6F Parkplace, 5-27-1 Shimbashi, Minato-ku, Tokyo 105-0004, Japan
Phone : +81-3-6435-8601
http://www.irid.or.jp/en

Published ：September 2014

Message from the President
Over three years have now passed since the March 2011 Tohoku Pacific Ocean

The decommissioning of the Fukushima Daiichi Nuclear Power Station is a projectthat presents numerous technological challenges ‒ challenges
that have never been faced by any other nation in history.

Earthquake and Tsunami and the accompanying accident at the Fukushima Daiichi

It is vital that this project includes technologies outside of the nuclear powerindustry, such as robotics, and that it promotes R&D by bringing together the richknowledge and experience of various institutions based in Japan and overseas.

the minds of those who are enduring hardship and worry at ease as soon as possible, it

Furthermore, collaboration between all concerned institutions is required to foster
the human resources needed to carry on the decommissioning of
the Fukushima Daiichi Nuclear Power Station over the medium to long term.

Nuclear Power Station (NPS) run by the Tokyo Electric Power Company (TEPCO).
However, even now many people from Fukushima Prefecture and surrounding regions arestill forced to live as evacuees, an issue of great concern to wider society. In order to put
is essential that the process of decommissioning the damaged reactors moves forwardsafely and as swiftly as possible.
The International Research Institute for Nuclear Decommissioning (IRID) was establishedin August 2013 as an organization to develop nuclear power plant decommissioning
technologies efficiently based on collective wisdom from Japan and abroad.
In the year since its inception, IRID has identified research and development into thetechnologies required for the decommissioning of the Fukushima Daiichi NPS as a matterof urgency. These include R&D of technologies to safely retrieve nuclear fuel from thecores of the reactors and those related to the treatment/disposal of radioactive waste

IRID is engaged in the integrated managementof decommissioning technologies to address these needs.

generated by the accident.
In August 2014, the decommissioning of the damaged reactors was added as a
responsibility of the Nuclear Damage Liability Facilitation Fund. With this came thereorg aniz ation o f the Fund int o the Nuclear Dama ge C ompensation andDecommissioning Facilitation Corporation (NDF). The Japanese Government is now at theforefront of the decommissioning of the Fukushima Daiichi NPS and in developing
measures to deal with contaminated water, strengthening the framework that supports

CONTENTS

Message from the President

the steady progress of the decommissioning work.
1

Organization ProﬁleProﬁle/Founding of IRID/Organizational Structure
・Technology Advisory Committee

Role of IRID
・Technology Research Associations
・A Short Note : Looking back over the past year
・The Decommissioning Process in the Mid-and-Long-Term Roadmap towards the Decommissioning of
Tepco s Fukushima Daiichi Nuclear Power Station Units1-4
・R&D Using Commission Expenses and Subsidies from the Government

The extremely difficult task, even by global standards, of safely achieving steady progressin the decommissioning of the Fukushima Daiichi NPS requires NDF (technology
strategy/technology-related decisions), TEPCO (on-site operations), and IRID (technical2

development) to collaborate and closely work together as one.

3

IRID is fully aware of the vital role it plays, and will continue working on developing

4
5
5

technologies steadily and with a sense of urgency. We appreciate your kind guidance andcontinued support, and encouragement of our efforts.

6
7

Scope of Business
Nuclear Decommissioning Technolgy R&D
1. R&D for Fuel Removal from Spent Fuel Pool
2. R&D for Preparation of Fuel Debris Retrieval
3. R&D for Treatment and Disposal of Radioactive Waste

8

September 2014

10
11
16

Technology Research Association,
International Research Institute for Nuclear Decommissioning

・Requests for Information (RFIs) from Japan and Around the World

17

Promotion of Cooperation on Nuclear Decommissioning with Internationaland Domestic Organizations
Human Resource Development for R&D

18

Hirofumi Kenda, President
20

1Organization Profile
ProfileFounding of IRID

1. NameTechnology Research Association,
International Research Institute for Nuclear
Decommissioning (IRID)
2. Location of Main Office
6F Parkplace, 5-27-1 Shimbashi, Minato-ku,
Tokyo 105-0004, Japan
website: http://www.irid.or.jp/en
3. Scope of Business● Nuclear decommissioning technology R&D● Promotion of cooperation on nuclear decommissioning
with international and domestic organizations● Human resource development for R&D
4. Membership (18)
Incorporated Administrative Agencies:
Japan Atomic Energy Agency
National Institute of Advanced Industrial Science and Technology
Manufacturers, etc.:
TOSHIBA Corporation
Hitachi-GE Nuclear Energy, Ltd.
Mitsubishi Heavy Industries, Ltd.
ATOX Co., Ltd.
Electric utilities, etc.:
Hokkaido Electirc Power Co., Inc.
Tohoku Electirc Power Co., Inc.
Tokyo Electric Power Company, Incorporated (TEPCO)
Chubu Electric Power Co., Inc.
Hokuriku Electric Power Company
Kansai Electric Power Co., Inc.
The Chugoku Electric Power Co., Inc.
Shikoku Electric Power Company, Incorporated
Kyushu Electric Power Co., INC.
The Japan Atomic Power Company
Electric Power Development Co., Ltd.
Japan Nuclear Fuel Limited
5. Board of Directors
President: Mr. Hirofumi Kenda
Vice President: Dr. Tamio Arai
Executive Director: Mr. Kiichi Suganuma
Directors: Mr. Kiyoshi Oikawa, Mr. Hiroto Uozumi,
Mr. Ei Kadokami, Mr. Masahiro Seto,
Mr. Mamoru Hatazawa, and Mr. Yoshinori Moriyama
Auditor: Mr. Tomomichi Konashi(As of August 19, 2014)

2

In July 2011, four months after the accident at the Fukushima
Daiichi Nuclear Power Station (NPS), the first mid-and-long term
countermeasure proposal was released. Experts at the time
expressed the view that an organization dedicated to thedecommissioning process should be created in Japan; this opinion
was taken to the Japan Atomic Energy Commission.
In response to this, the Council for the Decommissioning of
TEPCO's Fukushima Daiichi Nuclear Power Station announced in
March 2013 that a new organization would be established.
A preparatory organization was then established to deliberate on
the new organization. As a result, an application seeking approval
for the establishment of IRID was sent to the Ministry of Economy,
Trade and Industry at the end of July 2011, and approval obtained
from the Minister on August 1 of the same year. IRID held its
inaugural General Meeting on August 8, establishing itself as anindependent decision-making body.

IRID Organizational Chart

General Meeting＊After the plenary session held in June 2014, responsibility of the IEGʼsadministration is to be taken over by TEPCOʼs Fukushima Daiichi Decontamination
and Decommissioning Engineering Company.

