PRO GRESSR E P O R T

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P R O G R E S S R E P O R T 2019

IRID amasses knowledge from arou nd the world for
the R&D on n uclear decommissioni ng
under an integrated management sy stem.
Decommissioning of Fukushima Daiichi is unique, unprecedented and extremely difficult tasks in the world. IRID is promoting R&D bygathering global knowledge while taking the technological challenges to be overcome.

Greeting

What

Since its establishment in August 2013 the International Research Institute for Nuclear Decommissioning (IRID) has been fully committed to an
urgent challenge: Research and Development (R&D) of the technologies required in the decommissioning of the Fukushima Daiichi Nuclear
Power Station (NPS). In August 2014, the Nuclear Damage Liability Facilitation Fund was reorganized as the Nuclear Damage Compensation
and Decommissioning Facilitation Corporation (NDF). The division of roles among the relevant organizations engaging in the decommissioning
was then clarified: The NDF formulates strategies and R&D plans for the decommissioning; The Tokyo Electric Power Company (TEPCO)
implements on-site operations; and IRID conducts R&D of the technology required in the decommissioning work. The four key players, including
the government, have been working closely together in the effort to decommission the Fukushima Daiichi NPS.

PurposeTo conduct testing and research for the decommissioning of nuclear
power stations, and implement projects aimed at improving thetechnological level of IRID member organizations and to put
technologies they develop into practical use.

This has resulted in the development of technology for investigating inside the primary containment vessel and the development of technology for
identifying fuel debris using cosmic rays, and thus the situation inside the Primary Containment Vessel (PCV) has been clarified while thetechnological challenges that have to be overcome have also become clearer.
The Mid-and-Long-Term Roadmap was revised by the government after reflecting a revision of the “Technical Strategic Plan 2017 forDecommissioning of the Fukushima Daiichi NPS of TEPCO Holdings, Ltd.” (Strategic Plan 2017, hereinafter) made by NDF, which provides thetechnological basis for the NDF Mid-and-Long-Term Roadmap for Decommissioning of the Fukushima Daiichi NPS of TEPCO Holdings, Ltd.
(Mid-and-Long-Term Roadmap, hereinafter) in September 2017.
It has been expressed that the policy with fuel debris retrieval should focus on the partial submersion side access method and retrieval of debris
from the bottom of the PCV, and that the fuel debris retrieval method for an initial unit will be determined in FY 2019. R&D on the fuel debris
retrieval is therefore about to enter a crucial phase.
In ensuring safe and secure decommissioning of the Fukushima Daiichi NPS, the IRID
is committed to the responsibility of making steady achievements in R&D with respect
to the reconstruction of Fukushima, and amassing knowledge from all over the world.
Furthermore, IRID would like to contribute to the next generations through the R&D weare involved in.

Basic principles
We devote ourselves to research and development (R&D)
of technology for the current, most urgent challenge,
the decommissioning of the Fukushima Daiichi Nuclear Power Station (NPS),
from the standpoint of strengthening the foundation of nuclear decommissioning technology.

Our Principles in Action

1

International ResearchInstitute for Nuclear
Decommissioning

We sincerely appreciate your kind guidance, continued support, and encouragement.
January 2019

President

Hideo Ishibashi

2

C O N T E N T S◆IRID Organization Information ・・・・・・・・・・・・・・・・・・・・・・・・・ 02●

Organization Profile●

Organizational Structure◆Roles of IRID・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・ 04●

Activities of IRID●

Role of the Organizations for the Decommissioning Projectof the Fukushima Daiichi NPS●

History: Chronology of IRID activities●

Overview of the Mid-and-Long-Term Roadmap●

IRID’s R&D Scope●

List of Government Subsidized R&D Projects Conducted by IRID

◆Scope of Work 1 : R&D for Nuclear Decommissioning・・・・・ 08

We work on R&D projects effectively and efficiently while advancing integrated project
management to develop and propose the best technologies and systems that are able tobe applied on site at the Fukushima Daiichi NPS at an early stage, in the face ofnumerous extremely difficult technological challenges.
We build an optimal R&D structure through cooperation with relevant organizations aswell as IRID member organizations and gathering knowledge from Japan and abroad.

3

We actively promote efforts to develop and secure human resources who will comprisethe next generation of those working in nuclear decommissioning and related
technologies, including efforts to collaborate with universities and research institutions.

4

We strive to release information on our R&D activities and results to obtain theunderstanding of Japanese people, including those in Fukushima, and the international
community to relieve their anxieties.

5

We form an international research hub (center of excellence) through our R&D activities
and contribute to the acceleration of the decommissioning of the Fukushima Daiichi NPS
and improvement of technological capabilities in the international community.

IRID’s R&D●

aims for・

CLOSE UP Policy of Fuel Debris Retrieval and Current Approach

Overview of IRID’s R&D Projects
Major R&D topics●

CLOSE UP

R&D Collaboration with Universities (Actual Projects)◆Scope of Work 2: Human Resources Development in R&D ・・・・・ 15●

PR Activities at Universities and Research Institutes●

IRID Symposium◆Scope of Work 3: R&D with Overseas Organizations ・・・・ 16●

CLOSE UP Enhancement of Cooperation with International Organizations

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P R O G R E S S R E P O R T 2019

IRID Organization Information
Organization Profile

Organizational Structure

1. Name of the Organization

5. Memberships (18 organizations)International Research Institute for
Nuclear Decommissioning (IRID)<National research and development agency>

General Meeting

Japan Atomic Energy Agency
National Institute of Advanced Industrial Science and Technology

Board of Directors

International Advisors<Plant manufacturers, etc.>

2 The Head Office
5F, 3 Toyokaiji Building, 2-23-1 Nishi-Shimbashi,
Minato-ku, Tokyo 105-0003, Japan
TEL:+81 3 6435 8601

3. Establishment dateAugust 1, 2013

Establishment was approved by the Minister of
Economy, Trade and Industry based on the
Research and Development Partnership Act.

4. Scope of WorkR&D for nuclear decommissioning● Promotion of cooperation on nuclear decommissioning with
relevant international and domestic organizations● Human resource development for R&D●

Toshiba Energy Systems & Solutions Corporation
Hitachi-GE Nuclear Energy, Ltd.
Mitsubishi Heavy Industries, Ltd.
ATOX Co., Ltd.

