the industrial activities
for themselves（non-profitable mutual benefit corporation established in accordancewith the Research & Development Consortium Act of Japan).
<Features of Technical Research Association>
 Each member provides researchers, researchfund, facilities etc., and manage and utilize
1. Organization change
those result together.
Change the organization to
Stock company orJoint research organization with legal
limited company and facilitate
personality, independent from the members.
utilization of research results.
Stock corporation or Improve transparence and reliability oflimited company
organizational operation through theregistration and application for authorization
2. Incorporation-type company split
for establishment for the competent minister,
Establish stock company or
and members’ general conference and thelimited company byboard of directors.
incorporation-type company split
and utilize research obtained.
 Person or party （including domestic
corporation, individuals, foreign corporation
Split stock corporation orlimited company
and foreigner ） that utilizes the results ofjoint research directly or indirectly can be amember of this organization.
3. Dissolution
 This organization can be utilized as a place of
Dissolve Technical Institutecooperation among government, industry
And the members brings
research results back and utilize.
and academia since the universities andindependent administrative corporation of
4. Split of Technical Institutetest research, technical college, local publicbody, foundation mainly aiming at the test
Extract specific research
themes and split organization
research etc. members can take part in.
for each research theme(Excerpts from METI)

Overview of Technical Research InstituteCorporation(member)

R&D tax system
Cost processing
Amount imposed
R&D tax system
Cost processing
Authority
Amount imposed
Legal entity
Research Institute

University(member)

Publicresearch
institute(member)

Reduction entry

Research
Institute

Split Technical InstituteResearch result

Corporation(member)©International Research Institute for Nuclear Decommissioning３

Outline of IRID
1. NameResearch & Development Consortium,“International Research Institute for Nuclear Decommissioning” (“IRID ” in brief)

2. Location of Main Office
6F, Parkplace, 5-27-1, Shimbashi, Minato-Ku, Tokyo, 105-0004, Japan(http://www.IRID.or.jp)

3. Founding members (18)- Incorporated administrative agencies:
Japan Atomic Energy Agency, National Institute of Advanced Industrial Science andTechnology.
- Manufacturers:
Toshiba Corporation, Hitachi-GE Nuclear Energy, Ltd., Mitsubishi Heavy Industries, Ltd.,ATOX (since May 29, 2014)- Electric utilities etc :Hokkaido Electric Power Company (hereinafter called as EPC), Tohoku EPC, Tokyo EPC,
Chubu EPC, Hokuriku EPC, Kansai EPC, Chugoku EPC, Shikoku EPC, Kyushu EPC, The Japan
Atomic Power Company, J-POWER, Japan Nuclear Fuel Limited.

4. Board of directors
President: Dr. Yamana, Vice President: Dr. Arai, and Mr. Kenda, Executive Director: Mr. Suzuki
Director: Mr. Oikawa, Mr. Moriyama, Mr. Uozumi , Mr. Hatazawa, Mr. Seto
Mr. Fukuda and Mr. Kadokami
Auditor : Mr. Konashi©International Research Institute for Nuclear Decommissioning４

Projects of IRID
IRID gathers knowledge and ideas
from around the world for the
purpose of R&D in the area of nuclear
decommissioning under the
integrated management system.

R&D for
Decommissioning

R&D projects:･Fuel assemblies removed fromspent fuel pool･Preparation for fuel debris
retrieval･Treatment and disposal ofradioactive waste

Promotecollaboration for
Decommissioning
with Domestic andInternational
PartiesDevelopmentof Human Resource
for R&D©International Research Institute for Nuclear Decommissioning５

Schematic image of IRID ’s function<With perspective of enhancing technological basis for reactor decommissioning, focusing on
clear and present challenges of Fukushima Daiichi NPS decommissioning.>-Accelerating the decommissioning of Fukushima Daiichi NPS,
securing its safety and restoring its environment.
-Early recovery of the Fukushima area and the confidencebuilding among the nation.

-Preparation for future decommissioning and enhancing its
safety level.
-Incubating , accumulating and improving the related
technologies.

Council for the Decommissioning of TEPCO's Fukushima Daiichi
Nuclear Power Station

Electric Utilities
Plant Manufacturers(Chaired by Mr. Motegi, the Minister of METI)[HQ of all projects]

Presentation/report of R&D program

Presentation/report of
Mid & Long term Road Map

Feed back to future decommissioning projects

Research and Development Consortium,
International Research Institute for Nuclear Decommissioning
R&D execution entities

Secretariat (R&D management )TEPCO
Fukushima Daiichi
Decontamination
andDecommissioning
Engineering
Company

Deriveon-siteneeds
Practically
apply
results
Suggestplans andstrategies

Integrated management of
decommissioning technologies-Review and optimization of the strategy of overall
decommissioning program.
-Analysis of on-site needs and seeds oftechnologies,
coordination (optimization/matching).
-Coordination and guidance of respective
technology
development.
-Adoption of international & domestic advices.
-Exploration of potential technology.
-Enhancement of human resource development,
alliance among universities, etc.

Advices on technological and managerial aspects

Advices from domestic/international organizations

Plant Manufacturers
Japan Atomic Energy Agency
Guidewell- designed
development
Guide
collaboration&cooperation
Shareresults

National Institute of Advanced
Industrial Science andTechnology
Electric Utilities
Other Research Organizations

Participation to joint study, R&D, etc.

Partner organizations of joint study©International Research Institute for Nuclear Decommissioning

６Organizational chart
System receiving worldwide advices(Technology Advisory Committee,
International Expert Group etc.)

General Meeting
Board of Directors

International Advisors

Contaminated Water
Technology Review Team
Research Strategy Planning
Dept.

Fuel Debris Retrieval Technology Review Team

Research Promotion Dept.

International & Alliance Dept.

