5F, 3 Toyokaiji Building, 2-23-1 Nishi-Shimbashi, Minato-ku, Tokyo 105-0003, Japan

Published: March 20162015-2016

――――― Our Vision
Our Purpose
To conduct experiments and research on decommissioning of
nuclear power stations, and implement projects aimed to

improve technological levels of member corporations and to put
their technologies into practical use.

Our Basic Principle
We devote ourselves to research and development (R&D) of
technology for the current most urgent challenge̶

decommissioning of the Fukushima Daiichi Nuclear Power
Station (NPS)̶from the standpoint of strengthening thefoundation of nuclear decommissioning technology.

Our Principle in Action
1. We work on R&D projects eﬀectively and eﬃciently whileadvancing integrated project management to develop andpropose the best technologies and systems that are

applicable early on site at the Fukushima Daiichi Nuclear

Power Station (NPS) while facing a lot of extremely diﬃcult
technological challenges.

2. We build an optimal R&D structure by cooperating with

CONTENTS
Message from the President ―――――――――――― 1◆Role of IRID ――――――――――――――――――― 2・Decommissioning Process Speciﬁedin the Mid-and-Long-Term Roadmap◆Scope of Business
R&D for Nuclear Decommissioning ―――――― 4
R&D at IRID
Overview of R&D Projects at IRID
Main R&D Topics
Promotion of Cooperation with RelevantInternational Organizations ―――――――――― 10・International Advisors
・Joint Research with Overseas Research Institutions
・Technological Cooperation with Overseas Nuclear
Organizations
・Information Release Overseas
Human Resource Development for R&D ――― 12
・R&D in Collaboration with Universities
・Eﬀorts for Human Resource Development

relevant organizations as well as our member organizations,and gathering knowledge from Japan and abroad.

3. We actively promote eﬀorts to develop and secure humanresources who will be major players in the next generation in
the ﬁelds of nuclear decommissioning and other related
technology ﬁelds, including eﬀorts to collaborate with
universities and research institutions.

Message from the President
Ever 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 of technologies required for the decommissioning work of
the Fukushima Daiichi NPS. In August 2014, the Nuclear Damage Compensation andDecommissioning Facilitation Corporation (NDF) was reorganized from the Nuclear
Damage Liability Facilitation Fund. Since then, the division of roles among relevantorg anizations eng a ging in the decommissioning has been c larified: The NDF
formulates strategies and R&D plans for the decommissioning; The Tokyo ElectricPower Company (TEPCO) implements on-site operation; and IRID conducts R&D oftechnology required for the decommissioning. The four key players including thegovernment have been working closely together in the effor t to decommission the
Fukushima Daiichi NPS. As a result, our R&D for fuel debris retrieval, including thedevelopment of technology for investigation inside the Primary Containment Vessel(PCV) and for identification of fuel debris locations, is gradually beginning to bear
fruit.
Under these circumstances, in April 2015, the NDF announced the Technical Strategic
Plan 2015 for Decommissioning of the Fukushima Daiichi Nuclear Power Station ofTokyo Electric Power Company. In June of the same year, the government revised the
Mid-and-Long-Term Roadmap towards the Decommissioning of TEPCO's Fukushima
Daiichi Nuclear Power Station Units 1-4 (Mid-and-Long-Term Roadmap), clarifying
milestones for fuel debris retrieval. The R&D for fuel debris retrieval is about to entera crucial phase.
Over four years have passed since the accident at the Fukushima Daiichi NPS
occur red due to the Great East Japan Ear thquake. A number of residents inFukushima Prefecture and surrounding regions are still forced to live as evacuees andmany Japanese people feel anxious over the decommissioning work at the Fukushima
Daiichi NPS. To enable the evacuees to return home as soon as possible and to dispel
the public's anxieties, it is vital to advance the decommissioning safely and surely.
IRID is determined to fulfil its responsibility to achieve steady results from R&D forthe decommissioning, according to the purpose of its establishment, i.e., to gather
k n ow l e d ge f r o m Ja p a n a n d a b r o a d a n d c o n d u c t R & D p r o j e c t s re q u i re d f o r
decommissioning effectively and efficiently. We sincerely appreciate your kind
guidance and continued support, and encouragement of our efforts.

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

5. We form an international research hub (a center of

excellence) through our R&D activities and contribute toacceleration of the decommissioning of the Fukushima Daiichi

December, 2015
Technology Research Association,
International Research Institute for Nuclear Decommissioning

Hirofumi Kenda, President

NPS and improvement of the technological capabilities in theinternational community.

◆Data
Organization Proﬁle ――――――――――――――― 14
・Technology Advisory Committee/Expert Advisors
・Technical Capabilities of IRID Members
List of Government Subsidized R&D at IRID ―――― 17

1

2015-2016

Role of IRID
According to the division of roles for decommissioning the
Fukushima Daiichi NPS, the Nuclear Damage
Compensation and Decommissioning Facilitation
Corporation (NDF) formulates strategies and R&D plans fordecommissioning, TEPCO's Fukushima Daiichi
Decontamination and Decommissioning (D&D) Engineering
Company performs the on-site operation, and IRID
conducts R&D. Thus, the three parties have established astructure under which they closely cooperate with eachother and work as one.
As an organization that plays a part in the structure, IRID,
through its R&D, actively works on risk reduction, ensuringsafety, environment preservation, etc., which are required
for the decommissioning of the Fukushima Daiichi NPS, so
as to help relieve anxieties of people in Fukushima
Prefecture and the rest of Japan.

IRID is a body made up of 18 organizations engaged
primarily in research and development required fordecommissioning of the Fukushima Daiichi NPS.
Its long-term goal is to foster, accumulate and improve
decommissioning and other related technologies for thedecommissioning of reactors throughout Japan. However,for the present time, we are focusing on the urgent
challenge—R&D for decommissioning of the Fukushima
Daiichi NPS—in accordance with the Mid-and-Long-Term
Roadmap set by the government.
IRID continues to gather knowledge from Japan and abroad
to conduct R&D required for decommissioning efficiently
and effectively in order to advance this globally
unprecedented, extremely difficult project.