Fuel Debris Technical
Assessment Team＊Technology Advisory
Committee

R&D Management Department

R&D Strategy Planning Department

Administration Department

Research Project & Information
Management Team

Development Planning Oﬃce

Administration & Human Resource
Management TeamTechnical Strategic Planning TeamInternational Cooperation Team

General Management Team

Corporate Communications TeamPCV Investigation andRepair Technology GroupAccounting & Procurement Team

Human Resource Development &Academia Cooperation Team

Organizational Structure
IRID was established under the Act on Research and Development
Partnership, and is therefore obligated to set up a General Meeting
and a Board of Directors.
The founding 17 members of IRID have been engaged mainly in thedecommissioning process after the accident at the Fukushima Daiichi
NPS. They were joined by a new member, ATOX, in May 2014.
The IRID Board of Directors is comprised of nine directors andone auditor. The Board also includes individuals who are not from
IRID member organizations (universities/companies).
The General Meeting is the decision-making body of IRID, and theorganization’s activities are determined by consensus among the
18 member corporations, while the Board of Directors acts as theexecutive body.
The basic approach of IRID is to proactively incorporate technicaladvice from domestic and international experts. In order to achievethis, an advisory panel comprised of three foreign experts(International Advisors) gives advice on organizational andmanagement aspects directly to the Board of Directors.
In addition, the Technology Advisory Committee and theInternational Expert Group (IEG)* have been set up within theorganizational structure for the purpose of obtaining technicaladvice from experts in order to pursue various R&D activities.
IRID is comprised of three departments that report directly to theBoard of Directors: the R&D Management Department, responsible
for research planning, investigating overseas
technologies/know-how, disseminating information, etc.; the R&D
Strategy Planning Department, responsible for evaluating R&D
results, human resources development, etc.; and theAdministration Department, responsible for the administration of
the organization.
Five groups have been set up under the R&D Management
Department to tackle research-related issues: the PCV Investigation
and Repair Technology Group; the Fuel Debris Retrieval Technology
Group; the Reactor Interior and Fuel Debris Evaluation Technology
Group; the Structural Integrity Assessment Technology Group; andthe Radioactive Waste Treatment and Disposal Technology Group.

International Advisors

Board of Directors

Fuel Debris Retrieval
Technology Group

Reactor Interior andFuel Debris
Evaluation Technology Group

Structural Integrity
Assessment
Technology GroupRadioactive Waste Treatment
and Disposal
Technology Group＊Fuel Debris Technical Assessment Team：Engaged in technological research on alternative methods for fuel debris retrieval. (As of August 19, 2014)

Technology Advisory Committee
The Technology Advisory Committee has
been set up with the objective ofobtaining technical advice from highly
knowledgeable experts in order toformulate plans for R&D projects
undertaken by IRID based on their overall
progress, and to have a flexible approach
towards review of the systems.
Subcommittees have been set up under
the Technology Advisory Committee inorder to obtain views on special matterswith regard to individual R&D projects.

Subcommittee members conducting onsite visit to view robot development (May 16, 2014)3

Role of IRID
IRID is a body made up of 18 corporations engaged
primarily in R&D required for decommissioning the
Fukushima Daiichi NPS. Its long-term objective is to foster,
accumulate, and improve decommissioning and otherrelated technologies for the decommissioning of reactors
throughout Japan.
However, for the present time, our focus is on thedevelopment of technologies required for thedecommissioning of the Fukushima Daiichi NPS withconsignment expenses and subsidies received from thegovernment.
We have tied up with TEPCO’s Fukushima Daiichi
Decontamination and Decommissioning (D&D) Engineering
Company to identify the needs of the Fukushima Daiichi

NPS site, and we are using this information to integratemanagement systems for the development of various
decommissioning technologies.
The integrated management of R&D being carried out by
IRID follows the Mid-and-Long-Term Roadmap towards theDecommissioning of TEPCO's Fukushima Daiichi NPS Units 1-4(Mid-and-Long-Term Roadmap). However, there are also
instances where IRID makes suggestions which are thenincorporated into the Mid-and-Long-Term Roadmap.
Through these activities, IRID aims for positive efforts toensure that the decommissioning of the Fukushima Daiichi
NPS proceeds swiftly, safely, and with due care for theenvironment in order to restore peace of mind to theresidents of Fukushima and the rest of Japan.

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

Overview of the Technology Research Association Model●1. Organizational Change
Company(Association Member)

Handling of
R&D tax expenses

Dues

Role of IRID

Company(Association Member)

Handling of
R&D tax expenses

Dues

IRID is focusing eﬀorts on the most pressing issue, the decommissioning of the Fukushima Daiichi NPS,
with a view to strengthening the foundations of decommissioning technologies.

University, etc.
(Association Member)● Accelerating the decommissioning of the Fukushima Daiichi NPS,

ensuring safety and protecting the environment.
● Early restoration of the Fukushima area and reassuring citizens.

● Preparation for future decommissioning and enhancing

safety levels.
● Fostering, accumulating and improving related technologies.

Contaminated Water and Decommissioning Issues Team

(Chaired by METI Minister, Mr. Toshimitsu Motegi) [Acts as HQ for all projects]

Mid-and-Long-term Roadmap
Presentation/ReportElectric Utilities, Plant Manufacturers, etc.

R&D program
Presentation/Report

Fukushima Daiichi NPS(decommissioning site)

4

Secretariat (R&D management)

R&D Implementation Entities

Integrated management of
decommissioning technology development
Elicitation of on-site needs
Practical application ofdevelopment results
Suggestion of plans
and strategies

Plant Manufacturers, etc.

・Analysis and coordination of on-site technology
Guiding of well-designed
needs and ideas (optimization/matching)development
・Coordination and guidance of respective technology
Guiding of collaboration
development& cooperation
・Adoption of international & domestic advices
・Exploration of potential technology
・Enhancement of human resource development,
and alliances with universities, etc.

Stock company or limited liability company

Legal personality
Technology Research
Association

Research
results

Deferred tax
reserves●2. Incorporation-type Company Split
Set up a stock company or limited liability company
through incorporation-type company split, and start
sequential implementation of research results.

Stock company or limited liability
company established through partition●3. Dissolution

Technology Research Association

The Technology Research Association is dissolved andassociation members bring back their research
results for use.

Technology
Research
Association

Technology Research Association
established through partition●4. Splitting of the Technology Research
Association

Speciﬁc research themes are selected, and the association ispartitioned based on these themes.

Features of a Technology Research Association

International Research Institute for Nuclear Decommissioning (IRID)

Fukushima Daiichi
D&D Engineering
Company

Approvals

Public ResearchInstitution(Association Member)

Feedback to futuredecommissioning projects

Nuclear Damage Compensation and Decommissioning
Facilitation Corporation

TEPCO

Transform organization into stock company orlimited liability company for smooth implementationof research results.

Sharing ofdevelopment results

Japan Atomic Energy Agency●Each of association member provides researchers, funds,
and equipment for joint research. These are jointly
managed and utilized among members.
●Technology Research Associations are joint researchorganizations that have a legal identity independent ofassociation members.
●Transparency and reliability of the management of theassociation is increased through the approval of the
Minister in charge, and by holding regular association
member meetings/board of director meetings.

National Institute of Advanced
Industrial Science and Technology●Those who directly or indirectly use the results of thejoint research (including corporations, individuals,
foreign companies and foreign nationals) can become
association members.
●Universities, research and development incorporated
administrative agencies, technical colleges, local
government organizations or foundations primarily
engaged in testing and research can participate asassociation members. This participation provides
opportunities for cooperation between industry,
academia and government.
(Source) Ministry of Economy, Trade and Industry Website.

Electric Utilities
Other Research Organizations

A Short Note

Advice on technologicaland managerial aspects

Participation in joint studies, R&D, etc.

Advice from domestic/
international organizations

Partner organizations
for joint studies

Looking back over the past year
After the accident at the Fukushima Daiichi NPS, the Ministry of Economy, Trade and Industry and TEPCO havebeen commissioning various projects for developing technologies based on specific requirements to relevant
manufacturers. Through the establishment of IRID, all concerned parties are now able to discuss the same
themes and resolve issues that may lead to inconsistencies or conflicts before they arise.
The process of sharing information, aligning opinions, and engaging in technological consultation initially tooktime. However, as we approach our first anniversary, integrated engineering is now possible, and issues that had
hereto gone unnoticed are being seen. We are now able to approach research and development for thedecommissioning of nuclear reactors through the exploration of better methods.

