Integrated management ofknowledge and expertise innuclear decommissioning gatheredfrom around the world

2016-2017

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

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

Our Principles 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 able to be
applied on site at the Fukushima Daiichi NPS at the early stage
in the face of numerous extremely difficult technologicalchallenges.

CONTENTS
Message from the President ――――――――――― 1◆Role of IRID ――――――――――――――――― 2・Decommissioning Schedule in the
Mid-and-Long-Term Roadmap◆Scope of WorkR&D for Nuclear Decommissioning ―――――― 4
IRID R&D
Overview of IRID R&D Projects
Major R&D Topics
Promotion of Cooperation with RelevantInternational Organizations ―――――――――― 10・International Advisors
・Joint Research with Overseas Research Institutions
・Technical Cooperation with Overseas Nuclear
Organizations
・Overseas Public Relations
Human Resources Development for R&D ――― 12
・R&D in Collaboration with Universities
・Human Resources Development through Small
Workshops with Universities◆Data
Organization Profile ―――――――――――――― 14
・Technology Advisory Committee / Expert Advisors
・IRID Member Technical Capabilities
List of Government Subsidized R&D Projects
Conducted by IRID ――――――――――――― 17

2. We build an optimal R&D structure through cooperation with
relevant organizations as well as IRID member organizations
and gathering knowledge from Japan and abroad.
3. We actively promote efforts to develop and secure humanresources who will comprise the next generation of thoseworking in nuclear decommissioning and related technologies,
including efforts to collaborate with universities and research
institutions.
4. We strive to release information on our R&D activities 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 (center of excellence)
through our R&D activities and contribute to acceleration of thedecommissioning of the Fukushima Daiichi NPS and
improvement of technological capabilities in the international
community.

2016-2017

Message from the President
Since it was established in August 2013, the International Research Institute for Nuclear
Decommissioning (IRID) has been fully commit ted to research and development oftechnologies required for addressing the urgent issue of decommissioning the Fukushima
Daiichi Nuclear Power Station (NPS). Since the Nuclear Damage Compensation andDecommissioning Facilitation Corporation (NDF) was reorganized from the Nuclear Damage
Liability Facilitation Fund in August 2014, the roles of the four major entities involved in thedecommissioning of the Fukushima Daiichi NPS have been clarified; the NDF that is
responsible for formulating decommissioning strategies and R&D plans, Tokyo Electric Power
Company Holdings, Inc. (TEPCO) that is responsible for on-site operations, and IRID in its
capacity of leading R&D for decommissioning technologies and the Japanese Government.
These four key players work closely together in decommissioning efforts.
As a result, the situation inside the reactor has been gradually ascertained through our R&D
work and the development of technology for investigation inside the Primary Containment
Vessel (PCV) such as the use of cosmic-ray muons to detect fuel debris inside the reactor.
Meanwhile, major technical issues to be tackled in order to retrieve fuel debris have beenpresented.
Under these circumstances, the milestones for fuel debris retrieval were clarified in thegovernment-led“Roadmap towards the Decommissioning of TEPCO’s Fukushima Daiichi
NPS”(hereinafter called the Mid-and-Long-Term Roadmap) revised by the government in
J u n e 2 015 . I n a d d i t i o n, t h e N D F r ev i s e d t h e“ Te c h n i c a l S t r ate g i c P l a n 2 016 f o r
Decommissioning of the Fukushima Daiichi NPS”to provide technical evidence for the
Mid-and-Long-Term Roadmap in July 2016. The R&D for fuel debris retrieval is about to entera crucial phase.
Over five years have passed since the Fukushima Daiichi NPS accident occurred in the wakeof the Great East Japan Earthquake. A large number of residents in Fukushima Prefecture
are still living as evacuees and the Japanese public is concerned about the decommissioningof the Fukushima Daiichi NPS. To enable evacuees to return home as soon as possible andease public anxiety, it is essential that decommissioning proceeds safely and steadily. IRID iscommitted to its responsibility of making steady achievements in R&D for decommissioning,and gathering knowledge from all over the world, conducting R&D projects required for
effective and efficient decommissioning according to the purpose of its establishment. We
sincerely appreciate your guidance and continued support.

December 2016
International Research Institute for
Nuclear Decommissioning

Hirofumi Kenda, President

1Role of IRID
IRID is a body comprised of 18 organizations that are key
players engaged in the research and development required fordecommissioning the Fukushima Daiichi NPS.

A structure has been established in which three organizations
cooperate closely together as one team and where each rolefor decommissioning the Fukushima Daiichi NPS is clarified:
the NDF formulates strategies and R&D plans fordecommissioning, TEPCO's Fukushima Daiichi
Decontamination and Decommissioning (D&D) Engineering
Company performs on-site operations, and IRID conducts R&D.

IRID intends to bring together decommissioning and otherrelevant technologies required for decommissioning all nuclear
power stations in Japan in future. However, at the present time,
we are addressing R&D for decommissioning of the Fukushima
Daiichi NPS as it is the most urgent issue at this time, as
outlined in the government-led Mid-and-Long-Term Roadmap.

For its part in this structure, IRID, through its R&D, actively
works on risk reduction, ensuring safety, environment
preservation, etc., which are required for the decommissioningof the Fukushima Daiichi NPS and help relieve the anxiety felt
by people in Fukushima Prefecture and the rest of Japan.

In order to undertake the unprecedented and extremely difficult– even by global standards – task of decommissioning the
Fukushima Daiichi NPS, IRID continues to gather knowledge
from around the world to conduct efficient and effective R&D
required for decommissioning.

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

TEPCO

Government(Fukushima Daiichi D&D Engineering Company)
Progress management

Steady implementation of decommissioning

Report● Formulation of the Mid-and-Long-Term● Fuel removal from spent fuel pool
● Contaminated water management● Storage and management of rubble and waste,etc.
● Ensuring safety & quality and improving work
environments, etc.