Decommissioning Process Speciﬁed in the Mid-and-Long-Term Roadmap
The Mid-and-Long-Term Roadmap towards the Decommissioning of TEPCO's Fukushima Daiichi Nuclear Power
Station Units 1-4 (Mid-and-Long-Term Roadmap) has been formulated based on present knowledge and analysis ofconditions that differ for each Unit of the Fukushima Daiichi NPS. It was revised a third time on June 12, 2015. The
revised Mid-and-Long-Term Roadmap shows the goals and estimated target years of the decommissioning process
based on an assumption that it is subject to revisions according to future on-site conditions, R&D results, etc.
The Roadmap divides the time until the completion of the decommissioning into three phases. Presently, thedecommissioning process is in the second phase; we are developing R&D for preparation for fuel debris retrieval.
IRID previously analogized the conditions inside the Primary Containment Vessels (PCVs) using analysis codes etc.
We presently visualize the conditions of reactor cores utilizing cosmic ray muons. We also investigate inside PCVs
with robots and verify previous analogy-based data by comparing with visual data. Thus, albeit gradually, we arecompiling data that allows us to study various new approaches to technological difficulties faced in advancing R&D
for the decommissioning, as well as developing new approaches to decommissioning methods.

Phases Deﬁned in the Mid-and-Long-Term Roadmap and R&D Structure
Phases of the Mid-and-Long-Term Roadmap

Role of IRID

December 2011
Eﬀorts to stabilize plantcondition(Step 1 and 2 completed)

Roles of the Organizations Involved in Decommissioning Project of the Fukushima Daiichi NPS

Government(Fukushima Daiichi D&D Engineering Company)

Steady implementation of decommissioning

Progress management
ReportPolicy making and progress management● Formulate the Mid-and-Long-Term● Remove fuel from spent fuel pools

environments, etc.

Supervise/Review

Report/Submit an action plan

Propose R&D
Put development results
in practical use and provide
information on the results

R&D needs

Ad

vic

Re

po

IRID

e/

rt

Gu

ida

Nuclear Damage Compensation
and Decommissioning Facilitation
Corporation (NDF)

nce

Implementation of R&D● R&D for fuel removal from spent

Formulation of strategies andprovision of technological support

Share progress
and issues

fuel pools● Develop a mid-and long-term strategy● Provide technical support for progress
management of key issues● Carry out R&D planning and progress
management, etc● R&D for preparation for fuel debris
retrieval● R&D for treatment and disposal ofradioactive wast

Pro

Nuclear Regulation Authority
Implementation of safety regulations

Re

jec

po

rt

tc

os

res

t(

Period up to thecommencementof fuel removalfrom spent fuel pool

Period up to the commencementof the fuel debris retrieval
Target: within 10 years after thecompletion of Step 2

Period up to
the completionof decommissioning
measures

Target: within 2 years
after the completionof Step 2・ Decision of a fuel debris retrieval policy
for each Unit (Target: 2017)
・ Finalization of a fuel debris retrieval
method for an initial Unit
(in the ﬁrst half of FY 2018)
・ Start of fuel debris retrieval at the initial
Unit (within 2021)

idy)

Target: 30 to 40 years
after the completionof Step 2

T EPCOIRID is engaged in research, ranging
from fundamental research topractical use of technology.

Research institutions including IRID
Ministry of Economy, Trade andIndustry: Project of Decommissioning
and Contaminated Water Management etc

Japan Atomic Energy Agency (JAEA)
Universities and research institutions

Foundational researchsbsPhase 3R&D Structure

ult

su

Phase 2(completed)

Now

ReportReport● Ensure safety/quality, improve work

Issue a project grant● Store and manage rubble, waste, etc.

Present key issues

Roadmap, etc.

● Manage contaminated water・Accomplishment ofa cold shutdownstate・Signiﬁcantreduction ofradioactive
materials release

Phase 1

December 2021- After 30 to 40 years

Funds for technology development(Secretariat: Mitsubishi Research Institute, Inc.)

Basic research

Applied development

Practical use
・ On-site requirements
・ On-site conditions
・ Regulatory requirements
・ Performance assurance

・ Application of newtechnology
・ Development of devices and equipment
・ Performance demonstration
・ Acquisition of safety data

・ Special research facilities and equipment
・ Fundamental
clariﬁcation
・ Collecting of foundational data
・ New ideas
・ Human resource
development and education

Uniﬁcation of knowledge
and researchers

TEPCO

November 2013

<Source> The above charts were created based on the Mid-and-Long-Term Roadmap (the third revision), as of June 12, 2015.

2

3

2015-2016

Scope of Business 1: R&D for Nuclear Decommissioning
R&D at IRID

Fuel Debris

IRID is conducting research and development to advance decommissioning of the Fukushima Daiichi NPS based on the
Mid-and-Long-Term Roadmap. The primary focus of our R&D activities is the upgrading of decommissioning strategies. For
this purpose, we are studying whether there are any other optimal approaches, how to reduce risks, etc., while exploring how
to achieve an end state (final optimal state), in tie-ups with TEPCO, relevant organizations, etc.
We have undertaken three main projects for decommissioning: R&D for Fuel Removal from Spent Fuel Pool, R&D for
Preparation of Fuel Debris Retrieval, and R&D for Treatment and Disposal of Radioactive Waste.

Total loss of all power sources at Units 1-3 of the Fukushima Daiichi NPS disabled the circulation pumps, preventing theflow of water into the RPVs. Without the necessary water to cool them down, the fuel inside the RPVs overheated, withtemperatures thought to have risen above 2,000 degrees Celsius—a temperature 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. Thissolidified material is called "fuel debris."
With radiation levels inside the PCVs being tremendously high even now, workers cannot get near the structures; the shapeand location of fuel debris can only be estimated using computer simulations.
The decommissioning process demands fuel debris to be retrieved from inside and stored under safe and stable conditions.

Overview of the Reactor Building and R&D at IRID

(Reference)

Fuel debris*1

Reactor building

Study of Options for Methods of Fuel Debris Retrieval
Fuel debris retrieved from Three
Mile Island Nuclear Generating
Station Unit2 (TMI-2) in the USA.

Spent fuel pool*2

Photo provided by the Japan Atomic
Energy Agency (JAEA)

Reactor Pressure Vessel (PCV)*3

R&D for Preparationof Fuel Debris Retrieval

R&D for Fuel Removalfrom Spent Fuel Pool

Drywell (D/W)*5
Vent pipe*7
Suppression Chamber (S/C)*6

R&D for Treatment andDisposal of Radioactive Waste
Torus room*8＊5 Drywell (D/W): A safety feature that is comprised of aflask-shaped container that houses equipment, including theRPV, and contains radioactive substances in case of an
accident occurring＊2 Spent fuel pool: A water tank that stores spent fuel that isinserted in a rack under water until decay heat generated
from fission products decreases. This tank is located on the
top floor of the reactor building.