R&D management

Promotion ofinternational alliance

Administration &Labor management

Alliance ofdomestic/international
academic institutes

Accounting &Procurement

Controlling
Human resource
development

Information
management ofaccident/recovery

Public relations

Technology planning
officeFuel Debris Retrieval Gr.
Development team to
Identify leakage points of PCVDevelopment team to
repair PCV

Administration Dept.

Reactor Interior and Fuel Debris
Evaluation Technology Gr.

R/W Treatment Technology Gr.

Development team to analyze fueldebris characteristics

Development team to treat &dispose of secondary R/W fromcontaminated water treatment

Development team to control
criticality of fuel debris

Development team to treat &dispose R/W

７©International Research Institute for Nuclear Decommissioning

Present operation plan (R&D projects)
R&D to set up fuel debris retrieval

Estimation of inside of reactor using severe
accident analysis code

R&D for remote decontamination in reactor building
Development of technology for investigation of
inside of PCVDevelopment of repair and stopping water leakage
technology for leakage location of PCVDevelopment of technology for retrieval of fueldebris and in-core structures
Development of technology for investigation of
inside of RPVDevelopment of technology for evaluation ofsoundness of RPV/PCVDevelopment of technology for grasping ofcharacteristics and treatment of fuel debris
Development of technology for detection of fueldebris in reactor
Development of technology for packing, transfer
and storage of fuel debris
Development of repair and stopping waterleakage technology for leakage location of PCV
Full-scale test for repair and stopping waterleakage technology for leakage location of PCV

R&D for treatment & disposal of R/W
Development of technology for disposal of accident waste

R&D to retrieve SFs from SF pools
Evaluation of long-term soundness of fuel assembly, etc. retrieved from spent fuel pool
Consideration of treatment method of damaged fuel, etc. retrieved from spent fuel pool

©International Research Institute for Nuclear Decommissioning

８

“Open Platform” to integrate knowledge from all around the world
Board of Directors

International Advisors
Advices from organizational governance &management aspects

Integrated management of
R&D projects

Alliance/collaborative
study with technology
partners, etc.
Procurement ofequipment, etc.
from technologicalvendors
Collaborative
studies withresearch institutes,
etc.

Needs atsite

Supply ofequipment

Joint study

International
collaborative projects*Planning of overall research strategy
for decommissioning.
*Coordination & optimization withregard to practical needs.

Joint business

Project -1

Sharing results

Project -2

Materialization of new
projects

Technologicaladvices

OECD/NEA- Accident analysis, etc.
IAEA
- Review missions- Others

International Expert Group

Discussions on innovative ideas, technologies and projects
Innovative ideas/ technology proposals

Companies, research institutes and others around the world©International Research Institute for Nuclear Decommissioning

９International Adviser and International Expert Group
Soliciting advices based upon findings & experiences of other countries

 Advices from the International Advisors on overall management at IRID .
•••-Mr. Lake Barrett (US): Former NRC, Individual consultant. (Director of measures to contain the
TMI accident.)
Dr. Adrian Simper (UK): Director of NDA
Mr. Luis E. Echavarri (Spain): Former OECD/NEA Director-General
The 1st Meeting held on Jan. 9-10, 2014

 Technological advices from the International Expert Group•

Douglas Chapin (USA): President of MPR (experienced in restoration from TMI accident
and clean-up of the facilities.)• Dr. Rosa Yang (US): Electric Power Research Institute(EPRI) Senior Technical Executive• Dr. Adrian Simper (UK): Director of NDA• Dr. Joel Pijselman (France): Current Chairman of ETC (former Vice president of AREVA)• Mr. Nikolai Steinberg (Ukraine): individual consultant (involved in Decommissioning strategy ofChernobyl Nuclear Power Plant. )• Mr. Anton Leshchenko (Russia): Deputy Head of Research Department, Research andDevelopment Company. “Sosny” (engaged in the retrieval work of damaged fuel at Paks Nuclear
Power Plant)- The 1st Meeting held on Sep. 23-27 (Tokyo/Fukushima)- The 2nd Meeting held on Feb. 17-21, 2014 (Tokyo)- The 3rd Meeting held on Jun. 24-27, 2014 (Tokyo)©International Research Institute for Nuclear Decommissioning

１０

IAEA Review Mission
 IAEA International Peer Review on “TEPCO Mid-and-Long Term Roadmap for
Decommissioning of Fukushima Daiichi Nuclear Power Station Unit 1-4”
(Nov. 25 -Dec. 4, 2013)
IRID , along with METI and TEPCO, discussed with IAEA inspection team consists of 19
members and obtained following evaluation results.
 A comprehensive structure was developed, such as establishing IRID so as toutilize technical knowledge and technological capability around the world in orderto accelerate the decommissioning activities of Fukushima Daiichi Nuclear Power
Station more safely.
 The intension to incorporate international experience and to seek international
cooperation by having IRID participated was clearly confirmed.
 IAEA confirmed that TEPCO and IRID make contribution toward the developmentof remote control technologies to identify cooling water leakage in the PCV andrepairing the leakage. Application of the equipment to identify the leakage points
is a significant step for PCV isolation (leakage points closure) Establishing the working group (WG) for the development of remote control
equipment will shorten the time between identifying specific needs and thehanding over of the facilities assisted by each developed remote technology. For
example, after the WG was established, the time it took for the device detecting
the leakage inside the dry-well was 7-8 month. Participation of plant
representative to the WG will contribute to successful development.
©International Research Institute for Nuclear Decommissioning

１１

International Joint Project
IRID contributes to enhance the safety and decommissioning work of
nuclear faculties around the world through the international joint work.