<Electric utilities, etc.>

Hokkaido Electric Power Co., Inc. Tohoku Electric Power Co., Inc.
Tokyo Electric Power Company Holdings, Inc.
Chubu Electric Power Co., Inc. Hokuriku Electric Power Company
The Kansai Electric Power Comapany, Inc. The Chugoku Electric Power Co., Inc.
Shikoku Electric Power Company, Inc.
Kyushu Electric Power Company, Inc.
The Japan Atomic Power Company
Electric Power Development Co., Ltd. Japan Nuclear Fuel Limited

6. Board of Directors: Hideo Ishibashi
President
Vice president : Tamio AraiManaging Director : Tadashi Kawamura: Shunji Yamamoto, Hiroshi Arima, Satoshi Ueda,
Directors
Akihiko Kato, Shigemitsu Suzuki, Satoshi Sekiguchi,
Koichi Noda, Goro Yanase: Masao Nakanishi
Auditor7．Number of staff
847 *(Excluding Directors) *Including members of the above

membership organizations who are
engaged in IRID’s resarch.
（As of October 1, 2018)

The 1 s t report on Mid-and-Long-Term actions to be taken at the160

dedicated national organization to engage in the decommissioning would
be necessary, and this proposal was then discussed by the Atomic Energy

120

120

148

143

149

Naraha Development Centerorganization was specifically expressed at the Council for theRadioactive Waste
Treatment and Disposal
Technology Group

Fuel Debris
Investigation & Evaluation
Technology Group

Reference: Technology Research Associations
Technology Research Associations are mutual aid organizations (non-profit mutual benefit corporations) that conduct
joint research on technologies for use in industrial activities that can benefit the association members. IRID was createdas a Technology Research Association in order to rapidly systemize its activities, and to take advantage of the transparency and flexibility offered within the running of the organization.

Overview of the Technology Research Association Model

University, etc.
(Association Member)

Decommissioning of TEPCO’s Fukushima Daiichi NPS in March 2013. As

submitted to the Ministry of Economy, Trade and Industry (METI) in late46

July, which was then granted by the minister of the METI on August 1,
2013. That approval resulted in a General Meeting of the autonomous
legislative body of the organization being held to commence operation of
the IRID on August 8, 2013.

0240●1.Organizational Change

Transform the organization into a stock company or limited liability
company in thereby ensuring smooth implementation of the results of research.

R&D tax expenses Contribution

R&D tax expenses Contribution

Approvals
Legal personality
Technology Research
Association
Deferred tax reserves

Public researchInstitute

Stock company or Limited Liability Company●2.Incorporation-type Company Split

Set up a stock company or limited liability company through an incorporationtype company split, and commence sequential implementation of research results.

Stock company or Limited Liability Company established through a partition●3.Dissolution

The Technology Research Association is dissolved and association
members then use their research results.

(Association Member)●4.Splitting of the Technology Research Association

Specific research themes are selected, and the association is then partitioned based on them.

Technology Research Association
established through partition

80

organization, a request for approval for the establishment of the IRID was

Fuel Debris Retrieval
Technology Group（As of April, 2018)

Technology
Research
Associationa result of continuous study via the establishment of a preparation

Accounting Group

Corporate Communications Group

Commission.
In response to that situation, the need for establishment of a new

Administration Dept.

International &Academia Cooperation Group

Company(Association Member)four months later than March 2011 when the accident at the Fukushima

R&D Management Dept.

Planning & Management Group

Company(Association Member)(100 million yen )Daiichi NPS occurred. At that time various experts proposed that a

R&D Strategy Planning Dept.

Research results<The Circumstances until Establishment>

Project Costs

Fukushima Daiichi Nuclear Power Station (NPS) was created in July 2011,

Technology Advisory Committee

Features of a Technology Research Association● Each of association member provides researchers, funds, and equipment for use in joint

research. These are jointly managed and utilized among all the members.
● Technology Research Associations are joint research organizations that have a legal
identity independent of association members.
● Transparency and reliability of the management of the association can be increased withthe approval of the Minister in charge, and by holding regular association member
meetings/board of director meetings.

● Those directly or indirectly using the results of the joint research (including corporations,individuals, foreign companies and foreign nationals) can become association members.
● Universities, research and development incorporated administrative agencies, technicalcolleges, local government organizations or foundations primarily engaged in testing andresearch can participate as association members. This participation then provides
opportunities for cooperation between industry, academia and the government.
(Source) Excerpt from the Technological Research Association”,
the Ministry of Economy, Trade and Industry Website.

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P R O G R E S S R E P O R T 2019

Role
ole of IRID
IRID works for R&D of decommissioning under a major policyof the national government while closely cooperating with related organizations
involved in the decommissioning work of the Fukushima Daiichi NPS.
IRID has a three-pronged strategy; R&D of decommissioning, cooperation
with domestic and overseas organizations and human resource development.

Roles of the Organizations for the Decommissioning Project of the Fukushima Daiichi NPS(Fukushima Daiichi D&D Engineering Company)

Progress management

Steady implementation of decommissioning

ReportMid-and-Long-Term Roadmap● Ensure safety/quality, improve work environments, etc.

R&D needs

Formulation of strategies andprovision of technological support

Implementation of R&D

Share progress
and issues● Carry out R&D planning and● R&D for preparation for fuel debris retrieval

2014〈August〉〈January〉

development of human resources
contributing to R&D〈December〉○Holding the 1st Technology Advisory
Committee

waste R&D results

Strategic plan
Reportresults
Project cost
(Subsidy)

Nuclear Regulation Authority
Implementation of safety regulations

IRID is committed to the decommissioning activities of the
Fukushima Daiichi NPS as a part of the decommissioning
organizations.

○Holding the 1st International Advisors
meeting〈March〉○Verification tests on thesuction and blast
decontamination devices〈May〉〈August〉○Investigation of the upper partof the suppression chamber (S/C)
in unit 1 using an investigative
device.

○Nuclear Damage Compensation
Facilitation Corporation wasrestructured to Nuclear Damage
Compensation and Decommissioning
Facilitation Corporation (NDF).

○With the joining of ATOX Co., Ltd.,the organization became an 18corporate structure as is current○Appointment of the 2nd president
Hirofumi Kaneda〈April〉〈July〉〈September〉○Verification tests on low
place decontamination devices(Dry ice blast device)○Holding the 1st IRID Symposium 2014
(In Tokyo)○Investigation of the wall of the torus
room in unit 2 using a submersible
robot and a floor traveling robot○Investigation of the unit 2 Suppression
Chamber (S/C) lower outer surface
using investigative apparatus○Verification tests on low
place decontamination devices(High pressure water
decontamination device)〈November〉○Investigation of the spent fuel poolthat was transferred to the common
pool at Unit 4.
○Holding the 2nd International
Advisors Meeting.

Funds for technology
development■…R&D■…Human resources development■…International relationship

2015

2016

2017

〈February – May, May – September〉〈March – July〉〈February〉〈July〉〈January〉○Observing unit 1 by using muontransmission method technology○Observing unit 2 by using muontransmission method technology○Investigation of the inside of theunit 2 PCV using a scorpion
robot○Investigation of the insideof the unit 3 PCV using
a submersible ROV〈April〉〈April〉○Investigation of theinside of theUnit 2 PCV using
a telescopic
investigative device○Investigation of the inside of the unit 1
Primary Containment Vessel (PCV) using
a robot, namely the PMORPH 1○Completing the Full-scale mock-up
facility in the JAEA Naraha Remote
Technology Center〈July〉〈May〉○Holding the IRID Symposium 2015
(In Fukushima city)〈December〉○Developing an upper floor
decontamination device○Holding the 3rd International Advisors
meeting○Verification tests of a high placedecontamination device (Dry ice blast
decontamination device) on the
1st floor of the unit 3 reactor building〈August〉○ Holding IRID Symposium 2016
(In Tokyo)〈November〉
04

progress management, etc.