＊6 Suppression chamber (S/C): A doughnut-shaped facility that
stores water located in the basement of the reactor building.
Condenses vapor generated in the case of reactor piping
breakage and prevents excess pressure from building up. It
also serves the important function of providing a water source
for the Emergency Core Cooling System (ECCS) in the case ofa loss-of-coolant accident.

＊4 Primary Containment Vessel (PCV): A steel container thathouses the RPV, cooling equipment, and other devices that
perform important functions. 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 of coolingequipment. It should be noted that each of the PCVs
installed in Units 1-3 at the Fukushima Daiichi NPS consistsof a flask-shaped drywell, a doughnut-shaped suppression
chamber and eight vent pipes connecting between thedrywell and the suppression chamber.

4

The Conceptual Diagrams of Three Representative Methods for Fuel Debris Retrieval

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

＊3 Reactor Pressure Vessel (RPV): A cylindrical steel containerthat houses fuel assemblies. This container can resist
high-temperature water and high-pressure steam generated
by the energy released by nuclear fission inside. The RPV ishoused within the PCV together with cooling equipment

Taking the Three Mile Island accident in the USA as a precedent, we have studied fuel debris retrieval methods while
prioritizing the "submersion method," whereby fuel debris is fully submerged in water. This is because the method offers
advantages in that water is expected to provide a shielding effect against radiation and dust scattered during the fuel debris
retrieval process. This helps reduce the radiation exposure of the workers.
However, in order to submerge fuel debris under water, it is necessary to fill with water up to the upper part of the PCVs
that have been affected by the severe accident at the Fukushima Daiichi NPS. There are many developmental challenges inrepairing the PCVs and stopping water leakage from them. It is therefore assumed that fuel debris may not be submerged inwater. Given these points, the Nuclear Damage Compensation and Decommissioning Facilitation Corporation (NDF)
suggested, in its Technical Strategic Plan 2015 for Decommissioning of the Fukushima Daiichi Nuclear Power Station ofTokyo Electric Power Company, that there is a need to study not only the submersion method, but also the partial
submersion method where fuel debris is retrieved with a part of it being exposed to the air. The NDF also showed three fueldebris retrieval methods to be focused upon as options that consider water levels in the PCVs and access directions to fueldebris (top, bottom and side), based on the viewpoints of the progress status and feasibility of technology development andrisk management.

＊7 Vent pipe: Connecting piping that takes vapor generated within
the D/W to the S/C in case of a reactor pipe breakage. Eightvent 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 the basement of the reactor
building.

Submersion̶Top entry method
Assuming the in-core structures
above the fuel debris are removed

Partial submersion̶Top entry method
Assuming that the in-core structures
above the fuel debris are removed

Partial submersion̶Side entry method
Assuming that the equipment and otherobjects outside the RPV pedestal in the
PCV are removed<Source> 'Technical Strategic Plan 2015 for Decommissioning of the Fukushima Daiichi Nuclear Power Station of Tokyo Electric Power Company' developed by NDF

5

Scope of Business 1: R&D for Nuclear Decommissioning
Technology for Fuel Debris Retrieval
Technology for Evaluating the Integrity of the Reactor
Pressure Vessel/Primary Containment Vessel

・Evaluation of long-term structural integrityof fuel assemblies (corrosion tests thatassume storage environments for removed
fuel assemblies and investigations of actual
fuel assemblies)
・Study of methods to process
damaged fuel and evaluationof impacts on damaged fuelwhen it is processed withthe methods

Technology for Investigation andAnalysis of the Reactor Interior
Technology for
Investigation
Inside theReactor Pressure
VesselBuilding behavior analysis(Building damage simulation)

Model creation

Technology
for Collection,
Transfer andStorageof Fuel Debris

Investigation of thecondition of stored
fuel

Corrosion
evaluation

Technology for Investigation Inside
the Primary Containment Vessel
Developmentof robots to investigate
the PCV interior

・Water level・Basis ground motion Ss
・Damage to equipment
・Inﬂuence of corrosion

Organizing
loading
conditions

Equipment
strengthassessment

Assessment
condition
・Allowable value・Corrosion wall thing・High-temperaturestrength deterioration

Canister handlingcrane (Shield)

Debris loading
Lid tightening
Closing plugattachment

Simulation of criticality
Criticality
detection
Fission output
Total quantityof ﬁssion
Judgement
criteria
for criticality

Canister handling crane(Shield)

Time (h)Shield plug

Spent
fuel
pool

Primary Containment
Vessel (PCV)

Muon
detector
Simulated image

DebrisTechnology for Decontamination
and Dose Reductionals

Technology for Treatment
and Disposal of Solid Waste

Technology for Remotely-operated
Decontamination in the Reactor Building・Characterization of
accident-generated waste
・Study of long-term storage
management
・Study of treatment and disposal

Identifying
Conditions Inside
the Reactor throughCore
Application of
Severe Accident Mol ten Core
Analysis Code, Core Support Plate
Data on the Actual
Particulate Debris
Reactor andMetal L ay e
Reactor Internals, Melton Pool
Solidiﬁed Crustetc.