5The Decommissioning Process in the Mid-and-Long-Term Roadmap towards
the Decommissioning of TEPCO's Fukushima Daiichi Nuclear Power Station Units 1-4
The Mid-and-Long-Term Roadmap towards the Decommissioning of TEPCO's Fukushima Daiichi Nuclear Power Station Units 1-4(hereafter, the Mid-and-Long-Term Roadmap) was finalized in December 2011 by the ‘Government and TEPCO's Mid-to-Long
Term Countermeasure Meeting’ to indicate reasonable and specific processes to recover from the accident at the
Fukushima Daiichi NPS. On June 27, 2013, the Council for the Decommissioning of TEPCO's Fukushima Daiichi NPS(established in February 2013; changed to the Contaminated Water and Decommissioning Issues Team in September 2013)
finalized a revised version of the roadmap. Further revisions will take place based on actual conditions.
The Mid-and-Long-Term Roadmap divides the time until completion of decommissioning into three phases, and sets out theschedule for major tasks to be undertaken onsite and the R&D schedule to the maximum extent possible. Phase 2 started in
November 2013 with the commencement of removal of the spent fuel from Unit 4. Phase 2 sees R&D on the removal offuel debris going ahead in preparation for the actual start of fuel debris retrieval by FY2020.
As of June 2014, we have been unable to directly view the inside of the Primary Containment Vessel (PCV) and Reactor
Pressure Vessel (RPV), but we are able to gauge the condition inside the PCV by measuring its temperature and dose rate.
We have also gradually been able to obtain a partial visual assessment. We are therefore steadily accumulating data whichallows us to examine methods of decommissioning along with various new approaches to handle technical difficulties andissues which hinder the progress of decommissioning R&D efforts.

Mid-and-Long-Term Roadmap and R&D Tasks
Following the completion of Phase 1 of the Mid-and-Long-Term Roadmap,
IRID addresses the following R&D tasks as part of Phase 2.
1. Promotion of long-term R&D in response to the start of fuel removal from the spent fuel pool
2. Development of multifaceted/multilayered methods and equipment for full-scale preparation of fuel debris
retrieval (1) Submersion method
3. Development of multifaceted/multilayered methods and equipment for full-scale preparation of fuel debris
retrieval (2) Alternative methods
4. Stable promotion of R&D in consideration of treatment and disposal of radioactive waste and decommissioning

December 2011

(Completion of Step 2*/
Mid-and-Long-Term Roadmap created)

Eﬀorts to stabilize
plant condition

・Accomplishment ofcold shutdown state・Signiﬁcant reductionof radiation release

November 2013

Phase 1
Period up to thecommencement of fuelremoval from the spent
fuel pool.
(Target: within 2 years fromthe completion of Step 2)

Phase 2

Period up to the commencementof the fuel debris retrieval(Target: within 10 years fromthe completion of Step 2)

2020-

After 30 to 40 years

Phase 3

Period up to the completionof decommissioning measures(Target: within 30-40 years
from the completion of
Step 2)NOW＊Step2：One of the steps in the Fukushima Daiichi NPS stabilization process. The step aims to ensure that the “release of radioactive materials is undercontrol and dose rate is signiﬁcantly reduced.” Reference: Mid-and-Long-Term Roadmap towards the Decommissioning of TEPCO's Fukushima Daiichi
Nuclear Power Station Units 1-4 (June 27, 2013 revised edition)

R&D Using Commission Expenses and Subsidies from the Government
Project for development of the technological foundation for decommissioning and safety of nuclear reactors for power generation for FY2013*1
Subsidy for development of the technological foundation for decommissioning and safety of nuclear reactors for power generation for FY2013*2
1. R&D for Fuel Removal from Spent Fuel Pool
Project type

Title

Remarks（1） Commissioned

Evaluation of long-term integrity of the fuel assembly removed from the spent fuel poolCompleted in March 2014

（2） Commissioned

Study of treatment method of damaged fuel removed from the spent fuel poolCompleted in March 2014

2. R&D for Preparation of Fuel Debris Retrieval
Title

Remarks（1） Subsidized

Development of technology for remotely operated decontamination in reactor buildings

Planned for completion in July 2014（2） Subsidized

Development of technology to identify and repair leakage points in the PCV

Planned for completion in September 2014（3） Subsidized

Development of technology for investigation inside the PCV

Planned for completion in July 2014（4） Subsidized

Development of technology for investigation inside the RPV

Completed in March 2014（5） Subsidized

Development of technology for collecting, transferring and storing fuel debris

Completed in March 2014（6） Subsidized

Development of technology for evaluating integrity of the RPV/PCVCompleted in May 2014（7） Subsidized

Development of technology for controlling fuel debris criticality

Completed in June 2014

（8） Commissioned

Assessing conditions inside reactor through application of severe accident analysis code

Completed in March 2014

（9） Commissioned

Development of technology for identifying properties of and treating fuel debris

Completed in March 2014

Project type

3. R&D for Treatment and Disposal of Radioactive Waste
Project type

Title

Commissioned

Study to examine technologies for the construction of a conceptual framework for treatment and disposal of accident waste

Remarks

Completed in March 2014

4. Others
Project type

Title

Remarks（1） Commissioned

Technical study to examine measures for the treatment of contaminated waterCompleted in December 2013

（2） Commissioned

Technical study to examine alternative methods of fuel debris retrieval

Completed in March 2014

＊1 Commissioned projects: FY2013 Nuclear Power Plant, etc. Decommissioning/Safety＊2 Subsidized projects: FY2013 Nuclear Power Plant, etc. Decommissioning/Safety Technology
Technology Infrastructure Development Works. Projects which the government is in charge
Development Subsidy. Projects which the government is in charge of conducted through thisof conducted through this fund are intended to establish the technical infrastructure that, forfund are intended to develop and demonstrate technologies such as remotely-controlled
example allows for the understanding and analysis of conditions inside reactors in order todevices and equipment in order to contribute to the smooth progression of thecontribute to the smooth progression of the decommissioning of TEPCO's Fukushima Daiichi
decommissioning of TEPCO's Fukushima Daiichi NPS, as well as to improve technical
NPS, as well as to improve technical infrastructure for the decommissioning and safety of
infrastructure for the decommissioning and safety of nuclear facilities.
nuclear facilities.