● R&D for treatment and disposal of solid radioactive

Chronology of IRID activities

2013○Holding the 1st workshop as● Progress management andtechnical support for key issues● R&D for fuel removal from spent fuel pools■…General〈September〉● Develop a mid-and-long-term strategy

Issue project grant

Nuclear Damage Compensation
and Decommissioning Facilitation
Corporation(NDF)

R&D results

operations, and IRID conducts R&D.

Present Key issues

ReportFor R&D on thedecommissioning

Report/apply

Human resource
development

ReportAdvice/Guidance

R&D Proposal
Practical applications ofdevelopment results
providing information

Supervise/Review

Cooperation withrelated domestic
and overseasorganizations
For decommissioning

ReportImplementation plan

For nuclear
decommissioning

In addition, it is necessary to amass further knowledge fromboth Japan and abroad to proceed with the decommissioningof the Fukushima Daiichi NPS, which is unprecedented in theworld and extremely difficult; therefore, the IRID is promoting
cooperation with related domestic and internationalorganizations. Moreover, the IRID is promoting thedevelopment of the necessary human resources to continue
the decommissioning work of the Fukushima Daiichi NPS.
A structure has been established in which three organizations
cooperate closely together as one team and where eachrole for decommissioning the Fukushima Daiichi NPS isclarified: “Nuclear Damage Compensation Facilitation
Corporation (NDF)” formulates strategies and R&D plansfor decommissioning, “TEPCO Holdings” performs on-site● Store and manage rubble, waste, etc.

R&D

Although it aims toward cultivation and accumulation of thetechnologies necessary for the entire decommissioning inJapan, currently it is tackling R&D for the decommissioning of
the Fukushima Daiichi NPS as an urgent challenge basedon the goverment-led Mid-and-Long-Term Roadmap.

Institute for Nuclear Decommissioning (IRID)(Started with 17 corporates)
First president Hajimu Yamana● Formulate the Mid-and-Long-Term Roadmap, etc.

● Manage contaminated water

IRID is an organization composed of 18 corporates thatare leading players for research and development (R&D)
of decommissioning the Fukushima Daiichi Nuclear Power
Station (NPS).

○Establishment of International Research

Policy making and progress management● Remove fuel from spent fuel pools

Activities of IRIDHISTORY

Government

TEPCO Holdings○Holding the 4th International Advisors
meeting〈March〉○Investigation of the inside of theunit 1 PCV using PMORPH 2〈May – September〉○Observing unit 3 by using muon
tomography〈June〉○Executing a full-scale test by
filling water stoppage material
in the suppression chamber(S/C)○Appointment of the 3rd president
Hideo Ishibashi

2018○Full-scale testing of
reinforcement
technology for the Suppression
Chamber(S/C) support columns〈August〉○ Holding the IRID Symposium
2018 (in Tokyo)〈August〉○Holding the IRID Symposium2017 (In Iwaki city)〈Decembert〉○Holding the 6thInternational Advisors Meeting〈December〉○Holding the 5thInternational Advisors meeting05

P R O G R E S S R E P O R T 2019

Role of IRID
Overview of the Mid-and-Long-Term Roadmap (Revised on September 26, 2017)
Decommissioning of the Fukushima Daiichi Nuclear Power Station (NPS) is proceeding based on the “Mid-and-Long-Term
Roadmap for Decommissioning of the Fukushima Daiichi NPS of the Tokyo Electric Power Company (TEPCO)
Holdings, Ltd.” (Mid-and-Long-Term Roadmap, herein after) that was decided by the government.
The period until completion of the decommissioning work is divided into 3 phases: 1st phase – 3rd phase and thecurrent period is the 2nd phase, “R&D to prepare for fuel debris retrieval.”
The current Mid-and-Long-Term Roadmap revised in September 2017 (4 th revision), in which the target processes(milestones) is described under the premise that it is subject to be revised depending on the on-site situation and
R&D results, aims for starting fuel debris retrieval at the initial unit during 2021.

Phases in the Mid-and-Long-Term Roadmap
December 2011
(Step 2* completed)

November 2013
(Starting fuel retrieval from unit 4)

Efforts to stabilize
conditions of the plant*Step 2Controlling radioactive
material release,achieving significant
reduction of radiation dose
● Accomplishment of cold
shutdown state●

December 2021

Phase 1

Phase 2

Period up to thecommencement offuel removal from spent fuelpool of the first unit

Period up to thecommencement offuel debris retrieval
from the first unit

Period up to thecompletion of
decommissioning(Within 2 years)(Within 10 years)(30 – 40 years later)

Phase 3( ) means the period from completing phase 2.

IRID has been engaged in various R&D activities under the
Mid-and-Long-Term Roadmap. As a result, IRID successfully
visualized inside the reactor by investigation inside the primarycontainment vessel using remote-operated robots andtomography utilizing a cosmic ray muon. On the other hand,
technological issues to overcome are also clarified.

○Clarification of target processes (milestones)

IRID continues challenging those issues and does its best for
the R&D required for the commencement of fuel debris retrieval
from the initial unit during 2021.

Decision on fuel debris retrieval policy (September, 2017)
Finalization of fuel debris retrieval methods for the initial Unit (FY2019)● Start of fuel debris retrieval at the initial Unit (within 2021)●*Resource: Mid-and-Long-Term Roadmap (4th revision) on September 26, 2017

Continuation of cold shutdown state of the reactor
Treatment of accumulated water(Countermeasure for contaminated water)● Reduction of radiation dose as a whole plant,
preventing spread of contamination

Overview of R&D●●

Fuel retrieval from spent fuel pool
● Fuel debris retrieval● Plan for storage/control and treatment/
disposal of solid wastes
Decommissioning plan of
nuclear reactor facility

R&D isconducted by
IRID.

Project name

Project Summary

PeriodMinistry of Economy, Trade and Industry
Agency for Natural Resources and Energy(As of end of June, 2018)*¹
SupplementarybudgetSubsidy project
Maximum Cost *2(Subsidy Rate)

Fuel debris characterization/
development of analysis technologies(1)Estimation of properties of fuel debris in the reactor(2)Characterization using simulated debris(3)Development of element technology for fuel debris analysis

April 1,2017- March
31, 2019

FY20160.65 billion JPY(Fixed)Development of technologies for detailed
investigation inside the primary containment vessel(1)Formation and upgrading of investigation and development plans(2)Development of access equipment and systems, and investigation and element
technology(3)Management of R&D

April 1,2018 - March
31, 2019

FY2016

3.4 billion JPY(Fixed)Upgrading approach and system for
retrieval of fuel debris and internal structures(1)Technology development related to confinement function(2)Technology development related to collection and removal of dust generated byfuel debris(3)Study of monitoring system for α nuclide-accompanying fuel debris retrieval.
(4)Study of optimization, etc. related to securing safety of work method and system

April 3,2017-March
31, 2019

FY2016

2 billion
JPY (Fixed)

Upgrading of fundamental technologies
for retrieval of fuel debris and internal
structures(1)Technology development related to preventing fuel debris diffusion(2)Element technology development related to the development of retrieval equiment(3)Development of remote maintenance technology for fuel debris retrieval equipment(4)Development of monitoring technology for fuel debris retrieval, etc.