ShroudMeasurement image

Improvement
Vessel Failure
Mechanism Modelof the physicalphenomenological PCV Floor Sump Pit
model
Corium Leakage through Sump
Piping Erosion Shape Model

6

CR Guide Tube
CRD Housing

Lower Plenum Debris
Bed Layering Model

Suppression
Chamber
Torus room (S/C)

High-pressure water
jet decontamination(for low places)
Dry ice blast
Equipment for decontaminating decontamination
upper ﬂoors (for upper ﬂoors)(for high places)

Repair and Water Leakage Stoppage Technology
for Leakage Points Inside the Primary Containment VesselmFull-scale test of repair
and water leakage stoppageof the PCV lower part

Characterization using simulated debris
Molten Fe-Cr-Ni- Zr -U-(Si-Mo-B-C)
Molten U-Zr-O

Technology for Repair
and Water Stoppageof the PrimaryContainment Vessel
Full-scale Test

Fuel Debris Characterizationm

Surface solidiﬁcation

Test of water leak stoppageof thevent pipe (with a half-scale mock-up)

Overhead craneThermal Conduction from Debris
to CRD Housing, Radiation HT
between CRD Housings
Bulk Cooling Model for the Early
Phase of Water Addition
on Top of Corium

Decontaminationof upper ﬂoors

Vent pipe

Radiation HT Model
between Shroud
and RPV Wall

Fuel Support PiecesnMuo

Decontaminationof low places

RPV WallJet PumpnMuo

Decontaminationof high places

Technology for Investigation and Analysis(Characterization) of the Reactor Interior

Achievementof subcriticality

Technology of Retrieval of Fuel Debris
and Reactor Internals

Reactor Pressure
Vessel (RPV)

Technology for investigationof fuel debris distribution
in the RPV using cosmic ray
muons

Start of boron
water injection

Reactor vessel

Operating ﬂoor

Technology for
Detection of Fuel
DebrisStop ofsubmersion

Transport
cask

Canister

Design of equipment
to investigate from a top route created by a boring process

Building-equipment
coordination
behavior analysis

Technology for
Criticality
Control in
Fuel Debris
Retrieval

Total quantity of ﬁssion

R&D for Fuel Removalfrom the Spent Fuel Pool

Fission output (W)Overview of R&D
Projects at IRID

2015-2016

Core component

Concretecomponent

Work ﬂoor

Concrete
Thermally-deteriorated concrete(Embrittlement)

Molten concrete(Molten vitreous state)

Pyrolysis gas(Mainly H2O)

Assembly

Demonstration test

Dismantling

Development of robots forinvestigating water leakage points

Test of reinforcement of the S/Cleg part (with a full-scale mock-up)

7

Scope of Business 1: R&D for Nuclear Decommissioning

2015-2016

Main R&D Topics
Technology for Visualizing the Reactor Interior Using Cosmic Ray Muons
Muon particles (muons) are generated by the collision of cosmic rays with the earth's atmosphere. About 170 muons per square meter
rain down on the earth’ s surface each second. Muons are characterized by the ability to easily penetrate substances. Some muons,however, cannot penetrate substances because they lose a part of their energy due to interaction with electrons in the process ofpenetrating the substances. Others are deflected from their initial direction due to interaction with nuclides. In collaboration withresearch institutions in Japan and abroad*, IRID developed equipment using the transmission method technology to detect the former
muon phenomenon and other equipment using the scattering method technology that detects the latter muon phenomenon. In 2015,
we successfully visualized the inside of the Fukushima Daiichi NPS Unit 1 using the transmission method. As a result, we obtained
information credible enough to convince us that it is reasonable to think there is no fuel at the location where the reactor core in Unit 1
originally existed. * High Energy Accelerator Research Organization (KEK), Los Alamos National Laboratory (LANL), etc.
Cosmic rays

Muon

Spent fuelpool

One day

Muon
One week

Muon
detector

One monthThree months

About one muon strikes
an extended human hand on the earth.
Images depicting the reactor
interior using the transmission
method (Changes for eachmeasurement period)

The muon detector was installed on the ground outside
the reactor building of Unit 1 to measure muons.

Amount of permeationis measured.

Target ofvisualization

Scattering method
Light-weight substance

Muon particles

Heavy-weight substanceTarget ofvisualization

small

Muon particles■ This is equipment used to remotely decontaminate
upper floors (the second and third floors) of the reactor
building, using three methods: high-pressure water jet;dry ice blast; and suction/blast. A lifter is used to movethe equipment up or down to and from upper floors.
■ When in use, the decontamination equipment for upper
floors comprises a combination of devices developed
separately by Hitachi-GE Nuclear Energy, Ltd., TOSHIBACORPORATION and Mitsubishi Heavy Industries, Ltd.,
respectively. Wheeled platforms are designed for common
use so that a certain type of decontamination unit carriedon each wheeled platform can be replaced with anothertype in order to effectively use the wheeled platforms anddecontamination units.

A line of wheeled platforms constituting the remotely-operated decontamination equipment(in the suction and blast method)
The equipment goes up and down to a heightequivalent to that of the second ﬂoor of the reactor
building (a height of up to 8 m above the ground).

Repair and Water Leakage Stoppage Technology for Leakage Points Inside the PCV■ Tested water leakage stoppageof the downcomer in S/C*
Pressure was applied tounderwater anti-washout
concrete in the S/C and tested
the water permeability of theconcrete. The test results
confirmed that the amount of
the water leakage was minimal
and it was therefore possible tostop water leakage from thedowncomer.
* Suppression chambe
Injecting grout into(pressure control room)a large-sized downcomer■ Tested properties of reinforcement materials
that had risen after injection into a mock-up
A mock-up as large as the real S/C
was prepared and injected withreinforcement materials from one sideof the mock-up. This tested whether
the reinforcement materials could
reach and rise at the other side. The
test results confirmed that the height
to which the injected reinforcement
materials rose on the other side waslower by about 4 cm than at the sidefrom which the materials were
injected: this difference would notcause any problem when thetechnology is applied at the
Fukushima Daiichi site.
Pipe for injecting
reinforcement materials

Detector1

Picture of a full-scale mock-up

Scattering location

Detector2

Large

large

Scattering angle
is measured.

○ Presence of matter in incoming direction(two dimensional)◎ Presence of matter in locations where muon particles
scatter (three dimensional) Capable of identifying
locations of nuclear fuel material such as uranium○ Spatial resolution: about 1 m◎ Spatial resolution: about 30 cm◎ One small-size detector (applicable early)○ Two large-sized detectors (They have been developed.)

50.