Roadmap, etc.

Ad
R&D needs

vic

Re

ea

nd

po

rt

gu

ida

R&D implementation
pool

Sharing progress status
and issues to be solved● R&D for preparation of fuel debris
retrieval● R&D for treatment and disposal ofradioactive waste
Re

Pro

Nuclear Regulation Authority
Implementation of safety regulations

2

po

jec

rt r

t co

Strategy formulation andtechnological support● Formulation of the
Mid-and-Long-term Strategy● Progress management andtechnical support for key issues● R&D planning and progress
management, etc.

esu

st (

lts

sub

sid

y)

Funds for R&D

ReportReport and application

Supervising and review

Nuclear Damage Compensation
and Decommissioning Facilitation
Corporation (NDF)

Budget allocation

nce

IRID
● R&D for fuel removal from spent fuelPresenting key issues

ReportR&D proposal
Practical applications ofresearch achievements andproviding information

Policy making and progress management

2016-2017

Decommissioning Schedule in the Mid-and-Long-Term Roadmap“The Mid-and-Long-Term Roadmap towards the Decommissioning of TEPCO's Fukushima Daiichi NPS”
(Mid-and-Long-Term Roadmap) has been formulated based on current knowledge and analysis of conditions for each Unit at
the Fukushima Daiichi NPS. The third revision of the Roadmap was issued on June 12, 2015. The revised
Mid-and-Long-Term Roadmap provides a target schedule of the decommissioning under the premise that it is subject to berevised according to future on-site conditions and R&D results, etc.
The Roadmap divides the decommissioning period into three phases. Currently, R&D is taking place to prepare for fueldebris retrieval in the second phase. IRID is also visually confirming conditions inside the reactor using cosmic ray muon
tomography and investigating inside the Primary Containment Vessels (PCVs) utilizing robots. Conditions inside the reactor
have previously only been estimated through analysis codes. Through this work, we have gradually collected data thatenables us to study technological difficulties and explore new approaches to proceed with R&D for decommissioning.

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

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

November 2013

Phase 1

Period up to thecommencement offuel removal fromspent fuel poolPhase 3

Period up to the commencementof fuel debris retrieval

Period up to
the completion of
decommissioning

Target: within 10 years after Step 2
completion

・Decision on fuel debris retrieval policy for each
Unit (Target: 2017)
・Finalization of fuel debris retrieval methods forthe initial Unit (in the first half of FY 2018)
・Start of fuel debris retrieval at the initial Unit
(within 2021)

Target: within 2 years
after Step 2
completion

After 30 to 40 years

Phase 2(completed)・Accomplishment ofcold shutdown state・Significant reductionof radioactive material
releaseDecember 2021～

Target: 30 to 40 years
after Step 2
completion

Present
R&D Structure

T EPCOIRID is engaged in fundamental researchthrough to practical application oftechnology.

Research institutions, including IRID
Ministry of Economy, Trade and Industry(METI): Project of Decommissioning
and Contaminated Water Management, etc.

JAEA (Japan Atomic Energy Agency)

Basic research

Fundamental
research

Application
development

・ On-site requirements
・ On-site conditions
・ Regulatory requirements
・ Performance guarantee

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

・ Specific researchfacilities and equipment
・ Fundamental
・Acquisition of basic technology data
findings
・ New ideas
・ Human resource
development and education

Integration of knowledge
and researchers

Universities and research institutions

Practical application<Resource> The above charts were created based on the Mid-and-Long-Term Roadmap (Third revision), June 12, 2015.

3

Scope of Work 1:

R&D for Nuclear Decommissioning
IRID R&D
IRID conducts research and development to proceed with decommissioning of the Fukushima Daiichi NPS, according to theMid-and-Long-Term Roadmap. The key area is the advancement of decommissioning strategy. IRID is therefore studying whether
there are any other appropriate approaches, how to reduce risks, etc., while exploring how to achieve an optimal end state throughtie-ups with TEPCO and other relevant organizations.
Our main decommissioning R&D projects are:“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”.

(Reference)

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

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

Spent fuel pool*2(Photo provided by the Japan Atomic Energy Agency(JAEA))

Reactor Pressure Vessel(RPV)*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＊1 Fuel debris: Lava-like fuel containing material that is produced under＊5 Drywell (D/W): Safety structure that is comprised of a flask-shaped＊2 Spent fuel pool: A water tank that stores spent fuel that is inserted in a

＊6 Suppression chamber (S/C): Doughnut-shaped equipment that storeshigh temperatures through melting with control rods and structures inside
the RPV, after which it cools and re-solidifies.
rack under water until decay heat generated from fission products
decreases. This tank is located on the top floor of the reactor building.

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

fuel assemblies. This container can resist high-temperature water andhigh-pressure steam generated by the energy released by nuclear fission
inside. The RPV is housed within the PCV together with coolingequipment＊4 Primary Containment Vessel (PCV): A steel container that houses theRPV, cooling equipment, and other devices that perform importantfunctions. This prevents radioactive substances from being released into
the outside environment under abnormal plant conditions, such as whena 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 consists of a flask-shaped drywell, adoughnut-shaped suppression chamber and eight vent pipes connecting
the drywell and the suppression chamber.

4

Primary Containment Vessel (PCV)*4
container that houses equipment, including the RPV, and contains
radioactive substances at the time of an accident.

water located in the basement of the reactor building. Condenses vapor
generated in the case of reactor piping breakage and prevents excesspressure from building up. It also serves the important function of providing
a water source for the Emergency Core Cooling System (ECCS) in thecase of a loss-of-coolant accident.

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

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

2016-2017

Fuel Debris
Units 1-3 at the Fukushima Daiichi NPS lost all power supply at the time of the accident, disabling water injection into the RPV. This
resulted in the fuel inside the RPVs overheating without water to cool it down and it is thought temperatures rose above 2,000
degrees Celsius - high enough to melt the fuel rods.
It is assumed that the overheated fuel melted along with control rods and other structural components inside the RPVs and themelted 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."
The shape and location of fuel debris can only be estimated at the present time, since radiation levels inside the PCVs are still
extremely high and workers cannot gain access.
The decommissioning process demands fuel debris retrieval and stored under safe and stable conditions.