FY 2013 supplementary budget subsidy for decommissioning and contaminated water management project*3 (adopted on June 30, 2014)
1. R&D for Fuel Removal from Spent Fuel Pool
Project type

Title

Remarks（1） Subsidized

Evaluation of long-term integrity of the fuel assembly removed from the spent fuel pool

Planned for completion in March 2015（2） Subsidized

Study of treatment method of damaged fuel removed from the spent fuel pool

Planned for completion in March 2015

2. R&D for Preparation of Fuel Debris Retrieval
Project type

Title

Remarks（1） Subsidized

Development of repair and water leakage stoppage technology for leakage points inside the PCV

Planned for completion in March 2016（2） Subsidized

Full-scale test for repair and water leakage stoppage technology for leakage points inside the PCV

Planned for completion in March 2016（3） Subsidized

Development of technology for investigation inside the RPV

Planned for completion in March 2015（4） Subsidized

Development of technology for retrieval of fuel debris and in-core structures

Planned for completion in March 2015（5） Subsidized

Development of technology for collecting, transferring and storing fuel debris

Planned for completion in March 2015（6） Subsidized

Development of technology for evaluating integrity of the RPV/PCV

Planned for completion in March 2016（7） Subsidized

Development of technology for detection of fuel debris in the reactor

Planned for completion in March 2015（8） Subsidized

Assessing conditions inside reactor through application of severe accident analysis code

Planned for completion in March 2015（9） Subsidized

Development of technology for identifying properties of and treating fuel debris

Planned for completion in March 2015

3. R&D for Treatment and Disposal of Radioactive Waste
Project type
Subsidized

Title
Development of technology for treatment and disposal of accident waste

Remarks
Planned for completion in March 2015

＊3 Projects conducted through this governmental fund are aimed at improving the level of scientiﬁc technology available in Japan and ensuring smooth progress in the decommissioning andcontaminated water management processes by supporting technical developments that contribute to decommissioning and treatment of contaminated water.

6

7

Scope of Business
Fuel Debris

IRID’s main areas of business are: (1) Nuclear decommissioning technology R&D; (2) Promotion ofcooperation on nuclear decommissioning with international and domestic organizations; and (3) Human
resource development for R&D.

Total loss of all power sources at Units 1-3 of the Fukushima Daiichi NPS disabled the circulation pumps, preventing the flow of water into
the RPVs. Without the necessary water to cool them down, the fuel inside the RPVs overheated, with temperatures thought to have risen
above 2,000 degrees Celsius – high enough to melt the fuel rods themselves.
It is assumed this overheated fuel melted along with control rods and other structural components inside the RPVs. The melted material
solidified again after reaching the bottom of the RPVs, and partially at the bottom of the PCVs. This solidified material is called “fuel debris.”
With radiation levels inside the PCVs being tremendously high even now, workers cannot get near the structures; the shape and location offuel debris can only be estimated using computer simulations. It is absolutely necessary in the decommissioning process to retrieve the fueldebris from inside and store it under a safe and stable condition.

Nuclear Decommissioning Technology R&D
R&D at IRID
IRID conducts R&D for the decommissioning of the Fukushima Daiichi NPS based on the Mid-and-Long-Term Roadmap. The primary focus
of our R&D activity is the upgrading of decommissioning strategies. Together with TEPCO and other related organizations, IRID studies
optimum methods and countermeasures to reduce risk with a view to an optimum end state.
The three main areas of R&D IRID addresses are: Fuel removal from the spent fuel pool; preparation of fuel debris retrieval; and,treatment and disposal of radioactive waste.

Submersion Method for Fuel Debris Retrieval
The fuel debris retrieval project uses the “submersion method,” an approach where fuel debris is fully covered with water. Since water is eﬀective inblocking radiation, the advantage of the submersion method is that it helps reduce unnecessary exposure of workers, and also prevents dust
dispersion during the machining of collected debris.
With the submersion method, as fuel debris are ﬁrst covered with water, water leakage from the PCV wall needs to be stopped. In order to stop thisleakage, the work areas and access routes need to be decontaminated to allow for worker access, and leakage points must be detected.
Robots are being developed to carry out decontamination and inspection of the facility. With the help of these robots, it is possible to determine
contamination levels, take samples from the concrete core, and carry out decontamination from a remote location.
Using the submersion method, the PCV/RPV upper heads and internal structures are ﬁrst removed. An apparatus to retrieve fuel debris is then set
up. For example, a manipulator which can expand and contract could be lowered down, and a special cutting tool at the end of this manipulator
could be used to cut up and retrieve the debris, placing it in special canisters for storage.
Other innovative approaches for fuel debris retrieval including in-air work are also being studied as alternative methods in parallel with thesubmersion method.

(Reference)

Overview of the Reactor Building and R&D by IRID
Fuel debris＊1

Reactor building
Spent fuel pool

Fuel debris retrieved from the Three Mile
Island Unit 2 (TMI-2) in the USA.

＊2

(Photo provided by Japan Atomic Energy Agency (JAEA))

Reactor Pressure Vessel (RPV)＊3

R&D for fuel removal fromspent fuel poolR&D for treatment anddisposal of radioactive waste［Submersion Method］Fuel debris retrieval operation steps＊5

RPV
upper head

Suppression Chamber (S/C)＊6

R&D for preparation offuel debris retrieval

Spentfuel pool

Torus room＊8

Primary Containment Vessel (PCV)＊1 Fuel debris：Material formed by high temperature fuel that has melted together with

control rods and structures inside the RPV which has then cooled and solidiﬁed again.

＊2 Spent fuel pool：A water tank that stores spent fuel that is inserted in a rack until decay

heat generated from ﬁssion products has decreased. This tank is located on the top ﬂoorof the reactor building.

＊3 Reactor Pressure Vessel (RPV)：A cylindrical steel container that houses fuel assemblies.

This container can resist the high-temperature water and high-pressure steam generated
by the energy released by nuclear ﬁssion in the RPV. The RPV is housed within the PCV
facility together with cooling equipment.

＊4 Primary Containment Vessel (PCV)：A steel container that houses the RPV, coolingequipment, and other devices that perform important functions. This preventsradioactive substances from being released into the outside environment underabnormal plant conditions, such as when a reactor accident occurs or in the event of abreakdown of cooling 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 and adoughnut-shaped suppression chamber interconnected by vent pipes.

8

Container
PCV upper head

Overhead crane

Drywell (D/W)＊7
Vent pipe

Spentfuel pool

Fuel debris canisters
Internalstructures
Transfer

Fuel debris
retrievalequipment
Manipulator＊4＊5 Drywell (D/W)：A safety feature that is comprised of a ﬂask-shaped container that houses

equipment, including the RPV, and contains radioactive substances in case of an accident
occurring.

＊6 Suppression Chamber (S/C)：A doughnut-shaped facility that stores water located in thebasement of the reactor building. This facility condenses vapor generated in the case ofreactor piping breakage and prevents excess pressure from building up. It also serves theimportant function of a water source for the Emergency Core Cooling System (ECCS) in thecase of a loss-of-coolant accident.

＊7 Vent pipe：A connecting piping that takes vapor generated within the D/W to the S/C in case ofa reactor pipe break. Eight vent pipes are installed in the PCV of Units 1-3 at the Fukushima
Daiichi NPS.

＊8 Torus room：A room contains a torus-shaped (doughnut-shaped) S/C located in thebasement of the reactor building.

RPV

RPV

Water ﬁlling PCV

PCVTorus room

Water stoppage

Torus room

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

Filling PCV/RPV with water- Opening upper head of RPV

PCVTorus room
Retrieving fuel debris(Reference) Based on Council for the Decommissioning of TEPCO s Fukushima Daiichi NPS documents, June 27, 2013.

9

1

R&D for Fuel Removal from Spent Fuel Pool

Fuel removal from the spent fuel pool in Unit 4 at the Fukushima Daiichi NPS commenced on November 18, 2013. TEPCO
evaluates the integrity of the spent fuel at Unit 4 before transferring it out of the facility.

(1) Evaluation of long-term integrity of the fuel assembly removed fromthe spent fuel poolIntegrity (corrosion resistance, etc.) of the fuel assembly removed from the spent fuel pool and stored in the common pool* for along period is being evaluated by IRID as part of a research project it is engaged in. In future, investigation of actual fuel integrity
and corrosion and strength tests on fuel components will be carried out, which will then be followed by an evaluation of theeffects of this based on actual water quality conditions.
＊Common Pool：A large pool where spent fuel from Units 1-6 at the Fukushima Daiichi NPS is stored.