Tremie pipem

S/C equator
Pin junction
part

1.3 m

Small

5.26 mLarge

Detector

Features

The muon detector using the transmission
method that is housed in a 10-cm-thickiron shield. (It consists of three units
arranged in three layers.
Outside dimensions: 2.5 m x 2.0 m x 2.1 m)

Mechanism

Transmission method

Technology for Remotely-operated Decontamination (Development of Decontamination Equipment for Upper Floors)

Transparent window(portion)10.1 mAbout 10 m

Technology for Investigation Inside the Primary Containment Vessel (PCV)■ Robot for investigating inside the PCV at Unit 1 (shape-changing robot)

We developed a robot to investigate the outside of the pedestal of the PCV at
Unit 1. We also used the robot to investigate the condition inside the PCV after
changing the robot's shape: The robot was converted to a rod shape with adiameter of about 10 cm when it penetrated the material. Then, the robot wasconverted to another shape when it moved inside the PCV to improve its moving
performance. We received the 7th Robots and Society Award of the Robotics
Society of Japan for this achievement.
In going through a penetration
leading to the PCV

In moving in the PCV

Shapechange8■ Robot for investigation inside the PCV at Unit 2
We have developed a robot to investigate the interior of
the pedestal of the PCV at Unit 2. After entering thepedestal, the shape of the robot was changed to raise
its tail section like a scorpion to improve its field ofview.

Range of ﬁlling with reinforcement
materials in Unit 1

Test on the water leak stoppage of the large-sized downcomer

Range of ﬁlling with reinforcement
materials (in Unit 1)

Information
More details about IRID R&D are
available on IRID s website and inits brochures.
Please visit the IRID webpage for
information and brochures.

Outline of the full-scale mock-up(simulating Unit 2 and 3)

IRID Annual Research
Report 2014

RobotsIRID Website http://irid.or.jp/

9Promotion of Cooperation with
Scope of Business 2: Relevant International Organiza tions
Under an operational policy that IRID is an open organization, IRID is striving to strengthen
relationships with relevant international organizations and experts to gather knowledge fromJapan and abroad while conducting its activities.

2015-2016

Technological Cooperation with Overseas Nuclear Organizations
We are advancing technological cooperation with overseas nuclear organizations that have experiencein decommissioning reactors and handling damaged fuels.

I n ternat io nal A dvi sor s■ At the Paks Nuclear Power Plant in Hungary

The International Advisors group consists of three nuclear
experts from around the world. This group was establishedto provide IRID's Board of Directors with advice fromorganizational, management and other perspectives.
Meetings were held to deliberate on the international
initiatives and management approach of IRID to provide
advice to IRID on future issues and points for
improvement.

We discussed how to handle damaged fuel andsafety in storing removed fuel. We are utilizing
results of these discussions for developmentof fuel debris canisters.

■ Members■ At the International Atomic Energy Agency (IAEA)

headquarters in Vienna, Austria

We discussed ideas concerning
decommissioning of the
Fukushima Daiichi NPS with ateam of IAEA experts consistingof engineers from many
countries. We also received advice
on how to gather technologicalinformation that will be of further
importance.

Mr. Lake Barrett (USA):
Independent Consultant (former Site Director for the Nuclear Regulatory
Commission (NRC) for the Three Mile Island accident)

Professor Melanie Brownridge (See the note below.) (UK):The Third IRID International Advisors Meeting (December 2, 2015)** From the left: Prof. Brownridge, Dr. Simper, Mr. Barrett, Mr. Echavarri

Head of Technology at the Nuclear Decommissioning Authority(NDA) (Head of R&D)

Mr. Luis E. Echavarri (Spain):
Former Director General of the OECD/NEA (expert with experience such as
membership in the International Nuclear Safety Group (INSAG)(Note) She is a UK member from the Third IRID International Advisors
Meeting. Dr. Adrian Simper (NDA director) served as a UK member at theFirst and Second IRID International Advisors Meetings.

■ Schedule・January 9-10, 2014 The first meeting was held.

・November 17-19, 2014 The second meeting was held.
・December 2-4, 2015 The third meeting was held.

■ At the Paciﬁc Northwest National Laboratory

and the Hanford facility in the USA.

We obtained knowledge on how to remove
damaged fuel and store it safely after removal. We
will continue to promote technical cooperation.

Joint Research with Overseas Research Institutions
We are collaborating with overseas research institutions to produce and analyze large-scale simulated debris
using uranium.
■ National Nuclear Center of the Republicof Kazakhstan (NNC)
Joint activities included producing aheterogeneous molten solidified substance by
mixing and melting tens of kilograms ofmaterials such as uranium fuel and cladding
tubes and making the mixed molten material
react with metal such as reactor components.
The test sample of the molten solidified
substance is used to study the mixed state ofmetal and ceramics and the properties ofinterface between the two.

Stainless steel plateWith the use of products generated when the
CEA tested molten core-concrete interaction(MCCI) with tens of kilograms of uranium,properties of the MCCI test products areanalyzed to predict actual MCCI products.

10

Tray

Information Release Overseas
We provideour results of our research and development at forums etc., organized by relevant internationalorganizations.
Area where stainless steel
plate has melted■ French Atomic Energy and Alternative

Energies Commission(CEA: Commissariat a l'Energie Atomiqueet aux Energies Alternatives)

Fuel debris

Metal which has solidified
after melting

Upper oxide crust
Corium/Concreteinterface(vertical direction)

Corium/Concreteinterface(horizontal direction)

Corium oxide
phase
Continuous
metallic phase

Silica-based
concrete

Lecture at the 2015 IEEE/RSJ International Conference on Intelligent
Robots and Systems (IROS) Workshop (October 2, 2015)

Lecture at the German-Japanese Symposium (April 21, 2015)

11

2015-2016

Scope of Business 3: Human Resource Development for R&D
Nuclear decommissioning is a long-term project that may span 30 to 40 years. It is therefore vital to get young
people engaged in work involving pertinent nuclear decommissioning technologies.

R&D in Collaboration with Universities

3. IRID Symposium
The IRID Symposium 2015 was held in Fukushima on July 23, 2015 to introduce achievements of our research anddevelopment in an easy-to-understand way; this also gave us an opportunity to explain our initiatives tomunicipalities, companies, school oﬃcials and the public in Fukushima Prefecture.
On the day of the symposium, panels and images were exhibited and a robot was demonstrated, which provided
opportunities for about 240 participants to directly communicate with IRID staﬀ members responsible for R&D.

IRID is involved in joint R&D of technologies with universities to improve the operabilityof remotely operated equipment.
Enhancement of capability to grasp surrounding conditions

Technological challenges[Yamashita Lab, University of Tokyo]● Easy-to-understand displays
showing conditions around robots● Improvement of operability ofmulti-joint manipulator
Improvement of capability to grasp
surrounding conditions[Tsubouchi Laboratory, University of Tsukuba]

The laboratory developed a system capable of mapping 3D
measurement data captured by cameras and laser sensors aroundthe robot and displaying the mapping in an easy-to-understand way.