Study of Options for Fuel Debris Retrieval Methods
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 for workers.
However, in order to submerge fuel debris under water, it is necessary to fill the upper part of the PCVs that have been affected by thesevere accident at the Fukushima Daiichi NPS with water. There are many developmental challenges in repairing the PCVs andstopping water leakage. It is therefore assumed that it may be difficult to fully submerge fuel debris in water. Given these points, theNuclear Damage Compensation and Decommissioning Facilitation Corporation (NDF) suggested, in its Technical Strategic Plan 2015
for Decommissioning of the Fukushima Daiichi Nuclear Power Station of Tokyo 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 exposedto the air.
The NDF also showed three fuel debris retrieval methods to be focused on as options that consider water levels in the PCVs and fueldebris access direction (top and side), based on the viewpoints of the progress status and feasibility of technology development andrisk management.

Three Representative Methods for Fuel Debris Retrieval of Primary Focus - Conceptual Diagrams

Submersion̶Top entry method

Partial submersion̶Top entry method

Partial submersion̶Side entry method

Assuming in-core structures above the fueldebris are removed

Assuming in-core structures above the fueldebris are removed

Assuming equipment and other objects outside
the RPV pedestal in the PCV are removed<Source> NDF“Technical Strategic Plan 2015 for Decommissioning of the Fukushima Daiichi Nuclear Power Station of Tokyo Electric Power Company”

5Scope of Work 1: R&D for Nuclear Decommissioning

Overview of IRID
R&D Projects

R&D for Fuel Removalfrom the Spent Fuel Pool

Technology for Investigation
Technology for Investigation
inside the RPV
Position of opening holes

Opening holes
from the top

Technology for
Investigation inside
the PCV
Development ofinvestigation robots
inside the PCV・Evaluation of long-term structural
integrity of fuel assemblies(corrosion tests under assumed
storage environments for removed
fuel assemblies and investigationof actual fuel assemblies)
・Study of methods of processing
damaged fuel and evaluation of
impact on damaged fuel when it isprocessed

Steam dryer

Position of opening holes

Corrosion evaluation

Investigation of thecondition of stored
fuel

Opening holes
from the top

O
Shield plug

Spent
fuel
pool

Upper grid

Elemental test condition for opening holes using
partial simulated reactor internals test device

Primary Containment
Vessel (PCV)

Technology for
Detection of
Fuel Debris
Technology for Detectionof Fuel Debris

Muon
detector
Simulated image

Image capturedby muon tomography

Technology for Investigation and Analysis(Characterization) inside the Reactor
ShroudIdentifying
Conditions inside
the ReactorCorethrough
Molten Core
Application of
SupportSevere Accident Core
Plate
Analysis Code,Particulate Debris
Data on the Actual Metal Layer
Molten Pool
Reactor, andSolidified
Reactor Internals.
Crust

Improvementof the physicalphenomenon
model

6

Suppression
Chamber
Torus room (S/C)

RPV Wall

Radiation HT Model
between Shroud
and RPV Wall
Jet Pump
Fuel Support Pieces
CR Guide Tube
CRD Housing

Lower Plenum Debris
Bed Layering Model

Vessel Failure
Mechanism Model

Thermal Conduction from Debris
to CRD Housing, Radiation HT
between CRD Housing

PCV Floor
Sump Pit

Bulk Cooling Model for the Early
Phase of Water Addition on
Top of Corium

Corium Leakage through Sump
Piping Erosion Shape Model

Vent pipe

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

Surface solidification

Core component

Concretecomponent

Concrete
Thermally-deteriorated concrete(embrittlement)

Molten concrete(Molten vitreous state)

Pyrolysis gas(Mainly H2O)

M

2016-2017

Technology for Fuel Debris Retrieval
Technology for Evaluating the Integrity of the RPV/PCV
Buildingequipment
coordination
behavior analysis

Building behavior analysis(building damage simulation)

Model creation

・Water level
・Base ground motion Ss
・Damage to equipment
・Impact of corrosion

Organizing
loading
conditions

Criticality Control Basic Concept
PCV submersion

Equipment
strengthassessment

Criticality
controlmethods

Assessment
conditions
・Allowable value
・Amount of corrosion
・High-temperaturestrength deterioration

Technology for Collection, Transfer and Storage of Fuel Debris
Reactorbuilding
Maintenancecell
Debrisretrieval storage cell

Carry out / in(added)Carry out cell

Building forcarrying out debris

Pure water

Debris retrieval

Boric acid water solution

Submerging gradually while
Same as leftconfirming subcriticality condition●Criticality
prevention byboric acid

Retrieving while
confirming subcriticality
condition●Monitoring subcriticality of criticality
approach detection system nearby debris●Criticality prevention by soluble/insoluble
neutron absorbing material

Criticality
prevention
system(PS)

Submerging graduallyat limited speed while
confirming subcriticality
condition

Mitigation of
impact at thetime ofcriticality (MS)Criticality detection by FP gamma detector
system using gas sampling, and terminating
criticality by injecting boric acid solution

Same as left

Technology for Retrieval of Fuel Debris and Reactor Internals

Storage canister
handling cell

Storagefacility

Storage incanister

Operating floor

Cleaning ofcanister

Storage of canisterin transport cask

Carry out oftransport cask

Technology for Decontamination
and Dose Reduction

Technology for Remotely-operated
Decontamination in the Reactor Building

Technology for
Treatment and Disposalof Solid Waste

Work cart

Activity concentration（Bq/cm3）

Fuel debris
retrieval

Existing ALPS: Coprecipitated iron
Existing ALPS: Carbonate
Additional ALPS: Carbonate