April 3,2017-March
31, 2019

FY2016

3.5 billion JPY(Fixed)Development of sampling technologies for
retrieval of fuel debris and internal structures(1)Study and formation of fuel debris collection and sampling scenario(2)Design and trial production of sampling system and equipment for fuel debris in
the reactor containment vessel(3)Conceptual study of sampling system for fuel debris in the reactor containment
vesselApril 1,
2018-March
31, 2019

FY2016

1.5 billion JPY(Fixed)Development of fundamental technologies
for retrieval of fuel debris and internal
structures(Development of small neutron detectors)(1)Identification and feasibility study of neutron detection technology applicable tofuel debris retrieval, etc. at the Fukushima Daiichi Nuclear Power Station.
(2)Development of neutron detector

April 24,2017-September FY2016
28, 2018

2 billion
JPY (Fixed)

Development of technologies for collection, transfer and storage of fuel debris(1)Investigation and formation of research plan for transfer and storage(2)Study of safety requirement specifications and system related to transfer andstorage of fuel debris canister(3)Development of safety evaluation methods and safety verification(4)Study of fuel debris storage form, etc.

April 1,
2018-March
31, 2019

FY2016

0.6 billion JPY(Less than 50%)

R&D on treatment and disposal of radioactive waste(1)Characterization(2)Study of management before treatment(3)Study of treatment concept and safety evaluation method that suit solid waste(4)Integration of R&D results, etc.

April 1,2017-March
31, 2019

FY2016

2 billion
JPY (Fixed)

Development of investigation technology
inside the reactor pressure vessel(1)Formation of investigation and development plans(2)Establishment of investigation methods(3)Study on supplementary systems for investigation(4)Development of access device and investigation device

April 1,
2018-March 31,
2020

FY2017

1.3 billion JPY(Less than 50%)

Upgrading approach and system for
retrieval of fuel debris and internal structures (Development of criticality control
technologies for fuel debris)(1)Development of technology for sub-criticality measurements and criticality
approach monitoring(2)Development of technology for re-criticality detection(3)Development of technology to protect against criticality(4)Study on optimization of the ensuring of the safety of methods and systems

April 1,
2018-March
31, 2019

FY20170.25 billion JPY(Less than 50%)Development of technologies for water
circulation systems in PCV(1)Organizing technology specifications for upgrading water circulation systems,
study on work plan and establishment of development plan(2)Development/verification of elemental technologies for access and connection in
PCV

April 1,
2018-March
31, 2020

FY2017

0.5 billion JPY(Less than 50%)Development of technologies for water
circulation systems in PCV (full-scale test)(1)Full-scale verification of technologies for access and connection of PCV
developed under the subsidy project of “Development of technologies for water
circulation systems in PCV”

April 1,
2018-March
31, 2020

FY2017

1 billion
JPY (Fixed)

Development of technologies for detailed
investigation inside PCV (on-site demonstration of detailed investigation technologies considering management deposits)(1)Formation of investigation and development plans(2)On-site verification of access and investigation devices and investigation
technology

April 27,2018-March
31, 2020

FY2017

2.6 billion JPY(Fixed)Development of technologies for detailed
investigation inside PCV (on-site demonstration of detailed investigation technologies through X-6 penetration)(1)Formation of investigation and development plans(2)On-site verification of access and investigation devices and investigation
technology

April 27,2018-March
31, 2020

FY2017

4 billion
JPY (Fixed)

R&D on treatment and disposal of radioactive waste (R&D on proceeding process
and analysis methods)(1)Evaluation on feasible technology for treatment of solid radioactive waste(2)Development of technologies for storage and management of solid waste

April 1,
2018-March
31, 2019

FY2017

0.9 billion JPY(Fixed)Needs on-site

R&D isconducted by
IRID.

1F
Decommissioning

TEPCO Holdings

Practical applicationof development●●

Subsidy Project on Decommissioning and Contaminated Water Managementin the FY2016 and the FY2017 Supplementary Budgets

For fuel debris retrieval●

IRID’s R&D Scope
Decommissioning work

List of Government Subsidized R&D Projects Conducted by IRID

Applied research
Universities andbasic research
institutes

Basic research
Fundamental
researchJapan Atomic
Energy Agency
Collaborative Laboratories
for Advanced
Decommissioning Science

Development of common fundamental
technology, organization of fundamental facility,
acquisition of fundamental data

*1 Projects listed in IRID “Project Plan” *2 Subsidy project maximum cost and subsidy rates are cited from the value given in the Solicitation Information.

* The above chart was created based on the NDF Technology Strategy Plan 2018.

06

07

Scope of work

1

P R O G R E S S R E P O R T 2019

R&D for Nuclear Decommissioning

The three-key-R&D in the decommissioning are: “R&D for fueldebris retrieval from spent fuel pool,” “R&D for preparation
for fuel debris retrieval” and “R&D for Treatment and Disposalof Solid Radioactive Waste.” IRID is promoting further R&D basedon the “Fuel Debris Retrieval Policy 2017.”
IRID’s R&D
IRID has been conducting R&D to proceed with the decommissioning of the Fukushima Daiichi Nuclear Power
Station (NPS), according to the Mid-and-Long-Term Roadmap. In order to improve decommissioning strategy, IRID
is studying alternative appropriate approaches, how to reduce risks, while exploring the end state (the mostappropriate final form) through tie-ups with TEPCO and relevant organizations.
Our three-key-R&D for the decommissioning are; “R&D for fuel debris retrieval from spent fuel pool,” “R&D for
preparation of fuel debris retrieval” and “R&D for Treatment and Disposal of Solid Radioactive Waste.”

Overview of the Reactor Building and R&D Conducted by IRID

(Reference)

Fuel debris*1

CLOSE UP

Policy of Fuel Debris Retrieval and Current Approach

Based on feasibility evaluation and proposals of fuel debris retrieval
methods that were studied in the NDF Strategy Plan, IRID is promoting
future activities in the following fuel debris retrieval policy.

1 Step-by-step approach

Fuel debris will be retrieved by starting with a small portion and then gradually expanding with a review of the work.

2 Optimization of overall decommissioning work

From the preparation work through to retrieval, treatment storage and clearing up, a comprehensive plan aiming at overall
optimization is being studied.

3 Combination of multiple methods

The study is executed assuming the side-access method for the bottom of the PCV andtop-access method for the inside of the RPV.

4 Focusing on the partial submersion method

Reactor building
Spent Fuel pool*2
Fuel debris retrieved from Three Mile Island Nuclear Power
Station Unit 2 (TMI-2) in the USA. (Photo provided by theJapan Atomic Energy Agency (JAEA))

Reactor Pressure Vessel*3（RPV）

R&D for Fuel Removalfrom Spent Fuel PoolR&D for Preparationof Fuel Debris Retrieval
Drywell (D/W)*5

R&D for Treatment andDisposal of Solid
Radioactive Waste

Vent pipe*7

Considering the difficulty of stopping water leakage and the exposure dose at work,
the partial submersion method is focused on because the submersion method is difficult at present.