Evaluation items for long-term integrity of fuel assembly and scope

Structural integrity
・Tie rod bolt joint

R&D for Preparation of Fuel Debris Retrieval(1) Development of technology for remotely operated decontaminationin reactor buildings
Remotely operated decontamination equipment has been developed to respond to contamination conditions at the site andimprove the environment for investigation of leakage in the PCV and undertaking repair works in preparation for fuel debris
retrieval.
IRID will develop decontamination equipment for elevated locations and upper floors to follow on from the decontamination work
performed on lower floors up until now. A comprehensive scheme to reduce radiation exposure to workers through a combinationof decontamination technology and shielding will also be studied.

MHI-MEISTeR Remote control robot[Mitsubishi Heavy Industries]

Status of investigation of fuelin common pool

Handle2This remote-controlled robot was developed by Mitsubishi Heavy Industries in response to the criticality accident at thenuclear fuel processing facility in Tokaimura, Ibaraki Prefecture, in 1999. This robot has been modified and improved forthe purpose of remote operation work at the Fukushima Daiichi NPS.
In 2013, remote operation performance at the Fukushima Daini NPS was assessed and areas for improvement wereidentified. After the improvements were made, demonstration decontamination test*1 by remote operation and concretecore sampling *2 at the Fukushima Daiichi NPS were completed between January and March, 2014.
The robot has two arms with seven joints. The arm ends are equipped with swappable tools that enable the carrying out ofvarious kinds of work, such as concrete wall boring, cutting hand rails and pipes, removal of obstacles, decontamination,and repair work.

Top tie plate
Channel box

Uranium dioxide pellet＊1 Demonstration decontamination tests：Tests to prove the eﬀectiveness of absorption (absorbing
radioactive contaminants using a dedicated nozzle) and blast decontamination (by spraying the blast
material (abrasive material) and scraping a thin layer of the contaminated surface).

Water rod

Cladding airtightness
・Fuel cladding

Fuel cladding

Spacer＊2 Concrete core sampling：Taking a cylindrical concrete sample of approx. 70mm in depth from the wall andﬂoor for the purpose of investigating contamination levels inside the building.

Exterior of the upper part of
the fuel assembly

Tie rod bolt joint

Structural integrity
・Bottom tie plate

Bottom tie plate
BＷR fuel assembly(2) Study of treatment method of damaged fuel removed from the spent
fuel pool
There is a possibility that fuel may have been damaged by the adhesion ofsea salt or suffered physical damage due to rubble impact. Evaluation of theeffect this may have on the reprocessing plant and development of criteria todetermine the possibility of reprocessing damaged fuel will be carried out.

Behavior check for impurities at reprocessing time
Concrete core sampling

Organic phase (solvent)

Impurities (compositions of seawater and concrete)dissolved in nitric acid

Extraction work by shaker

The solution after
the left standing

Water phase

Simulated impurities(mortar)10

Dissolution test equipment

Nitric acid solution ofsimulated impurities(nitric acid solution containing impurities)

In the reprocessing plant, spent fuels are dissolved by nitric acid and uranium and plutonium are
extracted from the nitric acid solution using organic solvent. Major compositions of impurities(composition of seawater and concrete) need to be checked whether they are dissolved by nitricacid along with uranium and plutonium, or if impurities will aﬀect the extraction process ofuranium and plutonium.

Absorption/blast decontamination work

Core cutting (arm tip)11

(2) Development of technology toidentify and repair leakage points
in the PCV
Methods and equipment to investigate and repair leakage(water stoppage) from the PCV, etc., that take eachenvironment, including elevated locations, high radiationdose areas, narrow spaces, and areas under water into
consideration are now under development.
In addition to the establishment of measurement technology
to determine the necessity of repair, construction of a new
boundary for water filling, such as by injecting water
stoppage material (grout*) into the vent pipes that connect
the drywell (D/W) and the suppression chamber (S/C), will be
studied.
The performance of water stoppage technology by grout
injection will be demonstrated by a full-scale unit test to
confirm its applicability.

6

Preliminary test to verify water stoppage
method of injecting water stoppage material(grout) into vent pipe [ Toshiba]

In preparation of implementing the submersion method, deattaching
the S/C from the D/W is being considered since the RPV and the PCV are
required to be ﬁlled with water.
Speciﬁcally, a large inﬂatable sealing bag is placed on the tip of theinner side of the each of eight vent pipes and mortar is injected into thebag to temporarily stop water ﬂow. Water stoppage material (grout) isthen injected into the upstream side from the bag which will then stop
water ﬂow.

5

Support equipment(remotely operated manipulator*) [ Toshiba ]Equipment to transfer and collect the devices in 1 - 3 using a manipulator. In
each unit at the Fukushima Daiichi NPS, holes in eight locations will be drilled
through the ﬁrst ﬂoor of the building. The support equipment will be placed
over each of these holes so that it can deliver and retrieve the devices using an
extendable manipulator into the torus room.

Water stoppage
material
Inﬂatable sealing
bag which contains
material to help
water stoppage

4

Investigation device for the upper
part of the S/C[ Hitachi-GE Nuclear Energy ]This device can perform the following three types ofinvestigations by replacing the upper part of theequipment mounted on the transfer mechanism (carriage)that is ﬁtted with a crawler: (1) Upper part of the S/C (video
recording); (2) Torus room wall surface (video recording);(3) Torus room wall surface using images obtained by sonar(ultrasonic sensor) using Doppler measurement*.
On May 2014, investigation was performed at Unit 1 at the
Fukushima Daiichi NPS, and leakage from the expansion
joint cover for the vacuum break line in the upper part of
the S/C was detected.

＊Grout：Cement-based material injected to ﬁll voids during construction work, etc.

1

Device to inspect joint section between drywelland vent pipe (VT-ROV*) [ Toshiba]
A remotely operated vehicle designed for Units 1-3 at the Fukushima
Daiichi NPS to detect leakage around the joint area between the D/W
and the vent pipes with the assumption of “shell attack” (wheremolten fuel debris has fallen down and spread on the bottom of the
D/W, causing damage to the D/W body), etc.
This robot inspects for leakage using a camera mounted on its front
and adheres to the surface of the vent pipe using wheels magnetizedby a permanent magnet (neodymium).
The height of therobot is 90mm,
making it capableof entering the gap
between the ventpipe and concrete
wall that is as
narrow in places asapprox. 100mm.

＊ROV：Remotely Operated Vehicle.

2＊Manipulator：A general name for working robots that substitute for human manual
operation. Manipulator used in the sense here refers to an expandable arm robot.

Surface of the ﬁrst ﬂoorof the building

Vent pipe

Inspection of the wall surface ofthe torus room
Obtaining Doppler
measurement images by sonar

Drywell (D/W)

Torus room

＊Doppler measurement：Repeated bursts of ultrasonic waves
numbering several hundred in one second to detect smallchanges in reﬂected waves that may be caused by particles in
the water, detecting ﬂow.

Sand cushion
Water level

Sand cushion*1 drain pipe*2
inspection device (DL-ROV) [ Toshiba]This small device that maneuvers underwater is equipped with threethrusters*3 to investigate the sand cushion drain pipe. It is designed
for use in Units 2 and 3 at the Fukushima Daiichi NPS, and will be
used when the drain pipe outlet is submerged.
This device investigatesleakage from the drainpipe by applying tracer *4
just around the drain pipe
outlet and observing its
ﬂow using the camera.