Analysis data ofradioactive waste(slurry) generated
by ALPS operation

Reactor Pressure
Vessel (RPV)

n

Muo

n

Muo

Relay cart
Support cart

Decontaminationof upper floors
Decontaminationof high places

Transport cart

Upper floor decontamination equipment(mounted suction/blast decontamination equipment)

Absorber vessel

Saltwater tankPressure filtering test
device to examine
dehydration treatmentof ALPS slurry

Full-scale absorber vessel to be
used for various absorption tests

Decontaminationof low places

Technology for Repair
and Water Stoppageof the PCV

Repair Technology for
Water Leakage Section of the PCV

Full-scale Mock-up Test

Simulated S/Ctest device

Preparation for testing

ResearchandAdministrative
Building

Reinforcement material placing in
Unit 1 S/C support column (green area)

Turbid water treatment facility
Test Building

Work floor

Heating and feedwater facility

Mock-up transfer rail

Full-scale test device

Water stoppage material(concrete which does notseparate in the water)←Placing
pipe

10m

Verification test for evenly balanced flow
behavior for strengthening S/C support column(1/1 scale: Simulated Unit 2 and 3)

Down-comer long-distance fluidity testing7

Scope of Work 1: R&D for Nuclear Decommissioning
Major R&D Topics
Cosmic Ray Muon Tomography inside the Reactor
Muon particles (muons) are generated by the collision of cosmic rays with the earth's atmosphere; each second, about one muon particle falls on our palms.
Muons are characterized by their ability to easily penetrate materials. Some muons, however, cannot penetrate substances because they lose a part of theirenergy due to interaction with electrons in the process of penetration. Others are deflected from their initial direction due to interaction with nuclides. In
collaboration with research institutions all over the world including Japan*, IRID has developed a transmission method system to detect the aforementioned
phenomenon and other system using the scattering method that detects the latter muon phenomenon. We successfully visualized inside the reactor at
Fukushima Daiichi NPS Unit 1 by the transmission method in 2015, and at Unit 2 in 2016. As a result, we determined that some fuel remains in the Unit 1
reactor core where it originally existed, and high density materials that are assumed to be fuel debris were identified at the bottom of the Unit 2 RPV.
* High Energy Accelerator Research Organization (KEK), Los Alamos National Laboratory (LANL), etc.

Cosmic ray■ Fuel debris measurement in the Unit 2 reactor by transmission method*N
Photographing
direction

System installation position(west side of the reactor building)(Small measurement device, approx.
1m x 1m x height 1.3m)

Muon
detector

Unit 2 reactor building(first floor cross-section)*One pixel size: Equivalent to approx. 25cm in the reactor cross-section.

Height OP (m)About one muon particle falls on a size ofhuman hand on the earth each second.

Ground contact area is five times smaller thanfor the Unit 1 measurement system; therefore,
the measurement system can be placed closer
to the reactor building and thoroughly measure
the bottom of the RPV.

Muon

North

Measuring existence and density of materials at the incoming
muon direction based on the measurement amount of muonsfalling on the reactor (image)

Horizontal distance (m)SouthStructure of the lower
part of the RPVHigh density materials that are assumed to be fuel debris at the bottom of the RPV were identified.
*TEPCO Holdings Inc. conducted the measurement at Unit 2 as a part of an IRID project.

Investigation Technology Inside the Primary Containment Vessel (PCV)■ Robots Designed forInvestigating Inside the Unit 1 PCV(shape-changing robot)

Investigation of basement outside of
Unit 1 pedestal (image)
Camera for travelling(two cameras on both sides)

Winch

Cable
・Composite cableincluding optical fiber：Lens direction：Light direction
Dosimeter, underwater camera
Size (target): approx. 20mm

*This figure describes an image based on aconcept studied by IRID. It might be changed
according to an actual investigation.

8■ Investigation Robot inside the Unit 2 PCVIRID has developed a robot to investigate inside the pedestalof the Unit 2 PCV. After entering the pedestal, the shape ofrobot changes into a shape like a scorpion raising its tail to
improve its field of view.

2016-2017

Repair Technology for Water Leakage Sections in the Reactor Containment Vessel
Overview of water stoppage sections■ Water Stoppage Testing by injecting concrete into S/C
Full-scale concrete injection testing for water leakage stoppage using S/C mock-up
In order to fill the PCV with water, water stoppage treatment whereby concrete isplaced into the S/C has been developed to stop water in vent pipes connected to
the PCV, and also to prevent water release from the S/C to other systems.
A water stoppage test that involved injecting filling concrete into the S/C wasconducted to verify water stoppage capability on October 15, 2016.
Test devices incorporating a strainer, quencher and holes (50 mm) that simulated
actual damage conditions in the surface shell of S/C were manufactured. For the
purpose of verification of the water stoppage capability of these devices anddamaged holes, concrete was placed into the test devices. Concrete moved underwater and gradually accumulated in damaged holes, quencher, and strainer, inthat order. It was ultimately successful in stopping water flow.

Overview of repair sections in lower part of the PCV (Ex.1F-2)

QuencherWater flow route from D/Wside MS vacuum breaker to
S/C

Water stoppage
in vent pipes

Strainer
Water stoppage inside
S/C by injecting filling
Sections where waterleakage is to be stopped

Leaking water in the systemfrom water stoppage sections

Damaged parts of S/C surface shell
Water leakage route from
S/C to torus room

Test facility (installed behind the sheet curing)
Strainer
Quencher

Full scale testing

Test facility during injection of concrete■ Full-scale Mock-up Test at the JAEA Naraha Remote
Technology Development Center
In order to verify on-site applicability as the last phase of the technology development,
full-scale mock-up testing for the three following techniques are planned to take placeat the JAEA Naraha Remote Technology Development Center. A full-scale mock-up
test of one of these methods (workability verification test for strengthening S/C support
columns) has been underway at the JAEA Naraha Remote Technology Development
Center since November 2016.
①Vent pipe water stoppage technology
This technology is intended to stop water leakage from the PCV through vent pipes, themain path that water leakage takes, in order for submersion to take place.
②Water stoppage technology by filling of suppression chamber (S/C)
This technology is intended to stop water leaks at piping ends (quencher andstrainer) and damaged parts of S/C (assumed to be belowφ50mm).