Screen displaying 3D mapping ofdata captured by Super Giraﬀe(under development)

Image of a display showing
surrounding environment
using sensor-captured 3D dataand camera-captured images

The lab developed
technologies that enableeasy adjustment ofimage correction thatenables operators tofreely change types,
overview image
mounting positions and Simulated
captured by Super Giraﬀeorientations of cameras.

Simulated overview image
captured by MEISTeR

Improvement of operability [Yokokohji Laboratory, Kobe University]

Explaining the current status of R&D
for the decommissioning

Exhibiting and demonstratinga shape-changing robot (prototype)

Exhibiting panels

4. Participation in various events
We have actively provided lectures and participated in meetings and events hosted by various organizations such as the scientiﬁc societies.

The laboratory developed a manipulation interface that allows operators to give immediate motioncommands to the multi-joint manipulator to perform self-motion*, in order to improve the operability ofthe manipulator.
＊ Movement to change theChange the posture(Move the shoulder
forward and backward)

Fix the positionand postureof the hand tip

manipulator's overall shapewith position of hand tip
and base ﬁxed

Examples of the self-motion movement of the ninedegree-of-freedom manipulator

Eﬀorts for Human Resource Development

Lecture of Environmental Radioactivity Measures& Radioactive waste Disposal International Exhibition(RADIEX) 2015 (July 16, 2015)

Panel discussion at the 33-rd Annual Conferenceof the Robotics Society of Japan (September 5, 2015)

1. Workshop activities in cooperation with human resource
development project hosted by the Ministry of Education,
Culture, Sports, Science and Technology (MEXT)IRID participates in workshops held by universities andresearch institutions in cooperation with human development
project 'Decommissioning Basic Research: Human resource
development program', hosted by the MEXT.

Second workshop for FY 2014 in Tohoku University(January 15, 2015)

Lecture in the special session on decommissioningat the 2015 Fall Meeting of the Atomic Energy Societyof Japan (Sept. 11, 2015)

Exhibition and demonstration of the shape-changing
robot (prototype) at the Robot Festa Fukushima 2015
(November 3, 2015)

2. Information release to universities, research institutions, etc.
We are participating in joint and contract research with universities,
research institutions, etc. and dispatching lecturers to speak at their sites.

Information̶We have an IRID glossary on our website̶
The IRID Glossary consists of a Japanese-English/English-Japaneseglossary named "TransI" (containing about 2,500 terms) and anuclear-related abbreviation glossary named "TermsI" (containing
about 12,000 terms).
We hope that the IRID Glossary will be used by companies andstudents engaged in decommissioning projects in Japan andabroad, and hope that it will facilitate decommissioning of the
Fukushima Daiichi NPS as much as possible.

Guest lecture at the Department of MechanicalEngineering, National Institute of Technology,
Oyama College (December 8, 2014)12

Lecture at the 4th University-Industry
Guest Lecture at Koriyama City Tomita
Cooperation Forum at the University of Aizu Junior High School (November 25, 2015)(March 2, 2015)

Website URL
http://irid.or.jp/glosy̲index.html▶

(Note) This system operates only in Internet Explorer. It is not available in other browsers.

The search system of the IRID Glossary

13

2015-2016

Data
Organization Proﬁle
1. NameOrganizational Structure of IRID

Technology Research Association,<Establishment of Our Organization>
August 1, 2013: Establishment of IRID was approved by the
Minister of Economy, Trade and Industry under the Act on
Research and Development Partnership.

2. Location of Headquarters

August 8, 2013: IRID held its inaugural General Meeting
and Board of Directors meeting, and began operation.

International Research Institute for Nuclear
Decommissioning (IRID)
5F, 3 Toyokaiji Building, 2-23-1 Nishi-Shimbashi, Minato-ku,
Tokyo 105-0003, Japan
TEL: +81 3 6435 8601 (representative)
3. Date of Establishment
August 1, 2013

4. Scope of Business・ R&D for nuclear decommissioning

・ Promotion of cooperation on nuclear decommissioning
with relevant international and domestic organizations

・ Human resource development for R&D
5. Membership (18 organizations)

National Research and Development Agencies:
Japan Atomic Energy Agency

National Institute of Advanced Industrial Science andTechnology
Manufacturers, etc.:
TOSHIBA CORPORATION

Hitachi-GE Nuclear Energy, Ltd.

<Organizational Role>
IRID devotes its utmost eﬀorts to the current urgent
challenge̶R&D for the decommissioning of the
Fukushima Daiichi NPS̶in cooperation with the Nuclear
Damage Compensation and Decommissioning
Facilitation Corporation (NDF) and Tokyo Electric Power
Company, Incorporated (TEPCO), with a view tostrengthening the foundation of future decommissioning
technology and to fostering, accumulating and improving
related technology.
<Organizational Structure>

・ IRID was inaugurated with 17 organizations, with the
General Meeting as the highest decision-making body andthe Board of Directors as the executive body, incompliance to the Act on Research and Development
Partnership. We presently consist of 18 organizations after
ATOX Co., Ltd., joined in May 2015.

ATOX Co., Ltd.

Electric utilities, etc.:

Hokkaido Electric Power Co., Inc.
Tohoku Electric Power Co., Inc.

Tokyo Electric Power Company, Incorporated (TEPCO)
Chubu Electric Power Co., Inc.

Hokuriku Electric Power Company

The Kansai Electric Power Company, Incorporated
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

Board of Directors

International Advisors

R&D Management Department

Administration Department

Technology Advisory
Committe

R&D Strategy Planning Department

Administration & Human Resource
Management Team

Planning & Management TeamInternational & Academia Cooperation Team

Accounting & Procurement Team

Corporate Communication TeamRadioactive Waste Treatment
and Disposal
Technology GroupPCV Investigation,
Repair & Structural Integrity
Assessment Technology Group

Fuel Debris Retrieval
Technology Groupp

・ Our organization consists of three departments: the R&D
Strategy Planning Department, responsible for planning,
human resource development, international cooperationand public relations; the R&D Management Department,
responsible for R&D; and the Administration Department,
responsible for administration. The following four Groups
are dedicated to research projects: the Radioactive Waste
Treatment and Disposal Technology Group; the PCVInvestigation, Repair & Structural Integrity Assessment
Technology Group; the Debris Retrieval Technology Group;and the Reactor Interior and Fuel Debris Evaluation
Technology Group.