 OECD/NEA BSAF Phase I
 Joint benchmark research on accident status of Fukushima Daiichi andcurrent condition of the core through the analysis codes including
improved version for severe accident analysis codes.
 Sharing common data and information database Project for the next stage (plan) BSAF Phase II with expanded scope (Hydrogen, MCCI etc. ) Sampling, analysis, and property identification of fuel debris
 Issues regarding the management of radioactive waste(methods of identifying and categorizing the properties and disposing
the waste material)©International Research Institute for Nuclear Decommissioning

１２

Evaluation of R&D ProjectTechnical Advisory Committee (Experts of third parties)
Role : Evaluate and advice on overall R&D strategy and the activities of IRID .
Chairperson: Satoru Tanaka (Professor of School of Engineering, University of Tokyo)
Committee member :Hajime Asama (Professor of School of Engineering, University of Tokyo)
Yutaka Watanabe (Professor of School of Engineering, Tohoku University)
Shinsuke Yamanaka (Professor of Graduate School of Engineering, Osaka University)
Osamu Tochiyama (Director, Radiation and Waste Safety Research Center, Nuclear Safety
Research Association)
Subcommittees(Evaluation of R&D
project)(1)Fuel debris retrieval
equipment/remote
operation technology*(2) Spent fuel ・PCV/RPV soundness
evaluation technology

Chairperson:
Hajime Asama

Chairperson:
Yutaka Watanabe(3)Technology ofidentifying internal
conditions /fuel debris
properties
Chairperson:
Shinsuke Yamanaka(4)Treatment/disposal
technology ofradioactive waste
Chairperson:
Osamu Tochiyama*Deliberate and propose solutions through integratingknowledge and experience of remote technology.
©International Research Institute for Nuclear Decommissioning

１３

Measurements against the contaminated water issue
In response to the 1st Inter-Ministerial Council for Contaminated Water and Decommissioning
Issues on September 10, a review team consisting of the related experts mainly from IRID has
been established to implement concrete measures for contaminated water issues.
Solicitation for domestic/foreign technologies, gathering information and classification/sorting of
the proposed technologies will be implemented. The results will be then reported to thegovernmental “Committee on Countermeasures for Contaminated Water Treatment.”<Schedule>
Sep. 20: A website to solicit the technology proposals started. www.IRID.or.jp/cw
Oct. 2: An explanatory meeting on solicitation for the technology proposals(at Iino building, Tokyo).
Early Oct : Information exchange with the foreign organizations, etc.
Oct .23: Deadline for proposals.
Late October to early November: Classification/sorting of the technology proposals.
Nov.15: Report to the Committee on Countermeasures for Contaminated Water
Treatment
Dec.10: Summarize Report to the Committee on Countermeasures for Contaminated
Water Treatment©International Research Institute for Nuclear Decommissioning

１４

Gathering knowledge on contaminated water issue around the world( Contaminated water treatment committees meeting)■ Call for technical proposal◇ An expert team established mainly by the International ResearchInstitute of Nuclear Decommissioning(IRID ) to gather knowledge fromexperts around the world collected the technical proposal. (application
period: Sep. 25-Oct. 23.)
◇ Ideas submitted were evaluated mainly by "contaminated water
treatment committees” to reflect to the preventive and multilayered
measurements on contaminated water .
■ Status of submitted idea
◇Total number of proposals submitted was 780. Details are as follows.

(Note 1) Field of proposal was selected by applicant.
(Note 2) Some of the proposal submitted for one filed were
subject to multiple fields.

◇Large picture of countermeasure technology for contaminatedwater can be overlooked by the technical proposal from around theworld, and all the proposals submitted are valuable data.
◇Following technologies are extracted in reference to the level oftechnological maturity, urgency of measurement, and applicability
to the site etc.
(1) Technology which should be utilized as soon as possible after
confirming applicability to the actual site
 Large size tank with high credibility , like Double steel shell tank etc.
 Light-weight shielding sheet without lead
 Pollution preventing membrane(silt fence) Water stoppage technology (water stoppage inside the building,
stoppage of the water around the building) Maintain geological condition, ground water investigation,observation network etc.
(2) Technology which should be utilized after selecting execution
method in consideration of workability and cost effectiveness etc.
 Countermeasure technology water shielding (phasing , water
shielding etc.)(3)Technology whose that are expected to be effective but need
confirmation and verification before utilization.
 Small leak detection technology (including dose rate) Tank decontamination technology without using water Tritiated water storage ・separation technology
 Purification technology for seawater inside the bay Filter in the ground (capturing technology of strontium in soil) Unmanned boring technologyetc.
(4) Items to be addressed based on the verification results ofcontaminated water treatment committees.
 General evaluation for tritiated water Examination(?) of problems regarding tanker, underground storage
etc.

©International Research Institute for Nuclear Decommissioning

１５

Promoting fundamental studies and human resource development
・Promote the fundamental studies in alliance with universities, research institutes and so forth tosecure human resource and its development from mid-to-long term perspective.
・Through hosting workshops in cooperation with the Ministry of Education, Culture, Sports, Scienceand Technology (MEXT), disseminate and share the information on R&D programs, as well as
considering areas and tasks of any fundamental studies to be focused on that meet practicalneeds.
(Workshops hosted)
Hosted a series of workshops on R&D programs and fundamental studies.
- 1st (September 25, Kanto-1): R/W, Fuel debris.
- 2nd (October 8, Fukushima): Development of remote controlled equipment and device, Datavisualization.
- 3rd (November 1, Kansai/Western Japan-1): R/W, Fuel debris.
- 4th (November 20, Tohoku/Hokkaido): Integrity of PCVs, etc., R/W.
- 5th (November 26, Kanto-2): Development of remote controlled equipment and device.
-6th (Dec. 20, Kansai/West Japan-2):Development of remote controlled equipment and device.
-7th (Dec. 25, Hokuriku-2): Integrity of PCVs, etc., Fuel debris.
Development of remote controlled equipment and device.
-8th (Jan 18, Chubu): Integrity of PCVs, development of remote controlled equipment and device
Fuel debris, R/W.
-9th (Jan. 22, Kanto-3): Fuel debris, material, R/W, and analysis-related issue.
©International Research Institute for Nuclear Decommissioning

１７

Basic Research for Decommissioning etc. and Human Resource Program
Creation of new knowledge on mid-and-long-term decommissioning etc., and development and securing the human resource
development are required through the countermeasures on TEPCO’S Fukushima Daiichi accident.
⇒ In collaboration with International Research Institute for Nuclear Decommissioning, implement basic research by gatheringknowledge and ideas from various fields of research institute such as of universities for the priority area regarding human resource
development defined by the Council for the Decommissioning from perspective of human resource of Mid-and-long term andcreate the deliverables which can contribute to the decommissioning site and human resource development.
Decommissioningof Fukushima
Daiichi

IRID(2)-3 Provide technology(2)-1 Disclose

Integrated managementfor R&D for
decommissioning of Fukushima
Daiichi gathering knowledge
from around the world.