＊1 Sand cushion：Region underneath the exterior of the D/W base ﬁlled withsand to act as a buﬀer to absorb localized stress in the PCV (base part of theD/W) in case of an accident.

＊2 Drain pipe：A pipe that releases water accumulated in the sand cushion
mentioned above.

Inspection of the upper part of
the S/C
Obtaining camera images

Water level

Sand cushion drain pipe

Suppression Chamber
(S/C)

3

Investigation device of the outer lower surface of
the S/C (SC-ROV) [ Toshiba ]This autonomously maneuverable robot mainly investigates the submerged area
to detect holes of 30mm or more in diameter by adhering on the surface of S/Cwith wheels magnetized by a permanent magnet (neodymium).
It is powered by electricity and air as well as receives signals by the cable. This
robot searches damaged portions using the cameras equipped on its front andback, and on its left and right by moving from the inner peripheral side to theouter peripheral side on the S/Couter lower surface.
Also, it is capable of marking theplace which has already been
investigated using a stick-type
marking system to avoid
repetition.
This device can be separated
from the surface of the S/C byjacking up the detachable
mechanism that is ﬁxed on thelower part of this device.

＊3 Thruster：Propulsion system (screw propellers) to move equipment
forwards and backwards, as well as up and down.

＊4 Tracer：Particles to track ﬂuid and gaseous ﬂow. A ﬂuorescent tracer isused for this DL-ROV.

12

13

(3) Development of technology for investigation inside the PCVInvestigation methods and remotely operated
devices are now under development to identify
conditions inside the PCV and determine thesituation regarding fuel debris.
Specifically, devices being developed include
equipment that can use the existing CRD*1 hatch foraccess in order to investigate the lower part of thePCV (inside and outside the pedestal*2).
IRID plans to develop investigation devices that canbe operated within high-dose radiation
environments and guarantee performance in acompact form. The performance of these devices
will be verified through demonstration testing.

Accessing the inside of the PCV(pedestal interior) (artist s impression)Access route① Entering from the CRD
hatch/traversing the top of
the CRD replacement rail
② Entering the inside of thepedestal through pedestal
opening(7) Development of technologies for controlling fuel debris criticality
Reactor Pressure Vessel

Pedestal opening
CRD hatch②①

PCV wall surface＊1 CRD (Control Rod Drive)：A mechanism required for inserting and withdrawing control rods, such as
when starting up and stopping the ﬁssion operation, adjusting the control rod pattern, and during
SCRAM procedures.

CDR replacement rail

Pedestal＊2 Pedestal：A reinforced concrete cylindrical structure that supports the RPV.

＊

Shape-changing robot (crawler type)[Hitachi-GE Nuclear Energy, Ltd.]Moving within pipes

This shape-changing robot (crawler type) can change its shape from asingle line posture when moving through pipes with a diameter of about
100mm, and then open to a rectangular posture when investigating inside
the PCV. This shape changing ability enables the robot to run stably on flat
surfaces and pass through piping with a small diameter.
This robot will be introduced into Unit 1 at the Fukushima Daiichi NPS for
verification testing during the second half of FY 2014. It is planned thatthe robot will enter the PCV from a narrow access port (inner diameter of100mm), and investigate conditions inside the PCV from the top of the
Shape changing
grating (a lattice-shaped metallic object used to cover gutters, etc.) on thefirst floor outside the pedestal.

Moving along ﬂat surfaces＊Crawler：Equipment that enables robots to travel on uneven surfaces by connecting plates
circularly, and rotating them using a drive tumbler.

In addition to subcriticality assessment during the retrieval of fuel debris, IRID is currently developing criticality control
technologies, such as monitoring and recriticality prevention technologies (development of neutron absorption material, etc.).
IRID will develop analysis criteria for rational criticality assessment in response to fuel debris retrieval and collection scenarios, inaddition to collecting the required data for criticality control studies and ensuring that the latest detailed information is reflectedin these studies.

(8) Assessing conditions inside reactor through application of severe
accident analysis code
In addition to conducting accident progression analysis using current severe accident analysis code, we will determine analysis
code items for improvement based on a comparison with actual parameters and the PIRT (Phenomena Identification and Ranking
Table), and aim to advance technologies for accident progression analysis.
In future, we aim to enhance nuclear safety research around the world through collaboration with the Atomic Energy Society ofJapan in establishing the PIRT, and through discussions with experts in Japan and overseas at OECD/NEA (Organization for
Economic Co-operation and Development/Nuclear Energy Agency) workshops, etc.

Status of manufacturing and analysis testof simulated debris(9) Development of technology for
identifying properties of andtreating fuel debris
To ensure safe fuel debris retrieval and in order to develop retrieval
equipment and storage canisters, etc., we will first examine specificmethods using simulated debris. These simulated debris will be
manufactured considering the circumstances of the Fukushima Daiichi
NPS (seawater effects, etc.).
Evaluation will be conducted through a combination of accident
progress analysis and chemical equilibrium computation using theresults of the Three Mile Island Unit 2 (TMI-2) accident and othersevere accident research results as a comparative guide.

Simulated debris is made of uranium dioxide powder and zirconium
dioxide powder, etc. These ingredients are mixed and heated toapprox. 1600℃ - 3000℃ (varies depending on the test and facility)
and shaped into simulated debris. Various types of tests are thenconducted on the simulated debris. Tests are conducted inʻgloveboxʼ, a facility with high sealability equipped with windows
and gloves. Researchers can handle materials that are isolated toprevent exposure and contamination caused by the uranium.

Reaction with Control rod material (B4C＋SUS)(Observation samples of section view of simulated debris)
Fe-Cr-Ni(Fe,Cr,Ni)2B

Fe-Cr-Ni(4) Development of technology for investigation inside the RPVPrior to the retrieval of fuel debris, technologies to identify conditions inside the RPV (temperature, dose rate, degree of damage
to equipment in the reactor, location of fuel debris, etc.) and to sample fuel debris will be developed.

(5) Development of technology for collecting, transferring and storing
fuel debris
The design concept of storage canisters (basic function, outline shape, etc.) will be established with consideration to thecondition of fuel debris ((1) Temperature, (2) Degree of concentration, (3) Period of cooling, and (4) Effect of seawater, etc.).
Additionally, technologies required for collecting, transferring and storing fuel debris will be developed by studying the validity ofstorage canister design using several storage methods from economic and technological perspectives, as well as in considerationof safe storage methods.

(6) Development of technology for evaluating integrity of the RPV/PCVAssuming there has been a corrosive effect caused by the injection of seawater, the integrity of equipment and structures invarious plant conditions is being evaluated in preparation for fuel debris retrieval. IRID is aiming to establish a life extension
scheme, which includes countermeasures for corrosion control, etc., as well as predicting the long-term integrity of structures
based on seismic evaluation of equipment and the structures and on corrosion test results for each material used.

14

ZrB2(beaten or(Fe,Cr,Ni)2(Zr,U)plate-like crystal) (Fe2Zr -type cubic）

Arc melting

Annealing in the oxidizing atmosphere（Ar-0.1%O2,1500℃）(Zr,U)O2(Zr-rich)（Alloy and oxidized ZrB2）

An example of a high temperature reaction test on boron carbide (B4C) the material used in control rods (boron carbide absorbs neutrons
in the reactor and controls the nuclear ﬁssion reaction), stainless (SUS) control rod cladding material, and uranium dioxide (UO2) andzirconium dioxide (ZrO2), the crude materials used in simulated debris.
The creation of a new oxide layer, etc., was observed on the surface of the alloy phase by annealing (heating using comparatively low
temperatures) simulated debris in the oxidizing atmosphere using arc melting (melting using heat generated by discharge).