5 Proceeding forward with the side-access method,which is horizontal access to the bottom of the PCV
The fuel debris exists both at the bottom of the PCV and the inside of the RPV of each unit.
The side-access method the bottom of the PCV is prioritized to minimize the increase of risk accompanied with the retrieval
in consideration of the following.
[1] Accessibility to the bottom of the PCV would be the best and knowledge was obtained from investigating inside the PCV,
[2] There is a possibility to execute it earlier, and [3] It can be processed in parallel with spent fuel removal.

Current approach based on the policy for fuel debris retrieval
Top access method –Image of debris retrieval–Suppression Chamber (S/C)*6
Torus room*8

Primary Containment Vessel (PCV)*4*1 Fuel debris: Lava-like fuel containing material that is produced underhigh temperatures through melting with control rods and structuresinside the RPV, after which it cools and re-solidifies.

*2 Spent fuel pool: A water tank that stores spent fuel that is inserted intoa rack under water until decay heat generated from fission products
decreases. This tank is located on the top floor of the reactor building.

*5*6*3 Reactor Pressure Vessel (RPV): A cylindrical steel container thathouses fuel assemblies. This container can resist high-temperaturewater and high-pressure steam generated by the energy released by
nuclear fission inside. The RPV is housed within the PCV together withcooling equipment.

*4 Primary Containment Vessel (PCV): A steel container that houses theRPV, cooling equipment, and other devices that perform importantfunctions. This prevents radioactive substances from being released
into the outside environment under abnormal plant conditions, such as
when a reactor accident occurs, or in the event of a breakdown ofcooling equipment. It should be noted that each of the PCVs installed in
Units 1-3 at the Fukushima Daiichi NPS consists of a flask-shaped
drywell, a doughnut-shaped suppression chamber and eight vent pipes
connecting the drywell and the suppression chamber.

Drywell (D/W): A safety structure that is comprised of a flask-shaped
container that houses equipment, including the RPV, and contains
radioactive substances at the time of an accident.
Suppression chamber (S/C): Doughnut-shaped equipment that storeswater located in the basement of the reactor building. Condenses vapor
generated in the case of reactor piping breakage and prevents excesspressure from building up. It also serves the important function ofproviding a water source for the Emergency Core Cooling System(ECCS) in the case of a loss-of-coolant accident.

*7

Vent pipe: Connecting piping that takes vapor generated within theD/W to the S/C in case of a reactor pipe breakage. Eight vent pipes are
installed in the PCV of Units 1-3 at the Fukushima Daiichi NPS.

*8

Torus room: A room containing the torus-shaped (doughnut-shaped)
S/C located in the basement of the reactor building.

*The submersion method may bestudied in the future, considering theadvantage of shielding effects.

Continuous investigation of the inside PCV,
and acceleration of focused R&D

Side access method: Access rail method – Image of debris retrieval –● Debris “in” the pedestal ⇒ Insert the access rail from X-6

penetration into the pedestal and retrieve by using a robot arm.

Cover

●Debris “outside” of the pedestal ⇒ Retrieve by using a robot arm

through the equipment hatch.

Image of unit 2 and 3*
Shielding Port with openable

Accessdevice in RPV(Image)Film for prevention of dust scattering
Up/Down

Opening

Access device
Rotating mechanism

Lower device sealing

PCV
Pedestal opening for
CRD replacement
Cell adapter

Fuel debris

Robot arm
(For debris outside in thepedestal)

Cell forair tightness
X-6
penetration

RPV inner
surface seal
Processing
device/work arm

RPV

Cell for air
tightness

Manipulator

Equipment hatch

Access rail
Pedestal

Robot arm
(For debris in the pedestal)

Fuel debris

Note) Those in the red frames are new equipment. *Position of X-6 penetration of unit 1 is different from those of unit 2&3.

*Scan the text or photos marked with08

by COCOAR2.

09

Scope of work

P R O G R E S S R E P O R T 20191

Overview of IRID’s R&D Projects

R&D&D for Nuclear Decommissioning

R&D for fuel debris retrieval including the developmentof investigation robots of inside the reactor andretrieval technology are being promoted according to theMid-and-Long-Term Roadmap.

Technology for Treatment andDisposal of Solid Waste
90Sr activity concentration (Bq/g)

1 …R&D for Fuel Removal from the Spent Fuel Pool3

3 …R&D for Treatment and Disposal of Solid Radioactive Waste

Absorbervessel

2 …R&D for Fuel Debris Retrieval

Saltwater tankfor Fuel Removal from
1 ⓐ R&D
Spent Fuel Pool
Evaluation of Long-term Integrity of Fuel Assembly○ Technology for

Spent fuelpool●

Support cart

Basic Tests for Long-term Integrity

10-1

10-2

White blank sections are the lowest
levels of the lower detection limit
102

104

DebrisRetrieval storage cellⓑ

Reactor Pressure
Vessel（RPV)Side hole drillinginvestigation
methodUpper grid plate

Reactorcore

An image of high density
substance thought to befuel debris is confirmedon the bottom of the RPV.
*Measurements at unit
2 and 3 were made by
TEPCO Holding as apart of IRID activities.

ShroudCleaning ofcanister

Formulation of safety scenario for large earthquake
Development of seismic resistance /impact assessment method for formulating safety scenario● Safety scenario upgrading●

monitoring

Primary Containment
Vessel (PCV)① Prevention of・Monitoring of criticality approach(Adjacent to retrieval work area)

criticalityⓖ

B4C sintered Glass material
metal material with B-Gd

24

Torus room

22
20

Vent pipe

Neutrondetector① Approach in improved reliable

Suppression Chamber (S/C)

Gd2O3
particles

DSP

Well
-6

-4

-2

0

2

4

6

problem analysis in estimating a better
understanding of the phenomenon.

Probability
densityⓕ

Characterization using simulated debris

ZrO2 cylinder

Ф25cm

High frequency
induction heating
coil

Simulatedfuel material, etc.
UO2＋ZrO2＋Zr＋Stainless steel

y
ＣＲＤ

0.3

y

ar
PCV water levelX- 6penetration.

CRD rail

ＰＣＶ

Platform

0.3

0.3
0.5
0.6

0.6
1500
mm

Opening ofPedestal

50cm

ar[Sv/h-γ]

PCV Wall

350
mm

1.0

0.7

1.4
1.4
1.1
1.0
)

X-6 penetration flange(After steel plate removal)
290mm
約50mm

600
mm

0.8

7.2
8.0

0.7

ua
ll
re y colat m
ion ple
sh me
ip nt

t
en
m
ple hip
om onsy c ati
all reltu

Mu

Severe accident

Reactorcore damage

RCIC water
SRV opening(success/failure) injection
Scram(success) DC power
RPV integrity RCIC water
source(success)(maintaining/ injection (loss)(loss) AC powersource (loss)
damage)Accident progression time

ＲＰＶ

1.2

>10 >10Groove after
9.4 8.0 block
removal2ⓔ Fuel Debris Characterization③Approach based on information obtained from on-site investigations andMut

Probability
density

SeverityHigh temperature over 200℃
Repetitive elevating/lowering
Lowering below the saturated
temperature by injecting through the CS

1000
mm 300mm
350mm

impact・Prompt termination incase of criticality

Technology for Retrieval of Fuel Debris andReactor Internals

16

14

Identifying conditions inside the reactor

estimation from the results of the investigations.