(7) Createdeliverables that
contribute to thedecommissioningsite and humanresource development.

Council for the Decommissioning of Fukushima Daiichi
Deliberate and determine thecritical issue on Decommissioning(1) Needs of the site

2. Can be developed with current
technology

3. basic researches requiring Mid-and-longterm human resource developed
4. Verification(2)-2 Report

Technical
Technical issue
issue･Integrity･Integrity andand reliability
reliability ofof containment
containment vessels/
vessels/ building.
building.
Issue (1):(1): XXXX
XXXX
Issue
･Development,･Development, verification
verification andand operation
operation ofof remoteremote equipment
equipment /device.
/device.
Issue
(2)
:
XXXX
Issue (2) : XXXX
5. Public offering by Ministry of
Education, Culture, Sports, Science and Technology,
a member of council of decommissioning

Basic research of decommissioning/human resource development program
Hub : XXX Univ.
Collaborative
R&D

Collaborative
R&D(8) Provide
deliverable
obtained bydecommissioning
foundation andhuman recourse
development

Hub : XXX Univ.
Collaborative
R&D

Collaborative
R&D

Collaborative
R&D

Collaborative
R&D

Human resource development required fordecommissioning of Fukushima Daiichie.g.) Learn risk communication
Identify mid-and-long-tem roadmap etc.
©International Research Institute for Nuclear Decommissioning

１８

R&D schedule
Having completed Phase 1 of Mid-and-Long-Term Roadmap, R&D will be addressed as follows fromthe Phase 2.
1. Promotion of long-term R&D in response to the start of fuel removal from spent fuel pool.
2. Development of multilateral・multilayered method and equipment for full scale preparation offuel debris retrieval(1) - Submersion method3. Development of multilateral・multilayered method and equipment for full scale preparation of .
fuel debris retrieval(2) - Alternative method4. Stable promotion of R&D inconsideration of treatment and disposal of radioactive waste, anddecommissioning.
December 2011
(Roadmap established)
Efforts to stabilize
plant condition<Achieve cold
shutdown>• Cold shutdown state• Significantly reduceradiation releases

2020-

November 2013

Phase 1

Phase 2

Period up to thecommencement of
the removal of thefuel from the spent
fuel pool (within 2
years)

Period up to thecommencement of theremoval of the fuel debris(within 10 years)

30 to 40years
in the future

Phase 3
Period up to thecompletion of
decommissioning measures(30 to 40 years in the
future)Now©International Research Institute for Nuclear Decommissioning

１９

R&D Activities of IRID
■ R&D activities to be carried out in order to meet severe conditions of reactor
buildings at Fukushima Daiichi.
High dose rate

High temp.

High humidity

RubbleElevated places

Underwater

Narrow places

Injection ofsea water

R&D for fuel removed fromspent fuel pools

DS pitSpent fuelpool
Steam Dryer
Steam
Separator
RPV

Equipment Hatch
Debris

R&D for treatment anddisposal of R/W

2014/11/18

R&D for preparation forfuel debris removal

PCV
Torus room

WM'14 - session 84©International Research Institute for Nuclear Decommissioning

２０

1. Promotion of study from long-term perspective in response to
the start of fuel removal from SFP･Fuel removal from spent fuel pool at Unit 4 was started on Nov. 18, 2013.
･Soundness of transferring these fuels and storage was approved by TEPCO.
･IRID established evaluation method for soundness of long-term storage at the common pool(corrosion resistance etc.), regarding this as one of IRID’s research targets, byobtaining verified data from the fuel at the actual unit. The results obtained from theresearch will be reflected to the actual evaluation.
＜Major activities＞－ Establish test conditions for the long-term soundness evaluation based on the result of
trial examination within 2013
－Also, conduct corrosion test for fuel material, strength test, technology of water quality
effect evaluation.

・In addition, a research on the index for judging the possibility of reprocessing the retrieved
damaged fuel, while taking the adhesion of salt contained in the seawater and physicaldamage by the rubbles into consideration, is ongoing.
＜Major activities＞－Aiming to obtain the research results in 2017, in order to determine the methods of the
spent fuel management and storage based on the case study conducted overseas in2013.

©International Research Institute for Nuclear Decommissioning

２１

R&D and tasks for fuel removal from spent fuel pool – (1)Common Pool (wet type) concerns at storage
corrosion in the common pool material factors■Evaluation of long-term integrity of the fuel assembly removed
from the Spent fuel pool・development of the methods to evaluate long-term integrity offuel assembly considering the specificity of sea water inflow anddebris mixing and study of long-term storage methods.