Microhardness of each phase of the simulated debris

Boride
Oxide
Metal
0

(Fe,Cr,Ni)2B
Vitreous（Si-Fe-Ca-AI-O)
UO（sintering）
2
Fe,Fe-Cr-Ni

Fe-Si-AI-Zr-U5（U0.5Zr0.5)O2（U,Zr)O2(sintering,15-75%U)

If debris were created by a reaction
between the fuel and the control rod,
it suggests the possibility that a boride
layer, which is harder than the metals
and the oxide observed in the TMI-2
accident in the U.S., may have beencreated within the debris.

ZrB2（Zr,Fe,Ca)O2（Zr,U,Ca)O2(Fe,Cr,Ni)2(Zr,U)
10

Vickers hardness (GPa)*

15

20＊Vickers hardness：One measurement of hardness of a material. It is calculated basedon the size of an impression produced under load by a diamond indenter.

15

3

R&D for Treatment and Disposal of Radioactive Waste

Study to examine technologies for the construction of a conceptual
framework for treatment and disposal of accident waste
Radionuclide analysis of rubbles, fallen trees and contaminated water, etc. sampled at the Fukushima Daiichi NPS and inventory
evaluation* of waste materials based on the analysis of these results are now being performed.
In order to acquire the prospect of safe solid waste treatment and disposal, IRID will continue to conduct R&D of technologies
required for storage management, understanding waste characteristics, and waste encapsulation, and for waste disposal.
From FY 2014, IRID will collect and organize information gathered from Japan and abroad related to concepts concerning
securing the safe decommissioning of reactors, and contribute to the examination of decommissioning scenarios.
＊Inventory evaluation：Method to assess the amount of radionuclides contained in radioactive waste, or abundance ratio and correlations based on analysis
results or physical/chemical behavioral characteristics.

[Japan Atomic Energy Agency (JAEA)]■ Requests for Information for Addressing the Contaminated Water Issue

Samples (Standing trees)

Request for Technology Information Workshop (Oct. 2, 2013)■ Requests for Information for Innovative Approaches to Fuel Debris Retrieval

Samples (Standing trees)

γ-ray detection by using germanium semiconductor detector

16

In addition to independently engaging in research and development in decommissioning reactors, IRID has been
actively seeking a wide range of knowledge from Japan and around the world in order to deal with the contaminatedwater issue and contribute to the study of innovative approaches for fuel debris retrieval at the Fukushima Daiichi
NPS.

On September 10, 2013, the 1st Inter-Ministerial Council for Contaminated Water and Decommissioning Issues
discussed policies and concrete actions for addressing contaminated water and decommissioning issues, andconcluded that a team to collect expertise from all over the world and carefully investigate countermeasureproposals would be established.
In response to the RFI on the contaminated water issue, a total of 780 proposals were received from Japan andoverseas. These proposals were then classified according to a specialist team within IRID. After initial review andverification by an Expert Review Panel, the report on the
RFI results was passed to the Committee on
Countermeasures for Contaminated Water Treatment on
November 15.
Following the disbanding of this team in December
2013, Requests for Proposals (RFPs) are now processedby the Mitsubishi Research Institute, Inc.

Radioactivity analysis for standing trees
sampled at the site
(Evaluation of contamination condition
within the site)
Radioactivity analysis of standing trees at the Fukushima Daiichi
NPS was conducted between October 2013 and February 2014 tocollect and evaluate basic data which will be required to verify themethod of radioactive waste treatment and disposal.
To date, in order to determine the extent of radioactive
contamination on the power station site, the site has been divided
into 20 areas based on the distribution of air dose rates, and avariety of environmental samples taken. As it cannot be ruled outthat rubble sampled for analysis may have been moved from its
original location after the accident, using the standing trees foranalysis, we can determine what kind of radionuclide was spread
into which section of the site and better understand thecontamination distribution data.
Specifically speaking, around three pine trees in each area werechosen as ‘representatives, ’ and from these trees, branches at aheight of around four meters were sawn off. Thirty samples (not allareas had these branches) with high dose rates at their surface
were selected and sent to the JAEA Nuclear Science ResearchInstitute to be analyzed.
The findings showed that radiation distribution readings reflected
those of air dose rates, with a similar high concentration ofCesium-137, Strontium-90, and Tritium around the reactor
buildings. From these results, it can be presumed that the primarycause of contamination was radioactive nuclides spread by theaccident.
Looking at overall correlations, it was seen that there was a
proportional relationship between concentrations of Cesium-137
and Strontium-90. The ratios of these nuclides were found to be
the same as those found in soil outside the site, and rubble orfelled trees within the site.

Requests for Information (RFIs) from Japan and Around the WorldIRID put out a call around the world between December 2013 and January 2014 seeking ideas for internationallycollaborative and innovative approaches to fuel debris retrieval. Of the more than 200 responses received, around
40% were from overseas.
In addition to announcing this outcome at a domestic workshop on April 25, 2014, the Agency for Natural
Resources and Energy, TEPCO, and Mitsubishi Research Institute., Inc. in its capacity as secretariat have beendeveloping technical specifications for requests for proposal.
Please note that Mitsubishi Research Institute., Inc. started accepting RFPs from June 27 this year.

Workshop for R&D on Innovative Approaches for Fuel Debris Retrieval (Apr. 25, 2014)17

Promotion of Cooperation on Nuclear Decommissioning
with International and Domestic Organizations■ International Advisors

IRID’s operational policy is to facilitate an open framework that pools the collective wisdom of experts in Japan and overseas. In orderto accomplish this, it is essential that the government (policy), TEPCO (decommissioning operations), and IRID (mid-to-long term R&D)
collaborate with each other in carrying out their respective roles and strengthen relationships with relevant domestic and internationalorganizations and experts.

The International Advisors Panel consists of three nuclear experts from around the world. This group was established with the purposeof providing IRID’s Board of Directors with advice from organizational and management perspectives.
The first meeting was held in January 2014 to deliberate on the international initiatives and management approach of IRID, and offeredadvice to IRID on future issues and points for improvement.

In order to derive the benefit of international wisdom, IRID has established a structure consisting of the International Advisors and theInternational Expert Group (IEG)* to receive advice from experienced foreign experts. We have also made a worldwide RFI for innovativetechnological approaches to treatment of contaminated water and the retrieval of fuel debris. In addition, we are also supporting the
IAEA (International Atomic Energy Agency) Review Mission and participating in joint research projects through the
OECD/NEA.

Members●Mr. Lake Barrett (USA)
Independent Consultant (former Site Director for the Nuclear
Regulatory Commission (NRC) for the Three Mile Island accident)＊After the general meeting in June 2014, administrative responsibility was taken over by the TEPCO Fukushima Daiichi D&D Engineering Company.