④ Mitigation of18② Approach taken by data analysis and inverse

Mutually complementary relationshipanalysis code evaluation andaccident progression scenario analysis

Emergency injectionof boric acid solution

Soluble neutron absorbent (boric acid solution)
Non-soluble neutron absorbent

ⓔ ⓖ

26

・Early detection of criticality
signs (the entire PCV)

Injecting neutron absorbersⓒⓓ＊Size of one pixel: Equivalent to approx.
25 cm at the cross section of the nuclear reactor

detection

Gas monitoring
systemManagement of procedure
to prevent criticality

Technology for Investigation and Analysis (Characterization) inside the Reactor
Estimate conditions inside the reactor based on three approaches

Carry out oftransport cask●

ReactorPressure Vessel(RPV)Work floor

SFP lid
Robot arm

Scale model test facility

2

Storage of canisterin transport cask

② Criticality approachⓓTechnology for Detection of Fuel Debris
Height OP（ｍ）

Steam separator

Storage incanisterDevelopment of Technology for Criticality Control ofFuel Debris③ Criticality

Muon detector

Investigative technology
for the fuel debris distribution
inside the RPV in Unit
2 utilizing cosmic ray muons

Storage canister
Handling cell

Storagefacility

Fuel debris
retrieval

Development of investigation robots inside the PCVSteam drier

Building forcarrying out debris

Carry out cell

Development of Seismic-resistance and Impact Assessment
Method for RPV / PCVⓒTechnology for Investigation inside the PCV

Reactor building(R/B)(Buffering structure)

Idea with basic plan of storage canister

Maintenance Carry out/in(Added)cell

Ratio of 90Sr/137Cs in rubble

Relay cart

Top hole drillinginvestigation method

Primary
Containment
Vessel（PCV)(Unit canister)

Reactor building

106

Technology for Investigation inside the Reactor
Evaluation for feasibility of two methods(Conceptual view of investigation method)

State of unit
canister stored

10-4

Shield plug

Transport cartⓑ Technology for Investigation inside the RPV

Mesh(Side and bottom)

101

137Cs activity concentration (Bq/g)

Pressure filtering test
device to examine
dehydration treatment of
ALPS slurryⓐ2

Unit 3(Lid structure)
Inner diameter:
several 10cm
Height:Approx.2 m

Operating floor

Work cart

Remotely-operated
Decontamination in
the Reactor Building

Evaluation of Surface Depositsof the Fuel Assembly and Evaluation of
Fuel Integrity in Dry Storage

Unit 2

10-3

for Decontamination and2 Technology
Dose reduction●103ⓖ Technology for Fuel Debris Retrieval

Technology for Collection,
Transfer and Storage ofFuel Debris

Unit 1100

Full-scale absorber
vessel to be used forvarious absorption tests

2

Concrete test
body
Ф50cm
Large MCCI test device in cooperation with CEA

A simulation test of the Molten
Core Concrete Interaction (MCCI)
was conducted.
A MCCI test that used a molten
core with several kilograms of uranium and concrete was conducted incooperation with a research
institute in France.

ⓕ Technology for Repair and Water Stoppage of the PCV

Preparation for Full-scale
Mock-up Tests

Workability verification test for reinforcement of S/C support columns

・Verification of workability of installation and collection of the placing hose with the device on the work floor・Verification of construction procedures through water flow and remote monitoring performance.
Work floor (The first floorof the reactor building is assumed.)
Appearance oftest facility

Implementation ofreinforcing workability
verification test for
S/C support columns

Placing device
Simulated interference
objectives(two-stager grating)
Simulated suppression chamber

Placing hoseSimulated torus room

Red：surface of the flange
Blue：roof, wall
Green：Floor and melted stuff

Unit 5*Scan the text or photos marked with10

by COCOAR2.

11

Scope of work

1

P R O G R E S S R E P O R T 2019

Major R&D Topics

R&D for Nuclear Decommissioning

In 2018, IRID achieved R&D results from investigating
the inside of the reactor of unit 2 and development of
repair technology for the leaking parts. R&D forfuel debris retrieval is also being processed.

Repair Technology for Leakage Points Inside the Primary Containment Vessel (PCV)■ Technology for stopping water flow by filling in vent pipes

This technology is being developed as a water stoppage material using self-compacting concrete and repair material using sludge water, and which isintended to ensure water stoppage capabilities.
Welding device

Technology for Detailed Investigation of inside the Primary Containment
Vessel (PCV)

Guide pipe
Bentonite sludge water■ Development of investigative device

Repair material

Development of submersible type ROV

Unit 1 (Remotely Operated Vehicle) that can move around

Development of arm type access device

Unit 2a wider range of the basement floor

3

12.

Carriage
溶接部清掃装置

en

ext

m(

5.4

)
ded

ex
m(

)

ded

ten

Submersible ROV

Boom-link

Telescopic arm

Tilt-mechanism

Rubber material
injection port

500Ax2000mmx2
Steel pipe tilt angle:
20 degree

Self-compacting
concrete

Wand *

4.3m

Diameter: Approx. 25cm
Length: Approx.100cm

115mm x 95mmx750mm
Particle size of aggregate
Minimum 7mm

The tip of the arm is equipped with a sensor.
*Can alternatively be equipped with tools.

Rubber material pressure test

Unit 1

水・ガイドパイプシール装置

コーティング装置

・溶接部清掃装置

Concrete water stoppage test

【手順１６】２〜４パスの溶接・磨き・清掃
手順１３〜１５を繰り返し行い、２層４パスの溶接を行う。

【手順１７】溶接部の耐圧・漏えい確認【手順１８】溶接部のコーティング
ガイドパイプ内に水を充填し、フランジにて閉止する。その後、耐圧・漏えい確
コーティング装置をインストレーションカートのホイストにかけて、認を行う。耐圧漏えい確認終了後、ガイドパイプ内の水は、ポンプ等で回収、
コーティング装置の先端を所定の位置まで降下させる。その後、スタもしくはトーラス室内に排水する。
作動させて、コーティング装置を固定する。装置固定後、溶接部のコグを行う。コーティング後は装置を引上げ撤去する。

Unit 2Development of an abrasive water jet device designed to perforate thegrating and internal door and isolate the PCVDevelopment of technology for connecting the access device
used to open the hatch of X-6 penetration that can be remotely
operated and isolated inside the PCV

In PCVA new boundary part(extension pipe,
isolation valve)

Perforating internal doorck
Air lo tion)aenetr(X-2 pR&D for Fuel Debris retrieval
Specific R&D is being processed toward determination of the retrieval method for the initial unit (FY 2019) and starting the retrieval (during 2021).
Fundamental technology
development

Fundamental technology for the retrieval method is confirmed by an element test (smaller-scale model and full-scale model).
ペデスタル内アクセス技術(例)
Technology for accessingアクセスレール・ロボットアーム
inside the pedestal
Technology for accessing inside(example) Dual-arm muscular
robot
the
pedestal(example) Access rail/robot arm
PCV模擬体（開口無し）