Lowering hose operation
into a mock-up torus room

Strainer before injection of concrete③Technology for strengthening S/C support columns
This technology development is designed for seismic strengthening of S/C support
columns, as the total weight of S/C is expected to increase due to the injection offilling materials for water stoppage.
Units 2-3

Units 1

Filling of reinforcement
materials

Filling of reinforcement
materials

S／C

S／C

Candidate material: mortar which does not separate in water

Remote operation via monitor

Mixer agitator pressure pump to
inject reinforcement materials (mortar)

Information
For more information on the R&D IRID
is undertaking, please visit our website
or see brochures we have published.

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

IRID Annual Research
Report 2015

Robots9

Scope of Work 2:

Promotion of Cooperation with Relevant International Organizations
IRID has striven to enhance relationships with relevant international organizations and experts in order tocollect expertise from all over the world under an“open structure”management policy.

International Advisors
The International Advisor committee consists of three nuclear
experts from abroad. This advisory committee was establishedwith the purpose of advising the IRID Board of Directors onorganizational operation and management.
International Advisors provide advice on future challenges andrequired improvements as well as leading discussion oninternational efforts and management approaches.

■ Members
Mr. Lake Barrett (USA):

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

The Fourth IRID International Advisors Meeting (November 30, 2016)** From left: Prof. Brownridge, Mr. Echavarri, and Mr. Barrett

Mr. Luis E. Echavarri (Spain):

Former Director General of the OECD/NEA (experienced in theInternational Nuclear Safety Group (INSAG))
Professor Melanie Brownridge (UK):

Head of Technology, the Nuclear Decommissioning Authority(NDA)■ Meeting Schedule
・1st : January 9-10, 2014
・2nd : November 17-19, 2014
・3rd : December 2-4, 2015
・4th : November 30-December 2, 2016

Joint Research with Overseas Research Institutions
IRID is collaborating with overseas research institutions to produce and analyze large-scale simulated debris using uranium.

■ National Nuclear Center of the Republic of Kazakhstan (NNC)
Heterogeneous solidified
substances are produced bymixing and melting tens ofkilograms of uranium fuel andcladding tube material, andcausing a reaction of this withmetal, such as reactor
components.
Test samples of the solidified
substance are used to study
conditions when mixed withmetal or ceramics, andboundary zone properties.

(1) Rock shape (slow-cooling condition)

Fuel debris

Part where
stainless steel
has melted

Stainlesssteel

Production of metal ceramic melt-solidification using UO2 at the Kazakhstan NNC■ French Atomic Energy and Alternative
Energies Commission (CEA: Commissariat
a l'Energie Atomique et aux Energies
Alternatives)
Using test products produced in Molten Core-ConcreteInteraction (MCCI) testing that the CEA conducted usingtens of kilograms of uranium, analysis to determine
characteristics of the MCCI products was conducted.

10Rock-shaped
solidification(2) Powdery and granular shape (water cooling condition)
Powdery/granular
Fixed ring
shaped solidification
Fuel debris

Upper oxide crust

Corium/Concrete interface(vertical direction)
Corium/Concrete interface(horizontal direction)

Corium oxide
phase
Continuous
metallic phase
Siliceous concrete

2016-2017

Technical Cooperation with Overseas Nuclear Organizations
We are promoting technical cooperation with overseas nuclear organizations that have experience in nuclear
decommissioning and handling damaged fuel.

■ Paks Nuclear Power Plant (Hungary)Discussion focused on the handling of
damaged fuel and safety concepts whenstoring removed fuel. Results were utilized
for development of fuel debris canisters.

■ Sellafield Ltd. (U.K.)
Information on damaged fuel handling,storage methods and criticality control
after removal of fuel as well as generaldecommissioning activities was
exchanged.

■ International Atomic Energy Agency (IAEA) Headquarters (Vienna, Austria)

Concepts of decommissioning
activities for the Fukushima
Daiichi NPS were discussedwith an IAEA expert teamconsisting of engineers fromvarious countries. We were also
advised how to collect technicalinformation required for the
future.

■ Idaho National Laboratory (U.S.A.)
IRID participated in the TMI workshop to exchange
knowledge and experience gained in TMI-2 and how
this may be applied to the Fukushima Daiichi NPS. We
are utilizing this information in furtheringdecommissioning activities at Fukushima Daiichi.

■ Argonne National Laboratory (U.S.A.)
Information on the reaction andproducts of MCCI testing was
exchanged with engineers withextensive knowledge of the reaction
between fuel debris and concrete.

Overseas Public Relations
IRID introduces results of research and development at forums etc., organized by relevant internationalorganizations.

IAEA International Conference on Advancing the Global Implementation of
Decommissioning and Environmental Remediation Programmes (May 23, 2016)

Japan-United States Forum on Fukushima Recovery and Decommissioning“Fukushima(
Recovery Forum”) (February 24, 2016)11

Scope of Work 3:

Human Resources Development for R&D
Nuclear decommissioning is a long-term project that may last 30 to 40 years. It is therefore essential that we have young
people engaging in nuclear decommissioning activities.
IRID is committed to promoting development of the next generation that will be involved in nuclear decommissioning R&D.

R&D in Collaboration with Universities (Achievements)
IRID has been developing technology for improving theoperability of remotely operated decontamination devices
in cooperation with various universities.

Technical
challenges● Easy-to-understand display of conditions around robots● Improving operability of multi-joint manipulator● Reducing of labor required for remote control operations
and cart positioning

Improvement of capability of determining surrounding conditions

Improvement of capability of determining surrounding conditions[Yamashita Laboratory, University of Tokyo]

Development of technology toenable easy-adjustment of image
correction, and flexibly respond tochange for the type, installation
position, and direction of cameras.