••■ Tasks
・Corrosion evaluation considering influences such as sea water
inflow at SFP and debris falling etc. in a common pool fuel・development of fuel assembly strength evaluation method
considering corrosion
・dry storage evaluation points study considering environmental
history, technical evaluation

Status of fuelassembly

Influence to the material character byan irradiation history using in thereactorNew aspect exposure by rubbles fallingrubbles environmental factors
•

•
•
•

Taken from upper partof fuel assembly

Elusion from debris with fuel takenfrom SFP
component of sea water
concrete component

FP elusion from damaged part of fuelassembly

Concrete rubbles

Top tie plate
Channel box

Uranium
dioxide pellet

Sealability of cladding• Fuel cladding

Water rodCl‐(ppm)

HandleStructural integrity• Handle• Top tie plate• Tie rod bolt joint

nut
上部
端栓

time

Dissolution test by debris

Immersion test
Planning of investigation and examination

Spacer・ regulation
・examples
・existing test data

Structural integrity• Bottom tie plate

Bottom tie plate
BWR fuel assembly【structural integrity and sealability of cladding】(1)Influential factor
validation test byunirradiated material（2013-2014)(2) accelerating test
using spent fuel from
SFP (2014-)

Common pool storage
status of fuel examination

Dry storage technicalevaluation
・Unirradiated material・storage spent fuel・1F transferred spent fuelFeasibility validation of dry storage

Technical evaluation for dry storage

R&D and tasks for fuel removal from spent fuel pool – (2)■Study for the treatment method of damaged fuels removed from thespent fuel pool・impurities attached and research/study of tasks in the assumption of fuelreprocessing in the possibly damaged spent fuel pool, examination andindexes examination related to reprocessing propriety decision.

【Nitric acid solution of seawater and concrete】■ Tasks
・Considering the influence by engineering damage etc. by falling debris. etc.
・Considering material corrosion by salt and rubbles inside spent fuel cracks,chemical process, and the influence to the property of the waste

Fuel handling【behavior check for impurities at the
reprocessing (image）】

Impurities behavior during process (transition to product type/effluent type)

Import, storage

Shear, dissolve

separate

refinedenitrate

product storage

Test
solutionshear
Uranium refining
Fissionproduct
separation

cask

Test tube

Uranium andplutonium
separation

Heaterdissolve

uranium oxide products
uranium
denitration

Storage pool

Cladding
tube etc.

High level
radioactive
effluent
plutoniumrefinement

Safe storage in canister at 容器に入れて貯蔵庫で安全に保管

Uranium

Plutonium

uranium‐plutonium
mixed denitration

uranium‐plutonium
mixed oxide products

ガラス固化してSafe storage

Fission products (high level radioactive waster

Corrosion influence by impurities on equipment【solution including impurities corrosion test (image)】
Influences to the products
by impurities

Cladding tube etc.

Influence to waste by impurities【trial material of glass solidification with impurities (image)】【possible influences on reprocessing steps by impurities attached or damaged spent fuel】

23

2. Method and equipment in preparation of implementation offuel debris retrieval (1) ‐Submersion method‐(１) Acceleration of investigation and repair (water stoppage) technology development in repose to thecase of water flowing around the lower part of containment vessel
・ Water flow around the containment vessel at Unit 1 was confirmed from the research result obtained by
the remotely operated boat developed through the task force of remote operation technology (Nov. 1314, 2013) .
・Based on this result, aiming at accelerating the process including the investigation for other units in
preparation of development of remote equipment for Investigation and repair of lower part ofcontainment vessel (water stoppage) that IRID promote .
＜Major activities＞－ In FY 2013, continued development of investigation and repair (water stoppage)equipment, andaiming at conducting demonstrations this year while reviewing the development plan (target andprocess) based on the actual conditions.
－ In FY 2015, aiming at conducting demonstrations at mock-up facilities and on site.

－ Also, establishing remote operation subcommittees (tentative name) in IRID technical committees
and build the structures to receive advice for the development and site operation as well as evaluating
the research projects.

©International Research Institute for Nuclear Decommissioning

２２

Operation image of the fuel debris removal
 The approach of removing the fuel debris submerged in water is the safest
approach from the standpoint of minimizing exposure of workers.
 The primary containment vessel (PCV) will be examined and repaired forfilling the PCV with water. Furthermore, R&D for the fuel debris removal
and storage will be implemented.
Overhead crane

Building cover

Canisters of fuel debris

Upper head of the RPVSpent Fuel
Pool (SFP)

Spent Fuel
Pool (SFP)

Reactor Pressure
VesselFilling waterTransfer

Reactor Pressure
VesselPCV

Stopping water
Torus room

Repairing lower section of the PCV(water stoppage)- Filling lower section with water

PCV

PCV

Torus room

Torus room

retrieving the fuel debris(Reference) This figure is based on the documentsof the Council for the Decommissioning of
TEPCO’s Fukushima Daiichi NPS on June 27, 2013.

©International Research Institute for Nuclear Decommissioning

R&D and tasks in preparation for fuel debris retrieval (1)■ development of technology for remotely operated
decontamination in the reactor buildings
・Developing the remote operated decontamination equipment
corresponding to the contamination condition at the site to improvethe environment of investigating leakage of the PCV and repair
works for fuel debris retrieval.

DS pitSpent fuel
pool

蒸気乾燥器
気水
分離器

Device hatch■ Tasks
・Performance verification of developed device by field test
・Development of decontamination devices for high place and upper
floors・Study of environment improving method after retention water
dried up・Operation planning to reduce the exposure of workers to radiation
comprehensively such as combination of decontamination andshieldingHigh pressure water decontamination device

turbinebuilding

RPV

airlockdebrisPCV

sheet18

Torus room

Dry ice blast decontamination robot

Sheet 19
Water
stoppageleakage

Blast & suction recovery decontamination device

26

R&D and tasks in preparation for fuel debris retrieval (2)■ development of technology investigating inside thePCV• developing the devices, research method forunderstanding the condition inside PCV and fuel debris
by remote operation(developing the device to access from X-6 (CRD hatch) tocheck the condition under PCV (pedestal)■ Tasks• Achieving both performance maintenance ofinvestigating devices and accessing device in the highradiation dose environment and downsizing.
• sorting of research areas and items for other projects(fuel debris retrieval etc.)• performance verification of developed devices bydemonstration test

＜access route example to the researching part＞
CRD Housing
Opening of pedestal
X-6 penetration(2)(1)

Pedestal
CRD replacement rail

Platform

Image of accessing inside the PCV
Replacing or
replacement<Access route>(1) Entering from X-6 penetration/ transferring on the CRD replacement rail
(2) Entering the inside of the pedestal
through the opening on the pedestal

27

R&D and tasks in preparation for fuel debris retrieval (3)Development of technology to identify and repair the
leakage points in the PCV• Development of the methods and equipment to investigate
and repair for the leakage from the PCV, etc. (water
stoppage) considering the environment, such as high places,high radiation dose, narrow spaces, and under water.