Technology for preventing spread ofcontamination (example)
Equipment cell

Perforating the 1st ﬂoor grating

Abrasive water jet device

Rail

A new boundary part of X-2 penetration and perforating the grating

Equipment
transportation cart

Access structure in front of X-6 penetration

BSW

気密・遮へい扉模擬体

Sealing/shielding door

Dual-arm
muscular (例)
robot
BSW

Grasping
process

BSW模擬体PCV

気密・遮へい扉①Insert a guide pipe ⇒ ②Extend an extension pipe ⇒ ③Suspend a pan-tilt camera ⇒ ④Investigate

気密・遮へい扉模擬体

PCV模擬体（開口無し）

Hydraulicrobot arm
液圧式ロボットアーム

Access rail

アクセスレール

Pedestal opening
Blade

Parts of the fuel assemblies that were
found at the bottom of the pedestal (top of tie plate)Confirming the conditions
below the platform
Operation part for
Isolation valve
bending the tip

機器セル
機器搬送台車■ Investigation procedure

in Unit 2

液圧式ロボットアーム

アクセスレール

PCV

Investigation Technology inside Primary Containment Vessel (PCV)■ Investigation inside PCV

ペデス

BSW模擬体

Isolation part
Transport cart

PCV
Guide pipe

Parts of fuel assemblies①（ Φ110mm ）Pedestal

試験架台②

Manipulator
Platform

Alternative shielding
Cable
Cable feedmechanism
Bird’s eye camera
Dosimeter/thermometer③

Overview of the device
with camera at the tip

Grasping
試験架台 搬送用プレート
process
Test rack
インフレートシール
マニピュレータ
搬送用プレート

Top tie plate

Extension pipe

PCV penetration part(X-6 penetration)

12

閉止フランジポンプ

Figure: Overview of repairing lower part of PCV (filling in vent pipes and S/C guide pipe implementation)■ Development of establishing access routes into PCV

Cable drum

溶接部清掃装置【手順１３】溶接前の清掃【手順１４】ガイドパイプの溶接【手順１５】溶接部の清掃
溶接部清掃装置をインストレーションカートのホイストにかけて、遠隔操作にてガイドパイプシール装置をインストレーションカートのホイストにかけて、遠隔操溶接部清掃装置をインストレーションカートのホイストにかけて、遠溶接部清掃装置の先端部が所定の位置になるまで下降させる。その後、スタ作にてガイドパイプシール装置の先端部が所定の位置になるまで下降させる。
溶接部清掃装置の先端部が所定の位置になるまで下降させる。その後ビライザを作動させて、ブラシの軌道を確認した後、溶接前の溶接対象範囲
その後、スタビライザを作動させて、トーチの軌道を確認した後、溶接を行う。
ビライザを作動させて、ブラシの軌道を確認した後、溶接部の清掃作の清掃作業(磨き及び吸引)を行う。清掃作業終了後は装置を引上げ撤去
溶接作業終了後は装置を引上げ撤去する。
及び吸引)を行う。清掃作業終了後は装置を引上げ撤去する。
する。

Vent pipe 1/1 scale test

2-axis joint

ガイドパイプシール装置

Pan tilt camera・External light

Transport plate※：実機装置は、組合せ試験結果を およ び今後の設計進捗に伴い変更となる可能あり。

Location of the inscriptions

The inscription on the top tie
plate found at the bottom of thepedestal was examined in order
to identify the charging location of
the fuel assemblies from which itcame.

マニピュレータ

Inflatable seal

実機 装置構成※

Control rod
drive mechanism

マニピュレータ

搬送用プレート

PCV
内圧

Starting from the left the following four letters could be read:[F], [2], [X], and [N]. However, since the serial number, whichstarts with the fifth letter in this series could not be seen, wewere unable to identify the charging location of the fuelassemblies from which this top tie plate originated.

イ ンフレートシール

BSW模擬体- 100Pa(g)

間隙
44mm
PCV/RSW〜300Pa(g)（正圧）45 漏えい量（〜500Pa(g)m3/h）

PCV模擬体PCV模擬体45 漏えい量（m3/h）
3530

いじわる試験

（正圧）〜300Pa(g)

35

30

55mm

20

0MPa（内圧喪失）

55mm−

通常時インリークの上限目標）（40m3/h

シール内圧0MPa（内圧喪失）

10
5

空間圧力
加圧ラ イン

〜500Pa(g)

25 −
15

シール内圧
加圧ラ イン

継ぎ目段差2mm

40 0MPa（内圧喪失）

44〜50mm（公差）
溶接余盛3mm
流量計
継ぎ目段差2mm

インフレー トシール

40
BSW模擬体0〜0.1MPa−
板材のつなぎ目

Simulated BSW structure

試験条件- 100Pa(g)PCV内圧

0〜0.1MPa
0.08MPa
シール内圧
試験条件
Dual-arm（公差）
44〜50mm
44mm
Pedestal
openingPCV/RSW間隙いじわる試験
muscular
robot
組合せ試験
機器構成
仕様値
変動値
溶接余盛3mm
板材のつなぎ目 −BSW模擬体Inflatable seal

インフレートシール

機器構成
変動値
組合せ試験
仕様値

実機 装置構成※

試験結果を およ び今後の設計進捗に伴い変更となる可能あり。
※：実機装置は、組合せ

シール内圧 0.08MPa
Overview of parts of fuelassemblies (top tie plate)

インフレートシール

シール内圧0.04MPa

通常時インリークの上限目標
0（40m3/h
） 0
200
100

（通常）
シール内圧0.08MPa

300

400

Pa）
シール両側差圧（

シール両側差圧に対する漏えい量（グリース無し）

13

Scope of work

1

Scope of work

R&D for Nuclear Decommissioning

CLOSE UP

Human Resources Development in R&D

Nuclear decommissioning is a long-term project that can take 30 to 40
years. It is therefore essential that we have young people involvedin nuclear decommissioning activities. IRID is committed topromoting the development of next generation workers that will
be involved in nuclear decommissioning R&D.

R&D Collaboration with Universities (Actual Projects)■ Development of Criticality Control Technology [Misawa Laboratory, Kyoto University]
Aiming at verification of critical approach monitoring technology for detecting any sign of criticality approaching andthe nuclear characteristics of neutron absorbent material in preventing criticality from occurring , a feasibility
verification test was conducted using the Kyoto University Critical Assembly (KUCA) in collaboration with professor
Misawa, the Institute for Integrated Radiation and Nuclear Science, Kyoto University, which owns the KUCA. It can beused with variable amounts of fuel moderator according to the purpose of the test; therefore making it an appropriate
experimental system for use in simulating various fuel debris conditions, and which can acquire large amounts ofuseful data that can then be used to verify the criticality control technology being developed by IRID.

1. PR Activities at Universities and Research Institutes

IRID is actively involved in the development of human resources by providing information through visits to universities andresearch institutes.