Reactor Interiorand Fuel Debris Evaluation
Technology Group(as of October 1, 2015)

・Eleven Directors and one auditor have been appointed.
Some Directors are from non-IRID member organizations(universities and companies).
・ To promote decommissioning, we have appointed theInternational Advisors and set up the Technology Advisory
Committee, thereby realizing a structure to obtain thelatest global expertise.

Mitsubishi Heavy Industries, Ltd.

General MeetingTechnology Advisory Committee/Expert Advisors
IRID has set up the Technology Advisory Committee to obtain advice from external experts with high levelsof knowledge. We have received from the Committee a wide range of opinions from broad viewpoints,
including advice on technology that is extremely hard to be realized, and is based on the latest knowledge,
advice on project-speciﬁc and cross-project planning, advice on human development projects, etc.
We have also received from the Expert Advisors opinions on the research plan, implementation method
and result evaluation of each project, etc., and reﬂected the opinions in our R&D.

<Changes in Project Costs>
160 (Unit: 100 million yen)

6. 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. Kunikazu Kishimoto,
Mr. Masahiro Seto, Mr. Mamoru Hatazawa,
Mr. Jun Matsumoto, and Mr. Yoshinori Moriyama
Auditor: Mr. Nakatani Satoru

120

80

40

7. Number of Personnel

835* (excluding the number of the board of directors)* This number includes the number of staﬀ engaged in research
conducted by IRID at IRID member organizations

14(as of October 1, 2015)

The fourth Technical Advisory Committee (March 24, 2015)

FY 2013 (from August)

FY 2014

FY 2015 (estimate)

IRID Expert Advisors inspecting the workplace of robot development** 'TEMBO' equipment to remove shielding blocks and iron plates

15

Data

Technical Capabilities of IRID Members
1. Japan Atomic Energy Agency (JAEA)
JAEA believes its most important project is to contribute to recovery from the accident at the Fukushima Daiichi NPS and eﬀorts
for reconstruction of Fukushima and other aﬀected areas. JAEA has scientiﬁc and technical expertise as the sole comprehensive
nuclear research and development institution in Japan.
2. National Institute of Advanced Industrial Science and Technology (AIST)
AIST conducts R&D covering seven areas: energy and environment; biotechnology; information and human engineering; materials
chemistry; electronics and manufacturing; geology; and measurement standards. AIST has broad scientiﬁc knowledge and technicalcapabilities required for implementing IRID projects.
3. TOSHIBA CORPORATIONAs a plant manufacturer, Toshiba has expertise, experience, and a proven track record in the ﬁelds of development of
decontamination technology, PCV inspection and repair technology, remote operation technology, etc., related to the Project ofDecommissioning and Contaminated Water Management. The company is capable of applying their development results broadly.

2015-2016

List of Government Subsidized R&D at IRID
The Project of Decommissioning and Contaminated Water Managementin the FY2013 and the FY2014 Supplementary Budgets
Key Challenge 1: R&D for Fuel Removal from the Spent Fuel PoolKey Challenge 2: R&D for Preparation of Fuel Debris Retrieval
Key Challenge 3: R&D for Treatment and Disposal of Radioactive Waste
Key
Challenge

1
2

4. Hitachi-GE Nuclear Energy, Ltd.
The company puts in place a consistent structurer, ranging from the planning, designing and manufacturing to construction andmaintenance service of nuclear power stations and further operator training. The company is capable of developing usefultechnology for long-and mid-term eﬀorts towards the decommissioning of the Fukushima Daiichi NPS, etc.
5. Mitsubishi Heavy Industries, Ltd.
Mitsubishi Heavy Industries oﬀers services ranging from basic planning to designing, and includes manufacturing, construction,
maintenance and repair of pressurized-water reactor (PWR) nuclear power stations. The company has also accumulated anabundance of technologies in each of its business ﬁelds, i.e., nuclear fuels, advanced reactor plants and nuclear fuel cycles, which
are very eﬀective for project management in planning R&D. The company is capable of utilizing, applying and spreading its
obtained results broadly.
6. ATOX Co., Ltd.
ATOX has expertise, experience and a proven track record in operation, inspection and repair, decontamination, and radiation
control of general nuclear-related facilities. The company is highly capable of putting their expertise, experience and proven trackrecord into practice at the site. It also possesses gamma irradiation facilities and is capable of developing usefuldecontamination-related technologies.
7. Tohoku Electric Power Co., Inc., Tokyo Electric Power Company, Incorporated (TEPCO), Chubu Electric Power Co., Inc.,
Hokuriku Electric Power Company and The Chugoku Electric Power Co.,Inc.
These companies have an abundance of expertise, experience and a proven track record in operation, maintenance, etc., of boilingwater reactor (BWR) nuclear power stations, plus an abundance of technologies accumulated through joint research with otherelectric power companies, etc. The technologies are furthermore eﬀective for the project management of IRID projects. The
companies are capable of applying their development results broadly, based on knowledge at nuclear power stations.
8. Hokkaido Electric Power Co., Inc., The Kansai Electric Power Company, Incorporated, Shikoku Electric Power Company,
Incorporated, Incorporated and Kyushu Electric Power Co., Inc.
These companies have an abundance of expertise, experience and a proven track record in operation, maintenance, etc., ofpressurized-water reactor (PWR) nuclear power stations, as well as an abundance of technologies accumulated through joint
research with other electric power companies, etc. The technologies are eﬀective for management of IRID projects. The companies
are capable of applying their development results broadly, based on knowledge at nuclear power stations.
9. The Japan Atomic Power Company
The Japan Atomic Power Company is engaged in demolition work at the Tokai Power Station for the decommissioning of Japan'sﬁrst commercial nuclear power plant. Its mission is to act as a pioneer in demonstrating safe and rational decommissioning andpromotes the establishment of remotely-operated demolition technology, material quantities and radioactive evaluations, as wellas the treatment and disposal of radioactive waste, and the development of project management systems, etc. It has also
accumulated useful technologies for future decommissioning.
10. Electric Power Development Co., Ltd.
The company has an abundance of expertise, experience and a proven track record in construction of boiling water reactor (BWR)
nuclear power stations. It also possesses a great deal of technologies accumulated through joint research with other electric
power companies etc. The technologies are eﬀective for the management of IRID projects. The company is capable of applying
their development results broadly, based on knowledge at nuclear power stations.
11. Japan Nuclear Fuel Limited
The company has business experience concerning uranium enrichment, waste burial and management, reprocessing, mixed oxide
fuel production and transportation. The company also possesses an abundance of technologies accumulated through joint
research with other electric power companies, etc. In particular, their extensive expertise, experience and proven track record intreatment and disposal of radioactive waste are eﬀective for project management such as formulating what is to be implemented
in IRID projects.