●Dr. Adrian Simper (UK)
Director for Strategy and Technology at the Nuclear
Decommissioning Authority (NDA)(leading expert in the ﬁeld of
decommissioning strategy in the UK)●Mr. Luis E. Echávarri (Spain)
Former Director General of the OECD/NEA (expert withexperience such as membership of the International Nuclear
Safety Group (INSAG))
The 1st International Advisors Meeting(from left, Mr. Barrett, Mr. Echávarri, and
Dr. Simper) (Jan. 9, 2014)

Open framework to gather knowledge from around the world

Board of Directors

International Advisors

Advice on organizational operation/management aspects

Alliance/collaborative
studies withtechnical partners
Procurement ofequipment, etc.
from technology vendors

Supply ofequipment

Coordination and optimizationof practical needs at the site

International
collaborative
projects
Joint projects

Project-1
Joint study

Project-2

OECD/NEA- Accident analysis, etc.

Sharing results

・・・

Collaborative studies
with research institutes

Needs atthe site

Integrated managementof R&D projects

IAEA- Review mission- Others

Technological advice

Advice from external experts
International Expert Group (IEG)
Technology Advisory Committee
Realization of new projects

Exchange of opinions on innovative ideas, technologies and projects

Mr. Echávarri receiving an explanation from
Mr. Akira Ono, Fukushima Daiichi NPS
Superintendent (Jan. 14, 2014)■ International Expert Group (IEG)
The International Expert Group (IEG) was established to offer technical advice from a global viewpoint to IRID and TEPCO regarding thesafe and effective carrying out decommissioning activities for TEPCO’s Fukushima Daiichi NPS. The IEG is composed of experts innuclear facility decommissioning from the USA, the UK, France, Russia and Ukraine.
IEG plenary sessions were held in February and September 2013 and in June 2014 to deliberate on nuclear decommissioning R&D
plans and measures to be carried out on site. A review mission for the removal of spent fuel from Unit 4 at the Fukushima Daiichi NPS
and a working group on radiation management at the site were carried out in November 2013 and May 2014, respectively.
After the plenary session held in June 2014, administrative responsibility of the IEG was transferred to TEPCO’s Fukushima Daiichi
D&D Engineering Company so that the Group can implement their activities closer to the site.

Members●Dr. Douglas Chapin (USA)
Principal of MPR Associates, Inc. (experience in the stabilization of the Three
Mile Island accident and clean-up of facilities)●Dr. Rosa Yang (USA)EPRI Senior Technical Executive (experienced in response to the Three Mile
Island accident and R&D for analysis evaluation)●Dr. Adrian Simper (UK)
Director for Strategy and Technology at the Nuclear Decommissioning
Authority (NDA)(leading expert in the ﬁeld of decommissioning strategy in theUK)●Dr. Joel Pijselman (France)
Chairman of the Board of Directors of ETC (successively held various posts,
such as plant manager of La Hague reprocessing plant and former Vice
President of AREVA)●Mr. Nikolai Steinberg (Ukraine)
Independent Consultant (involved in stabilization activities after the accident at
the Chernobyl Nuclear Power Plant in Ukraine and decommissioning strategy
development as a chief engineer at the Chernobyl plant)●Dr. Anton Leshchenko (Russia)
Deputy General Manager of Research and Development Company Sosny(involved in damaged fuel removal at Paks Nuclear Power Plant, Hungary)

Review of spent fuel removal at Unit 4 of the Fukushima Daiichi NPS(Nov.15, 2013)

Fukushima Daiichi NPS visit during the 2nd IEG meeting (Feb. 19, 2014)

Final session during the 2nd IEG meeting (Feb. 21, 2014)

Innovative ideas/technology proposals

Domestic and international companies, research institutes, etc.

18

19

Human Resource Development for R&D
Nuclear decommissioning is a long-term project that may span 30-40 years. Continuity and further development possibilities will be lost if
youth are not involved in work related to nuclear decommissioning technologies. One of our main challenges is to find ways to encourageinterest in these technologies among the young, and we need to attract and nurture personnel that can work onsite and be involved in R&D
activities.

1

Collaboration with universities and research institutions

IRID believes that the first step in human resource development is to build relations with people from universities and research institutions.
We have therefore been actively proceeding with joint research and commissioned research with universities/research institutions as partof our ongoing R&D projects. Through these activities, we have been enhancing cooperation with researchers in various technologicalfields.

2

Workshop for R&D Planning and Scientific Research for
the Decommissioning of TEPCO’s Fukushima Daiichi NPSIn FY 2013, as a co-sponsored initiative with the Ministry of Education, Culture, Sports, Science and Technology entitled the “Workshop for
R&D Plans and Scientific Research for Decommissioning of TEPCO’s Fukushima Daiichi NPS” was organized to set out important areas forhuman resource development and to select universities and research institutions which will become the core of this development. IRID has
actively expanded on this workshop idea and has held a total of nine workshops on various technological issues concerning nuclear
decommissioning themes in collaboration with universities, etc. throughout Japan.
The themes of these workshops have not been limited to the nuclear field; wide-ranging technologies, such as those used in the study of
volcanic lava, raw materials, remote operation and robotics have been discussed, and university professors and other experts from various
related fields, such as risk communication, have been invited to share their knowledge in order to make progress in the decommissioning
process. IRID has also used these workshops to provide updates on R&D project initiatives and outline technological needs. Universities
and other institutions have also presented their related research ideas, helping to promote very lively discussions and exchanges of
opinions.
In addition to sharing information on nuclear decommissioning research with researchers and experts from various regions and fields,
these activities have contributed to an increase in awareness and interest among students, and this has helped us take the first step
towards building a human resource development network.

For more details about the above activities, please visit the websites of the Nuclear
Safety Research Association and IRID.

Workshops Overview
Date

Area

Venue

1

Sep.25

Kanto #1

University ofTokyo

Fuel debris characterization/accident analysis.
Radioactive waste treatment/disposal, etc.

2

Oct.8

Fukushima

Korasse
Fukushima

Development of equipment/apparatus for remote operation, etc., to retrieve fuel debris.
Information visualization.

3

Nov.1

Kansai/West Japan #1

Osaka
University

Fuel debris characterization/accident analysis.
Radioactive waste treatment/disposal, etc.

4

Nov.20

Tohoku/Hokkaido

TohokuUniversity

Integrity of containment vessel/building for fuel debris retrieval anddecommissioning.

5

Nov.26

Kanto #2

University ofTokyo

Development of equipment/apparatus for remote operation to retrievefuel debris.

6

Dec.20Kansai/West Japan #2

7

Dec.25

Hokuriku

University of
Fukui

Long-term integrity of materials and structures.
Remote technology.
Fuel debris characterization/criticality control, etc.

8

Jan.8

Chubu

NagoyaUniversity

R&D for six key points, such as long-term integrity of materials and structures,
remote technology, etc.

Ibaraki
University

Overview of current status of R&D related to decommissioning and basic andgeneric technology research conducted by the Japan Atomic Energy Agency.
Function overview of the facility for analyzing and researching radioactive
material and its requirements.
General discussion (linkage between generic technology research and developmentof decommissioning technology).

9Jan.22

Kanto #3

Theme

Kobe International Development of equipment/apparatus for remote operation to retrieve
Conference Center fuel debris.

(Reference) Nuclear Safety Research Association website.

Workshop 2 (Oct. 8, 2013)

Workshop 4 (Nov. 20, 2013）

Workshop 6 (Dec. 20, 2013)

Workshop 8 (Jan. 8, 2014）●Handouts and program details about main workshop activities:
http://www.nsra.or.jp/safe/fdecomi/workshop/2013/index.html●Workshops held in FY 2013 (Photos and videos):
http://irid.or.jp/en/human̲resources/workshop/20131022

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