Fuel assembly cell

Reflector cell

Control rod cell

Lecture at Kindai University

Neutron detector

MCNP Deb02 det-1 debris noise (Feynman-

25

)

Det-1

15

10

5

0

Image of neutron signals

0

Lecture at the National Institute of Technology,
Fukushima College

The IRID Symposium 2018 was held entitled “Challenges with Fuel Debris Retrieval Ⅱ,” and with the purpose of reportingR&D achievements as well as nurturing young researchers and engineers engaging in the decommissioning work, andwhich is a follow through from the previous year’s symposium. It was the first time that the students gave a presentation on
the research results of FY2018. In addition, on the following day of the symposium, a site tour of the Fukushima Daiichi
NPS and the JAEA Naraha Remote Technology Development Center took place for students from universities, graduate
students, and students from the National Institute of Technology who gave presentations and exhibited panels at the
symposium.

20

B-10 neutron detector

Lecture at the Kanagawa Institute of Industrial
Science and Technology (KISTEC) Educational Seminar

2. IRID Symposium

Example of test reactor core

KUCA solid moderated core2

P R O G R E S S R E P O R T 2018

5

10

15
Time(sec)

20

25

30

Development of Operational Plan that takes into Consideration Interference■ Avoidance via Use of Multi Flexible Robots【Yokokohji/Tasaki Laboratory, Kobe University]
Multi flexible robots (ex. access rail + robot arm or electric manipulator Necessary operational track
block①→block②→block③+ welded head etc.) can be used to increase the range of operations in
Cell adapter
narrow places; however, there are some places where it is difficult for
PCV
wall
operators to access them because accurate positioning is required.
X-6
For this reason, an automatic planning method that is capable ofpenetration
determining a continuous track while avoiding any surrounding
interference was developed in a way that the operator can instruct thenecessary positions at every key point of continuous operational tracks(block①→block②→block③), and assuming that the multi flexible
robot will be used in detailed operations in narrow places.
No solutions available.
No instructions
for posturing
through blocks.

[Solution] An operator instructs posturing at key points.
Instruction for posturing
through block①.

Instruction for posturing Instruction for posturing
through block②.
through block③
Welding head

Posturing on-sitethrough trial and error
Posturing is hard work.

Presentation at the Symposium

Opening remark

Site tour with students

3. Participation in Various Events

IRID actively participates in lectures and events held by various organizations, including academic meetings.

A track without any
interference is available.
Auto-tracking
plan→Simplified
on-site trackcorrection work

Manipulator

Presentation at 2018 Fall Meeting,
the Atomic Energy Society of Japan(September, 2018)14

Panel exhibition at the Environmental
Radioactivity Measures & Radioactive Waste
Disposal International Exhibition(RADIEX) 2018 (October, 2018)

Panel exhibition at the Robot/Aerospace FESTA Fukushima 2018 (November, 2018)15

Scope of work

3

P R O G R E S S R E P O R T 2019

R&D with Overseas Organizations

IRID is enhancing relationships with international research
institutes and experts based on an “open structure”
management policy, as well as the dissemination of
information, including R&D achievements.

CLOSE UP

Global information dissemination
IRID has introduced the achievements of research and development at forums organized byinternational organizations.

Enhancement of Cooperation with International Organizations

Acceleration of R&D with overseas organizations and implementation of
the latest technology for the nuclear decommissioning

OECD/NEA SAREF/PreADES Project Meeting (January, 2018)
Reporting current status of R&D for the decommissioning of the
Fukushima Daiichi NPS

Poland JICC Warsaw Seminar (May, 2018)
Reporting status of investigation inside the PCV of the Fukushima
Daiichi NPS and R&D for the decommissioning

Nuclear Air Cleaning 35th Charleston SC (June, 2018)
Reporting current status of R&D for the decommissioning of the
Fukushima Daiichi NPSICMST-Tohoku 2018 (October, 2018)
Reporting "Overview of IRID R&D Projects“ as the current status of IRID R&D

Joint Research with
Overseas Research Institutions
Glass, Orange color phase■ French Atomic Energy and Alternative

Concrete boundary layer

Before disassembly (Afterremoval of the upper cylinder)

Energies Commission (CEA)

Metal grain

A simulation test of the Molten Core ConcreteInteraction (MCCI) took place as international
cooperative research with the CEA. The results wereused to identify the characteristics of the productsuch as the porous regions, and separated layerswith metal and oxide layers.
Metal layer on the bottom

Conditions of the product

Molten materials
interacted with concrete

Technical Cooperation with Overseas Nuclear Organizations■ Hanford Facility (U.S.A.)■ Argonne National Laboratory (ANL) (U.S.A.)

Dust, including radioactive material, will
be generated by the fuel debris during
the retrieval process. It is therefore
necessary to study ventilation systems
that can be used to contain any dust
generated within the RPV and reactor
building. IRID visited the researchfacility in the U.S.A., which has related
systems, and discussed with engineers
reflecting them in the system design.

ANL has experienced various
demonstration tests ofinteractions between debris andconcrete (MCCI) in severe
accidents with the DOE (UnitedStates Department of Energy).
Through technical discussions
with researchers that haveknowledge at the world’s top level, IRID obtained useful information
for future debris retrieval methods and processing technology.

R&D Activities with Overseas Organizations (List of major items)○UK /Sellafield Ltd. : Handling of damaged fuel, safe storage and criticality control.
○France/Atomic Energy and Alternative Energies Commission (CEA) : MCCI test
○Hungary/Paks Nuclear Power Plant :Handling of damaged fuel and safe storage

International Advisors○Kazakhstan/

National Nuclear Research Center (NNC):
Debris characterization test

The International Advisor committee consists of three nuclear experts fromabroad. This advisory committee was established with the purpose of advising
the IRID Board of Directors on organizational operation and management.
International Advisors provide advice on future challenges and required
improvements as well as leading discussions on international efforts andmanagement approaches.

○U.S.A.
・Pacific Northwest National Laboratory : Handling and safe storage of damaged fuel・Hanford Facility : Handling and safe storage of damaged fuel, study of ventilation system for debris dust・Idaho National Laboratory : Information collection of knowledge about TMI - II

■ Members * From left of the photo○Professor Melanie Brownridge (UK)
Head of Technology,
Nuclear Decommissioning Authority (NDA)16○Austria/IAEA : Technical information collection○Mr. Luis E. Echavarri (Spain)

Former Director General of the OECD/NEA(Experienced in the International Nuclear Safety
Group (INSAG))○Mr. Lake Barrett (USA)

Independent Consultant (former Site Director for the
Nuclear Regulatory Commission (NRC) for theThree Mile Island accident)

・Argonne National Laboratory : Exchange of debris characterization information
・Los Alamos National Laboratory : Development of debris detection technology
・University of California, Berkeley : R&D for treatment and disposal of solid waste
・Mississippi State University : Study of ventilation system for debris dust

17

International Research Institute for
Nuclear Decommissioning

5F, 3 Toyokaiji Building, 2-23-1 Nishi-Shimbashi,
Minato-ku, Tokyo 105-0003, Japan
TEL:+81 3 6435 8601
http://irid.or.jp/en/

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Issued in March, 2019

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