[Tsubouchi Laboratory, University of Tsukuba]

Development of a system to enable the clear display of 3D measurement dataobtained by mapping area around robots via cameras and laser sensors.

Simulated overview image
captured by Super Giraffe

Simulated overview image
captured by MEISTeR

Improvement of operability

3D mapping data captured by Super Giraﬀe(under development)[Yokokohji Laboratory, Kobe University]

Development of control interface toconvey immediate self-motion*
motor commands to improve
operability of manipulator.

Fixing theposition andposture of hand tip* Movement to change
the manipulator's overall
shape with position ofhand tip and base fixed

Changing posture(Artist rendition of shoulder
moving forward and backward)

Displayed surrounding environment using sensor-captured
3D data and camera-captured images

Reducing labour required for operation of remote control and cart positioning[Matsuhira Laboratory, Shibaura Institute of Technology]

Establishment of
mechanism for theeasy processing ofdata between specificdevices connected ona network of multiple
controllable devices.

Examples of self-motion movement of manipulator with nine degrees of freedom

Formation of system for coordinating and controlling
movement of multiple moving carts

Human Resources Development through Small Workshops with Universities
1. Small workshop with universities
IRID is promoting activities toenhance communication with young
researchers and cooperate with
universities partly engaged in national
decommissioning projects.

2. PR activities at universities andresearch institutes, etc.

Small workshop with University of Tsukuba(February 9, 2016)

Small workshop with Shibaura Institute ofTechnology (September 26, 2016)

Nuclear Science and Technology for Decommissioning intensive
course at Tohoku University (September 15, 2016)

Lecture at National Institute of Technology,
Fukushima College (October 27, 2016)

IRID is actively involved in thedevelopment of human resources by providing information through visits to universities and research institutes.

Lecture at the Oarai Nuclear Summer School(August 1, 2016)12

2016-2017

3. IRID Symposium
Entitled‘Develop the Future for Decommissioning’, the FY2016 IRID symposium (held in Tokyo) was intended to develop young researchersand engineers who will engage in future decommissioning activities, Approximately 400 people attended the symposium.
A site tour at the Fukushima Daiichi Nuclear Power Station and JAEA Naraha Remote Technology Development Center was conducted the dayprior to the symposium. The tour was attended by students and post graduate students participating in the symposium, and by Atomic Energy
Society of Japan Kanto/Koshinetsu branches member universities.

Lecture at the symposium

Robot exhibition

Facility visit

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

Presentation at Atomic Energy Society of Japan 2016 Fall
Meeting (September, 2016)

Lecture at Environmental Radioactivity Measures & Radioactive Waste
Disposal International Exhibition - RADIEX2016 (October, 2016)

Exhibition at Science Agora 2016 (November, 2016)

Exhibition at Robot Festa Fukushima 2016 (November, 2016)

Information ― IRID glossary is available on our website ―The IRID Glossary consists of the‘Glossary of Nuclear
Technical Terms’(containing approx. 2,500 terms) and‘Nuclear
Abbreviation Glossary’(containing approx. 12,000 terms).
We appreciate the opportunity to provide the IRID Glossary tocompanies and students engaged in decommissioning projects allover the world, and also contribute to promoting decommissioning
activities related to the Fukushima Daiichi NPS.
IRID Glossary URL▶ http://irid.or.jp/glosy_index.html(Note) This system is available only in Internet Explorer; it is not operational in other browsers.

IRID Glossary search system

13

Data
Organization Profile
1. NameTechnology Research Association, International Research Institute for
Nuclear Decommissioning (IRID)
2. Headquarters
5F, 3 Toyokaiji Building, 2-23-1 Nishi-Shimbashi, Minato-ku, Tokyo
105-0003, Japan
TEL: +81 3 6435 8601 (main)
3. Date of Establishment
August 1, 2013
4. Scope of Work・R&D for nuclear decommissioning
・Promotion of cooperation on nuclear decommissioning with relevantinternational 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 and Technology
Manufacturers:
TOSHIBA CORPORATION
Hitachi-GE Nuclear Energy, Ltd.
Mitsubishi Heavy Industries, Ltd.
ATOX Co., Ltd.
Electric utilities, etc.:
Hokkaido Electric Power Co., Inc.
Tohoku Electric Power Co., Inc.
Tokyo Electric Power Company Holdings, Inc. (TEPCO)
Chubu Electric Power Co., Inc.
Hokuriku Electric Power Company
The Kansai Electric Power Company, Inc.
The Chugoku Electric Power Co., Inc.
Shikoku Electric Power Company, Inc.
Kyushu Electric Power Co., Inc.
The Japan Atomic Power Company
Electric Power Development Co., Ltd.
Japan Nuclear Fuel Limited
6. Board of Directors
President: Mr. Hirofumi Kenda
Vice President: Dr. Tamio Arai
Executive Director: Mr. Atsufumi Yoshizawa
Directors: Mr. Hirotsugu Fujiwara, Mr. Hiroto Uozumi,
Mr. Ei Kadokami, Mr. Kunikazu Kishimoto,
Mr. Masahiro Seto, Mr. Mamoru Hatazawa,
Mr. Jun Matsumoto, and Mr. Yoshinori Moriyama
Auditor: Mr. Atsushi Isobe
7. Number of Employees
859* (excluding directors)* Including a number of staff engaged in research conducted by IRID.
(as of October 1, 2016)<Establishment of Organization>
August 1, 2013: Establishment approved by the Minister of Economy,
Trade and Industry under the Act on Research andDevelopment Partnership
August 8, 2013: Operation starts and holding of IRID General Meeting
and Board of Directors<Organizational Role>
IRID is dedicated to R&D activities to address the urgent issue of
decommissioning the Fukushima Daiichi NPS in cooperation with the
Nuclear Damage Compensation and Decommissioning Facilitation
Corporation (NDF) and Tokyo Electric Power Company Holdings, Inc.
(TEPCO) in order to strengthen fundamental technologies for futuredecommissioning, and also develop, accumulate, and upgrade related
technologies.
<Organizational Structure>
・IRID was established in accordance with the Act on Research andDevelopment Partnership with an initial membership of 17organizations, with a General Meeting as the highest decision-making
authority and Board of Directors as executive body. Currently, there are
18 member organizations in total after ATOX Co., Ltd., joined in May
2015.
・Eleven directors and one auditor have been appointed. Some directors
are from non-IRID member organizations (i.e., universities and private
sector companies).
・The International Advisors and the Technology Advisory Committees
have been established to obtain the latest in global expertise forpromotion of decommissioning.
・IRID is comprised of three departments: the R&D Strategy Planning
Department (responsible for planning, human resource development,international cooperation, and public relations); the R&D Management
Department (responsible for R&D management); and, theAdministration Department. In addition, there are four project teams
engaged in specific research areas: the Radioactive Waste Treatment
and Disposal Technology Group; the PCV Investigation, Repair &Structural Integrity Assessment Technology Group; the Debris Retrieval
Technology Group; and, the Reactor Interior and Fuel Debris
Evaluation Technology Group.