3

Project Period

Supplementary Project Cost
BudgetAmount*2(FY)

Evaluation of Long-term Structural
Integrity of Fuel Assemblies Removed
from the Spent Fuel Pool

(1) Development of technology for evaluation of long-term
structural integrity of fuel assemblies(2) Basic test for long-term integrity, etc.

April 1, 2015March 31, 2017

2014

Development of Technology for
Remotely Operated
Decontamination Inside Reactor
Buildings(1) Development of decontamination equipment for high places(2) Development of decontamination equipment for upper ﬂoors(3) Conceptual study of decontamination of basement ﬂoors, etc.

October 17, 2014March 31, 2016

2013

Development of Repair and Water
Leakage Stoppage Technology forLeakage Points Inside the PrimaryContainment Vessel(1) Development of technology for repair and water leakage
stoppage of the Primary Containment Vessel(2) Formulation of plans up to ﬁlling the Primary Containment
Vessels with water, etc.

July 23, 2014March 31, 20162013

Full-scale Test for Repair and Water
Leakage Stoppage Technology forLeakage Points Inside the PrimaryContainment Vessel(1) Full-scale test etc., of devices, equipment, etc., for repairingand stopping water leakage at the lower part of the PrimaryContainment Vessel(2) Preparation of equipment etc., required for the full-scale test(3) Study of equipment etc., required at mock-up facilities andmaintenance of the equipment, etc.

July 23, 2014March 31, 2016

2013

Development of Technology for
Investigation Inside the PrimaryContainment Vessel(1) Plan of investigation inside the Primary Containment Vessel(2) Plan of development of investigation equipment(3) Development of investigation equipment, etc

October 15, 2014March 31, 2016

2013

Development of Technology for
Investigation Inside the Reactor
Pressure Vessel(1) Formulation and updating of investigation and development plans(2) Element test and feasibility evaluation of technology forinvestigation by drilling the upper part(3) Study and feasibility evaluation of technology for sampling of fueldebris, etc.

September 9, 2015March 31, 20162014

Upgrading the Identiﬁcation ofConditions Inside the Reactor throughApplication of Severe Accident
Analysis Code, Data on the Actual
Reactor and Reactor Internals, etc.

(1) Estimation of behaviors of fuel debris and ﬁssion products throughaccident progression analysis(2) Comprehensive analysis and evaluation of conditions inside thereactors using accident progression analysis and actual data, etc.

April 10, 2015March 31, 2016

2014

Development of Technology for
Detection of Fuel Debris in theReactor(1) Implementation of small-scale demonstration test
(spatial resolution: about 1 m)
(2) Design, production of a detector system(spatial resolution: about 30 cm), etc.

June 20, 2014December 31, 2015

2013

Project for Development ofFundamental Technologies for
Retrieval of Fuel Debris and Internal
Structures(1) Comprehensive coordination of each element test and analysis of
the element test results(2) Element test required for determining the feasibility of methods toretrieve fuel debris and internal structures, etc.

Septermber15, 2015March 31, 2017

2014

Project of Upgrading Approach and
System for Retrieval of Fuel Debris
and Internal Structures(1) Organization of plant information toward determining a policy of
retrieval of fuel debris and internal structures(2) Study of approaches, systems and equipment for retrieval of fueldebris and internal structures, etc.

Septermber15, 2015March 31, 2017

2014

Development of Technology forCollection, Transfer and Storage ofFuel Debris(1) Formulation of plans of investigation and research for transfer andstorage of damaged fuel(2) Study of storage systems of fuel debris(3) Development of safety evaluation methods(4) Development of technology for collection of fuel debris(5) Development of technology for transfer and storage of canisters, etc.

April 1, 2015March 31, 2017

2014

Development of Technology for
Evaluating Integrity of the Reactor
Pressure Vessel/Primary Containment
Vessel(1) Evaluation of feasibility of the submersion method, based on theseismic integrity of the Reactor Pressure Vessels/Primary Containment
Vessels(2) Simple evaluation of the earthquake-resistant strength of reactor
components, based on repairs (water stoppage) of the Reactor
Pressure Vessels/Primary Containment Vessels(3) Development of corrosion control measures(4) Upgrading of prediction accuracy of corrosion amount for a long term(5) Corrosion impact evaluation of the pedestal, etc.

July 25, 2014March 31, 2016

2013

Development of Technology for
Criticality Control in Fuel Debris
Retrieval(1) Development of criticality evaluation methods(2) Development of methods of monitoring critical approach(3) Development of recriticality detection technology(4) Development of criticality prevention technology, etc

April 1, 2015March 31, 2016

2014

Fuel Debris Characterization(1) Estimation of properties of fuel debris in the reactor(2) Characterization using simulated debris(3) Development of element technology for analysis of fuel debris, etc

April 1, 2015March 31, 2017

2014

R&D for Treatment and Disposal of
Solid Waste(1) Integration of R&D results (Presenting the basic policy of treatment and disposal)(2) Characterization(3) Study of treatment of radioactive waste and policy on long-term storageof radioactive waste(4) Study of disposal of radioactive waste, etc.

April 1, 2015March 31, 20172014

*1 Projects listed in IRID's "Project Plan"

16

Main Contents of the Project

Project Name(as of the end of November 2015)*1(Subsidy Rate)

700 million JPY（100%）
2 billion JPY(50%)

4 billion JPY(50%)

3.7 billion
JPY (100%)

3 billion JPY(50%)

1 billion JPY(50%)

1 billion JPY(100%)

580 million JPY(50%)

4 billion JPY(100%)

1.5 billion JPY(100%)

800 million JPY(50%)

1.4 billion JPY(50%)

300 million JPY(50%)
2 billion JPY(100%)

2 billion JPY(100%)*2 Project cost amounts and subsidy rates are cited from numbers written in the Application Guidelines

17