(R&D example)
Torus room wall

S/C

Torus roomWallpenetration

Tasks• Performance verification of developed devices bydemonstration test
• Establishing measuring technology for determining thenecessity of repair and judging points.
• Development of boundary considering things other than
PCV main body (system-side)

Retained
water

Check the leakage
investigating tracer
by ultrasonic wave

Traveling under water and checking Torus room wall penetration

Vent pipe - D/W joint
Adhering and running from the hole on the first floor to Vent pipe andchecking the joint part
Vent pipe
D/W joint part

Check the waterleakage by indirectly
viewing

PCV

Check damages ofTorus room wall
penetration by camera

Vent pipe bellows

28

R&D and tasks in preparation for fuel debris retrieval (4)Development of integrity verification technology of RPV / PCV• Estimation of structural strength decline by sea water inflow→Evaluating device/structural integrity and remaining life at various possible
plant conditions toward fuel debris retrieval• Establishing the method of prolonging life such as corrosion inhibition etc.
→Applying devices with less tolerance on the above evaluation as necessaryTasks• The acquisition of a parameter of key actual unit and establishment ofrational evaluation terms under the unclear circumstance of actual unit
conditions.
• Estimation of long-term integrity on the material deterioration data in thelimited evaluation time

Before the test

Corrosion testing status and example of the results(carbon steel / low alloy steel)

PCV(Low alloy steel)

PCV(Carbon steel)

PRV pedestal(reinforced concrete)

After the test

PRV pedestal
seismic-assessment model29

R&D and tasks in preparation for fuel debris retrieval (5)understanding fuel debris conditions / treatment technology
development• Estimation in advance of various debris characters information forfuel debris retrieval safety guarantee, retrieval equipment,
storage container development etc.
• study of each treatment for the discussion of the debris end-statechoice after retrieval
Tasks• Considering special terms of 1F accident (seawater influence etc.)• Actual debris sampling at 1F will take time・TMI-2 and previous severe accidents research⇒・combination of accident progress analysis and chemical
equilibrium calculation
・Simulation debris making and the property determination
The property estimation of these combinations are needed

Test result sample
Heating pellet type simulated
debris with seawater salt (inthe air – 1000c-12h)••

MgO accumulating layer

Uranate layer

Simulateddebris pellet

MgO accumulating on the surface
Forming the uranate layer【high-temperature reaction test of simulation debris and seawater salt】

Damaged fuel(debris)【Fuel debris sample takenfrom TMI-2】
1. Cutting tool A

4. Collecting tool

Example: Air Chisel
Principle: strike / shock
Utility: massive debris crushing etc.

Example:スペードバケット
Principle: Pick & Place
Utility：collecting small piece ofdebris

2. Cutting tool B

5. Suction system

Example: Heavy duty shears

Example: Air Lift

Principle: shearing
Utility: pipe, thin board cutting etc.

Principle：suction

3. Cutting tool C

Utility：collecting pulverize debris

6. Core boring

Example: plasma arc cutter

Example: Boring system

Principle: fusing
Utility: complicated structure
fractionalization

Principle: grinding・compression
Utility: Hard crust drilling etc.

【 classification of tools for retrieval】
w/o Intermediate process
w/ intermediate process

short-term
storage<Treatment scenario study>
Each scenario information are arranged
preparing for discussion on comparativeevaluation until fuel debris retrieval starting(around 2020)

long-term
storage【Individual technology development(2-①-6)/(2-①-7)】

stock【Individual technology development (2-③-3)】

wet processing

waste bodyU/Puwaste body
dry processing

U/Pu【Individual technology development (3-2)】

processing

waste bodywaste body (direct disposal)【Choices related to the treatment（processing, disposal)(examples) 】

R&D and tasks in preparation for fuel debris retrieval (6)■ Tasks
・data requirement for critical control study andelaborating evaluation reflecting latest news
・Monitoring method during operation, boric acidamount at the critical point, proposal for the criticalpoint management to the site
・Evaluation of the possibility of critical point basedon the scenario, formulation of the determinationreference for reasonable critical point evaluation
・Establishment of critical point management
Depend on construction method / design of fueldebris retrieval, storage etc.

••

Critical scenario sorting
Re-criticality behavior evaluation

Critical point detection
technology•
non-criticality
detection• re-criticality detection

criticality prevention
technology•
neutronabsorbent

Fuel debris critical point management
technology development

Waste liquid
treatment,
subcriticalityof coolerequipment

Inside thereactor (inside
the PCV) recriticality

Retained water fullscale processing or
circulation loop

■Development of fuel debris criticality control
technology
Developing critical control technologies such as
subcritical evaluation of Fuel debris retrieval worketc., monitoring technology and prevent re-criticaltechnology (neutron absorber material etc.)

Fuel debris critical estimation
technology

Object of critical point detection technology

Neutron absorber examination case
Solubility

Pentaboric acid sodium etc.
Absorber ：borosilicate glass, B4C/SUS
sintered body, gadolinia etc.
binder：Slurry, gel, cement, water glass etc.
Gel absorber

Insolubility

Right：binder example

Fuel debris

Binder: Medium absorbing absorber for fuel debris

31

R&D and tasks in preparation for fuel debris retrieval (7)Single transition path

■Understanding of the Reactor core condition utilizing
severe accident analysis code
To carry out the accident progress analysis by the latest
severe accident analysis code, compared with actualunit parameter and extracted improved code items
based on PIRT, upgrading improved items of accident
progress analysis code, estimate and understand thecondition inside the reactor utilizing upgraded analysis
code.