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

120

120

80

46
40

FY 2013 (from August)

14

148

FY 2014

FY 2015

2016-2017

IRID Organizational Structure

General Meeting
Board of Directors

International Advisors

Technology Advisory Committee

R&D Strategy Planning Department
Planning & Management GroupR&D Management Department

Administration Department

Naraha Development
Center

Accounting GroupInternational & Academia Cooperation Group
Corporate Communication GroupRadioactive Waste Treatment
and Disposal
Technology GroupPCV Investigation,
Repair & Structural Integrity
Assessment Technology Group

Fuel Debris Retrieval
Technology Group

Reactor Interiorand Fuel Debris Evaluation
Technology Group(as of May 30, 2016)

Technology Advisory Committee / Expert Advisors
IRID established the Technology Advisory Committee to obtain advice from highly knowledgeable external experts who
provide a wide range of opinions from broad viewpoints, including advice on technologies that are extremely difficult torealize based on the latest information, planning of whole projects, and human resources development, etc.
Expert Advisors provide opinions that are reflected in our R&D planning, implementation methods, and evaluation of
results for each project.

The 6th Technical Advisory Committee (August 4, 2016)

Visit to robot development facility by IRID Expert Advisors (May 22, 2015)** 'TEMBO' equipment to remove shielding blocks and iron plates

15

Data

IRID Member Technical Capabilities
1. Japan Atomic Energy Agency (JAEA)
JAEA is the sole comprehensive nuclear research and development institute in Japan. It contributes to recovery approaches andreconstruction efforts related to the Fukushima Daiichi NPS accident, bringing specific technical expertise to what it considers as its mostimportant project.

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; material andchemistry; electronics and manufacturing; geology; and measurement standards. The AIST possesses the broad scientific knowledge andtechnical capabilities required for implementing IRID projects.

3. TOSHIBA CORPORATION (TOSHIBA)As plant manufacturer, TOSHIBA has the know-how, experience, and track-record in the development of decontamination technology,
inspection of storage containers, and establishment of repair and remote control technologies related to the Project of Decommissioning andContaminated Water Management.

4. Hitachi-GE Nuclear Energy, Ltd. (HITACHI –GE)HITACHI-GE is capable of developing applicable technology for a mid-and-long term approaches towards the decommissioning of the
Fukushima Daiichi NPS. Furthermore, the organization possesses a coherent structure for the planning, designing, manufacturing,
construction and maintenance of nuclear power stations, and provides operator training.

5. Mitsubishi Heavy Industries, Ltd. (MHI)
MHI brings expertise that encompasses all facets of nuclear power plants (pressurized-water reactor (PWR) type), from basic planning todesign, manufacturing, construction, maintenance, and repair. The company has accumulated sufficient technology in each business area,
including nuclear fuel, new reactor plants, and the nuclear fuel cycle, can effectively engage in project management when planning R&D, andhas the capacity to widely utilize, apply, and develop obtained results.

6. ATOX Co., Ltd.
ATOX possesses practical capability in the operation, inspection, maintenance, decontamination, and radiation control of general nuclear
facilities, with extensive know-how, experience and achievements in these fields. ATOX also has gamma irradiation facilities and highcapability of developing applicable decontamination technologies.

7. Tohoku Electric Power Co., Inc., Tokyo Electric Power Company Holdings, Inc., (TEPCO), Chubu Electric Power Co.,
Inc., Hokuriku Electric Power Company and The Chugoku Electric Power Co., Inc.
These utilities possess extensive know-how, experience and achievements in the operation and maintenance of boiling water reactor (BWR)
nuclear power stations, in addition to accumulated technologies gained through joint research with utility companies. These technologies areapplicable to the management of IRID projects. Development results can also be widely applied based on the company’s knowledge of andexperience with nuclear power stations.

8. Hokkaido Electric Power Co., Inc., The Kansai Electric Power Company, Inc., Shikoku Electric Power Company, Inc.,and Kyushu Electric Power Co., Inc.
These utilities possess extensive know-how, experience and achievements in the operation and maintenance of pressurized water reactor(PWR) nuclear power stations, in addition to accumulated technologies gained through joint research with utility companies. These
technologies are applicable to the management of IRID projects. Development results can also be widely applied based on the company’sknowledge of and experience with nuclear power stations.

9. The Japan Atomic Power Company (JAPC)The Japan Atomic Power Company is engaged in demolition work at the Tokai Power Station, Japan's first commercial nuclear power plant, aspart of the site’s decommissioning. JAPC is committed to verifying safe and effective decommissioning activities as a pioneer in the field, andto promoting the establishment of remotely-operated demolition technology, evaluation of material quantities and radioactivity, treatment anddisposal of radioactive waste, and development of project management systems, accumulating applicable technologies for futuredecommissioning through these efforts.

10. Electric Power Development Co., Ltd.
Electric Power Development Co., Ltd., possesses the expertise, experience, and track record in the construction of boiling-water reactor(BWR) nuclear power stations, and has accumulated various technologies through joint research with utility companies. These technologies
can be effectively applied in project management for IRID projects and the company has the ability to widely apply development results basedon its on-site knowledge of nuclear power plants.

11. Japan Nuclear Fuel Limited
Japan Nuclear Fuel Limited has experience uranium enrichment, waste burial and management, reprocessing, mixed oxide fuel production
and transportation, and has accumulated various technologies through joint research with utility companies. In particular, the wide-ranging
expertise, experience, and track record it has related to radioactive waste treatment and disposal technologies can be effectively leveraged inproject management, such as determining implementation plans for IRID projects.

16

2016-2017

List of Government Subsidized R&D Projects Conducted by IRID
Subsidy Project of Decommissioning and Contaminated Water Managementin the FY2014 and the FY2015 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

1

2

3

(as of the end of November 2016)*1

Supplementary Budget

Project Maximum Cost *2(Subsidy Rate)

April 1, 2015March 31, 2017

FY2014(Conducted in FY2015 - FY2016)

700 million JPY(100%)(1) Estimation of properties of fuel debris in the reactor(2) Characterization using simulated debris(3) Development of element technology for fuel debris analysis

April 1, 2015March 31, 2017

FY2014(conducted in FY2015-FY2016)

2 billion JPY(100%)

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

September15,
2015-March 31,
2017

FY2014 (conducted in FY2015FY2016)

1.5 billion JPY(100%)

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

September 15,
2015March 31, 2017

FY2014(conducted in FY2016-FY2016)

4 billion JPY(100%)Development of Technology for Collection,
Transfer and Storage of Fuel Debris(1) Investigation and formulation of research plan for transfer andstorage of damaged fuel(2) Study of fuel debris storage systems(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

FY2014(conducted in FY2016-FY2017)

800 million JPY(50%)

Upgrading Level of Grasping State inside
Reactor(1) Integrated analysis and evaluation of conditions inside thereactor(2) Estimation/evaluation of behavior and characteristics of fueldebris and ﬁssion products for integrated analysis and evaluation(3) Management of R&D

April 1, 2016March 31, 2018

FY2014(conducted in FY2016)
Budget allocation is not yet determined.

2 billion JPY(100%)Development and Management of Evaluation
Method of Seismic Performance/Impact of RPV
and PCV(1) Construction of safety scenario for possible large-scale earthquake(2) Development of seismic performance and impact evaluation
method for safety scenario(3) Upgrading of safety scenario(4) Management of R&D

April 18, 2016March 31, 2018

FY2014 (conducted in FY2016)
Budget allocation is not yet determined (FY2017)

1 billion JPY(100%)Development of Corrosion ControlTechnology
for RPV and PCV(1) Evaluation of effectiveness and impact of corrosion control
measures(2) Study of fuel debris storage system(3) Management of R&D

April 1, 2016March 31, 2017

FY2014(conducted in FY2016)

1 billion JPY(50%)

Development of Technology for Criticality
Control in Fuel Debris Retrieval(1) Establishment of criticality evaluation methods(2) Development of technology for criticality control in fuel debris
retrieval(3) Management of R&D

April 1, 2016March 31, 2018

FY2014(conducted in FY2016)
Budget allocation is not yet determined (FY2017)

1 billion JPY(50%)

Development of Technology for Investigation
inside the Primary Containment Vessel(1) Formulation and upgrading of investigation plan and development plan
(2) Development of equipment and systems to access and investigate speciﬁc area
(3) On-site demonstrations(4) Management of R&D

April 1, 2016March 31, 2018

FY2014(partly in FY2016)
FY2015(conducted in FY2016 and FY2017)

8 billion JPY(50%)(1) Consideration and planning of process leading to water
replenishment in the PCV(2) Development of the PCV lower part repair technology
Development of Repair Technology for Leakage(3) Development of the PCV upper part repair technology
Sections in PCV(4) Consideration of environmental improvement concept for
application of repair construction method in actual equipment(5) Management of R&D

April 1, 2016March 31, 20182015 (conducted for FY2016 andFY2017)

6 billion JPY(50%)

Full-scale Testing of Technology for Repairing
PCV Leakage Points(1) Full-scale tests of PCV lower part repair technology① Strengthening S/C support columns② Stopping water in vent pipes③ Water stoppage by injecting ﬁlling in S/C(2) Conﬁrmation of integrity of reinforcement materials and water
stoppage materials after testing(3) Maintenance of VR data for preliminary simulation test(4) Management of R&D

April 1, 2016March 31, 2018

FY2014(partly conducted in FY2016)
FY2015(conducted in FY2016 and FY2017)

4 billion JPY(100%)Development of Technology for Investigation
inside the Reactor Pressure Vessel(1) Establishment and upgrading of the investigation/development plans(2) Conceptual design of corrosion control system(3) Development and selection of reactor core investigation
method(4) Design and construction plan of integrated investigation
system(5) Management of R&D

April 1, 2016March 31, 2018

FY2015(conducted in FY2016 and FY2017)

2 billion JPY(50%)

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

April 1, 2015March 31, 2017

FY2014(conducted in FY2015 and FY2016)

2 billion JPY(100%)

Project Name

Project Summary

PeriodEvaluation of Long-term Structural Integrity ofFuel Assemblies Removed from the Spent FuelPool(1) Development of technology for evaluation of long-term structural integrity of fuel assemblies(2) Basic test for long-term integrity, etc.

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

17

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

Published: March 2017

この印刷物は再生紙を利用しています。