Multi path
ShroudReactor coreCore melt
Core support plate

Particulate debris■Tasks

Metal layer

・Improving a model accuracy
・ In the process of creating PIRT, younger generation
participate discussion with national and international
experts to cooperate with Atomic Energy Society ofJapan during creating process and workshops etc. atOECD / NEA. Arranging these opportunities
continuously is needed for future human resource
development.

Regular debris accumulation

Debris spread fixing

Note: PIRT(Phenomena Identification and Ranking Table)

Asymmetry consideration /interaction refinement with thestructure

Modeling of spread
behavior based on
physical properties etc.

Molten pool
Solidified crust

PCV floor

32

R&D and tasks in preparation for fuel debris retrieval (8)■the inside of RPV investigation technology Development
・Retrieval from the inside of Reactor Pressure vessel (RPV) For retrieval from the inside of Reactor pressure
vessel (RPV), to develop the technology to understand the situation inside the RPV (pressure, temperature, dose,
equipment damages inside the reactor, fuel debris position etc.) and to enable fuel debris sampling■Tasks・access to the inside of RPV technology development considering the investigation purpose, site environment(dose, equipment damage etc.)
・Investigation technology development to enable to use at the possible severe condition (high dose, highhumidity etc.) inside the RPV.
＜Access method study example＞

Investigationequipment

Example to access through pipes

Example to access opening the hole

Example of accessing method after
opening the reactor

33

R&D and tasks in preparation for fuel debris retrieval (9)Fuel debris collecting, transferring, storage technology
development
Examination related to damaged fuel transfer and storage result
examination
Damaged fuel (including leaked fuel) transfer, storage result
examination (N. America (TMI-2), Europe (Paks))
Examination of Fuel debris storage system
Storage actual result of Spent fuel debris (concrete cask system(including horizontal silo) Vault method)
Task extraction and master plan creating
TasksTo extract technical tasks for the container management technology
development and the container specifications for transfer andstorage, considering 1F fuel debris distinctive condition (highradiation work environment, introduce seawater into the inside of
the reactor).
To sort the interface information (Debris property understanding PJ,
retrieval method PJ etc.) for developing and necessary timing.
•To reflect onto the storage can development project.

Opened thelid and
Fuel loading

Debris inflow
貫通孔から
from
the
デブリ流入
through-hole＜Fuel canister*＞・Filling piece of fuel assembly or fuel debris capable of handling jig
by remote control handling jig＜Knockout canister* ＞
・collecting particles over 140μｍ by vacuum suction system＜Filtering canister※ ＞
・collecting particles under 800μｍ by vacuum system※：Storage can is called Canister at TMI
Several canisters are used based on the form of fuel or fueldebris but those external dimensions are all same and thetransfer container is used in common

Fig. Canister for debris inside the reactor (TMI case)34

３. Development of multilateral and multilayered method andequipment in preparation of implementation of fuel debris retrieval(2) ‐Innovative approach‐(２) Innovative approach and Request for Information of technology for theidentification of fuel debris condition and acceleration of retrieval
・Mid-and-long-Term Roadmap states that the innovative approach other than
Submersion method shall be considered. Therefore started Request for Information(RFI) to seek information from overseas research institutes and corporations, aiming toconduct feasibility study (Ｆ/Ｓ, after 2015) of the technologies to identify the locationand the condition of the fuel debris required for the methods of investigation andretrieval work.
・Information submitted will be utilized for Conceptual Study and Technical feasibility
study (Ｆ/Ｓ).
・IRID expect this RFI to be an opportunity for collaboration with related parties
around the world.

©International Research Institute for Nuclear Decommissioning

２４

Announcement on RFI procedures andpromotion for invitation
IRID has been promoting publication and application for RFI, and announcement of RFI procedures since
fall of 2013 as well as providing reference information necessary for the study.
Announcement of RFI procedures andOutline of activities
Promotion activity of RFI invitation•Nov.

Opened website for invitation.
Held overseas workshop.

•Establishment/
announcement
on RFI
procedures

Sent reminder mail.
•Dec.

Announced RFI procedures .

•Holding ofworkshop

Held domestic workshop.
Set up web forms forapplication.
Uploaded basic data ofFukushima Daiichi NPS on the web. .
•Jan

Uploaded technical issues･
related R&D status.
Sent reminder mail.

• Provision ofreference info
for related
technology.
•Delivery of
RFI notice Established Entry form as well as opened website forapplication and announced procedures for RFI for
applicant’s convenience.
 Held workshop in Japan and overseas forthe publication of background and purpose of RFI
and promoted invitation.
Venue : UK, France, US, Canada, Germany and Japan.
- Tens of people attended from related company,
R&D agency for each workshop.
About 130 participants from Japan.

 Disclosed reference technology data on the website
for information collection for RFI- Basic data of Fukushima Daiichi NPS (Structure /external
dimension etc.)- Technical issues and status of R&D in Japan/overseas.

 Made announcements regarding implementation of RFI
and uploading of reference information for followings.
- Overseas and domestic related academic meeting , andindustry organization.
- Companies participated in previous workshop .

©International Research Institute for Nuclear Decommissioning

36

Contents of RFI
Topic A: Internal PCV/RPV investigation
A-1:Conceptual study of method (following aresamples)

1. Method of inserting investigation device e.g.
cameras inside.
a. Utilize current throughbore such as
piping/penetration.
b. Create new throughbore .
c. Methods of shielding penetrations and of
equipment operation in terms of reduction ofradiation exposure.
2. Method of detecting fuel debris location bymeasuring from outside, etc.

A-2:Required technologies (following are samples)
1. Advanced measurement technology (e.g. camera,
dosimeter, thermometer)
a. High performance optical equipment(e.g.
camera), other measurement technology (e.g.
ultrasonic, laser)b. Control technology of measuring instrument,
and information transmission technology .
2. Technology to detect whether the substance in thereactor is fuel debris or not.

Topic B: Fuel debris retrieval
B-1:Conceptual study of method (following aresamples)
1. Access to fuel debris from the top of PCV underwater
2. Access to fuel debris from the top of PCV in the air*1
3. Access to fuel debris from the side of PCV in the air*1
4. Access to fuel debris from the bottom of PCV in the air*1*1 including partial submergence

B-2:Required technologies (following are samples)
1. Technology regarding fuel debris retrieval (cutting,suction).
2. Equipment/device such as remote control manipulator,
with superior control capability from long distance.
3. Technology of shielding against fuel debris withhigh radiation.
4. Device and equipment capable of working under the highradiation environment.
5. Equipment/device to create a borehole on thebuilding concrete and PCV to enable access from the sideor bottom of the PCV.
6. Technology to store fuel debris safely in PCV/RPV
before retrieving.

©International Research Institute for Nuclear Decommissioning

２５

e.g. Fuel debris retrieval work (from top and side)

Fuel debris storage canRetrieve from the top

carry out

Retrieve from the side

Containment vessel
Torus room
Fuel debris retrieval

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38 ２６

Results of RFI
About 60% and 40% of the proposal were submitted from Japan and overseas countries respectively

Total

JPN

US

Breakdown by country
GER FRA
UK
BEL

33

20

7

3

-

2

-

1

-

A-2:Required
technology

58

32

6

10

6

2

2

-

-

B-1:Conceptual
study
for the method

43

23

8

3

2

5

-

1

1

B-2:Required
technology

60

41

7

3

4

2

2

-

1

Total (No. of items
of information)

194

116

28

19

12

11

4

2

2

Topic A
Internal PCV/RPV
investigation•Field of proposal for RFI
A-1:Conceptual
study for the
methodTopic B
Fuel debris
retrieval

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CAN

RUS

39 ２７

Reference: Upcoming schedule
2014
Apr

May

4/25

RFP
for entities
toimplement
the subsidy

Workshop

Jun

Jul

Aug

2015
Sep

Oct

Nov

Dec

Jan

Feb

Mar

Two months
Commencementof RFP

Deadline

Information
session of RFP

Review
Adoption
Coordination of
the contents, etc.

F/S, C/S

Decision on the
grant

Implementationof F/S, C/S

Progress report Result report”Project scheme of Decommissioning and Contaminated Water Management and RFP schedule” (Taken from adocument by MRI’s Management Office for the Project of Decommissioning and Contaminated Water Management)4. Stable promotion of R&D from the perspective of radioactive
material treatment and disposal• Conducted radionuclide analysis of sampled rubbles, felled tree and contaminated water among
other specimens from the site. Currently working on inventory evaluation of waste material basedon the results of these nuclide analysis.
• Further accumulation and evaluation of analysis data are planned. In addition, a prospect of theadsorption vessel of waste zeolite generated by contaminated water treatment maintaining its
soundness at the salt concentration level in the storage condition has been already confirmed.
＜Major activities＞－ Continue studies on the technologies for storage, identifying the properties, waste forming anddisposal to secure a prospect of maintaining the safety of the treatment and disposal of solid
waste－ Examine and establish the decommissioning scenario by collecting and organizing the conceptsof security control for the decommissioning from 2014.
－ For the issues with relatively high risks which are required to be addressed promptly, according
to the progress of decommissioning, promote studies flexibly while taking account of relations
with R&D plans defined in the Mid-and-Long-Term Roadmap and the priorities
For example, stabilization of the watery waste material such as slurry coprecipitation with iron and slurry of settled carbonate,
which are expected to be generated by ALPS as countermeasures for the contaminate water, shall be promoted forthwith.
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41 ２８

R&D and tasks of radioactive waste processing and disposal■Development of radioactive waste treatment and disposal technology
Having the prospect of the safety for processing, disposal, with studying of property understanding anddisposal, study of radioactive waste disposal (including long-term storage).

■ Tasks・adhesion of radioactive nuclide caused by damaged fuel, seawater component-containing etc. It has
different character from radioactive waste produced by current Nuclear power station, radioactive waste
produced by the accident is including the one which rarely process and dispose in Japan.
<sampling at the site>
RubbleStudy of method waste
the property understanding(Inventory, chemical composition etc.)
Secondary waste reflex/Review of waste sorting

Cutting trees

Analysis subject
samples, the prioritybased rating nuclideetc.

Study for radioactive waste processing(inc. storage, preprocessing, being waste disposed
setting of targets toimprove efficiency ofwaste body, etc.

Study for waste disposal（※）
Disposal concept study

Safety evaluation（※）<Development of waste solidified technology>
Geopolymer
amorphous state inorganic material
mainly consisted by AI and Si
Character ・high Metal ion CONTAINMENT・fire-resistantSummary
1.

IRID was established in Aug. 2013 as an integrated organization to conduct researches bygathering knowledge around the world according to the Mid-and-Long-Term Roadmap.

2.

As for R&D, IRID conducts an integrated management to promote multiple R&D projects
effectively. Fields of the R&D consists of following three. IRID also plans a total strategy of
the technologies required for the decommissioning by optimizing the on-site needs andtechnological seeds.
1. Removal of fuel from spent fuel pool
2. Preparation of fuel debris removal
3. Treatment and disposal of radioactive materials

3.

For the purpose of gathering knowledge around the world , IRID advances theestablishment of a structure to receive advise from the experienced experts around theworld through “International Advisors”, “Technology Advisory Committee” and“International Expert Group”, as well as considering the involvement in the joint research
project through OECD/NEA and responding to the IAEA review. Also, conduct Request for
Information (RFI) internationally for the countermeasures on contaminated water andfuel debris retrieval.

4.

Hold workshops to build a structure to promote basic researches in collaboration withresearch institutes and universities with Mid-and-Long-Term human resource
development in consideration.

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43 ２９