Mid-to-Long-Term Roadmap for
Decommissioning of Fukushima Daiichi NPPand International Cooperation

Kentaro Funaki
Director, Office for the Restoration from Nuclear Accident
Agency of Natural Resources and Energy (ANRE)
Ministry of Economy, Trade and Industry (METI), JapanSide event by Government of Japan
at 56th IAEA General Conference, Sep 17, 2012

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1. Mid-to-Long-Term Roadmap for
Decommissioning of Fukushima Daiichi NPP
2. R&D Roadmap
3. International Cooperation

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Mid-to-Long-Term Roadmap and Primary Targets“Government and TEPCO Council on Mid-to-Long Term Response for
Decommissioning”, which was established last December, adopted the “Midto-Long-Term Roadmap for TEPCO’s Fukushima Daiichi Units 1 to 4.” ThisRoadmap defines the term of decommissioning into three phases, and outlines
major milestones of on-site work and R&D projects

Phase 1: From the completion of Step 2 (last December) tothe commencement of fuel removal from spent fuel pools（Target: Accomplish in 2 years）

Phase 2: From the end of Phase 1 to the commencement offuel debris removal from RPVs
(Target: Accomplish in 10 years)

Phase 3: From the end of Phase 2 to the end of thedecommissioning process（Target: Accomplish within 30 to 40 years）

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Roles of the Government and TEPCO on
the Mid-to-Long-Term Roadmap
 Role of the Government
 METI/ANRE•Oversee the progress of the Roadmap and TEPCO’s onsite work
•PDCA Management of the R&D program NISA (Regulatory Authority)•Prepare necessary regulatory systems•Ensure safety

 Role of TEPCO•On-site work, consistently ensuring human resources
and project management, as the responsible site operator

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Organizational Structure
Government and TEPCO Council onMid-to-Long Term Response for Decommissioning
Co-Chair：Mr. Hosono, Minister for the Restoration from and Prevention of Nuclear Accident, Cabinet Office
Mr. Edano, Minister of Economy, Trade and Industry (METI)

Vice-Chair ： Parliamentary Secretary of Cabinet Office, Vice Minister of METI, and President of TEPCO
Members ： Agency of Natural Resources and Energy(ANRE), The Nuclear and Industrial Safety Agency (NISA)Management Board
Co-Chair:Mr. Sonoda, Parliamentary Secretary of Cabinet
OfficeMr. Kitagami, Vice Minister of METI
Mr. Aizawa, Executive Vice-President of TEPCO
Adviser : Ms. Kamimoto, Vice Minister of MEXT
Members: METI/ANRETEPCO
NISA (Nuclear and Industrial Safety Agency)
MEXT (Ministry of Education, Culture, Sports,Science and Technology)
JAEA (Japan Atomic Energy Agency)
Toshiba
Hitachi-GE

R&D Management Headquarter
Chair: Mr. Kitagami, Vice Minister of METI
Vice-Chair: Mr. Sonoda, Parliamentary Secretary ofCabinet Office
Ms. Kamimoto, Vice Minister of MEXT
Members : METI/ANRE
TEPCO
MEXT
AEC (Atomic Energy Commission)
JAEA
AIST
CRIEPI
Toshiba
Hitachi-GEand a couple of academic advisors

6Major Schedule of the Roadmap
TEPCO’s on-site work and government-led R&D program areclearly differentiated.
Some of the on-site work will proceed in a phased process,based on R&D results.
At the key points for judgment on the progression tosubsequent processes, there will be further deliberation andjudgment, including additional R&D and revision of process
and task content. These are set as Holding Points (HPs).

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9Major Areas in the Roadmap
The Management Board supervises the progress ofthe Roadmap. The major areas the following: Circulating Water Injection Cooling Accumulated Water Treatment Reducing of Environmental Radiation Dose Improvement of Work Environment
 Fuel Retrieval from Spent Fuel Pool

 Preparation for Fuel Debris Removal
 Radioactive Waste Treatment and Disposal

10The Roadmap Updated in July
The “Government and TEPCO Council on Mid-toLong Response for Decommissioning” held its
second meeting on July 30, 2012, and adopted theupdated roadmap, which: reflects the latest version of TEPCO’s “Facility OperationPlan” for increasing reliability of equipment and site facilities
 highlights major outcomes to date clarifies short-term targets and milestones in response to
the progress of the roadmap

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Major Areas in the R&D Roadmap
 Long-term management of retrieved fuel from SFP
 Preparation of fuel debris removal
 Equipment/device development
 Core status assessment and analysis
 Fuel debris characterization and management
 Radioactive waste treatment and disposal
 Remote-controlled technologies as a common base

Examination of waste treatment anddisposal

Stability of contaminated water
processing

Analysis of fuel debris properties
Fuel debris measuring andmanagement measures

Fuel debris treatment technologies

Assessment of simulated fuel debrischaracteristics
Accident development analysis

Fuel debris criticality control
Fuel debris storage technologies
Removal of fuel debris and structuresin the reactor
Investigation of the RPV interior

Investigation of the PCV interior
Sealing and repair in the reactor
building/PCV

Identification of leak areas in thereactor building/PCV

PCV/RPV soundness evaluation

Planning to Reduce overall dose

Remote decontamination of thereactor building interior

Damaged fuel processing
technologies[Specific R&D projects]

Long-term stability of fuel assemblies

FY2012FY2011-task force forremotetechnologies

Secretariat[Overall management]

Working teamfor spent fuelpool countermeasures

ReportExamination
ReportExamination
ReportExamination

Working team for preparation of fuel debris removal
SWT for fueldebrisSub-working team (SWT) for
propertyequipment/device development, etc.
assessment
and treatment
preparation

Workingteam forradioactive
waste
treatment
anddisposal

SWT for core statusassessment andanalysis

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Organizational Structure for Managing R&D Projects
R&D Management Headquarter14

Three Principles for Implementing the R&D
Program Address on-site technological needs
 Government involvement and support
 Open and flexible framework for implementation
with support from international engineering andscience communities

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R&D Roadmap (Example)
Phase 1
Period by when fuel removal from SFP starated
FY ２０１２

FY ２０１３
Within 2 years

FY ２０１４

FY ２０１５(Prior Period)

Phase 2Phase 3

Period by when fuel debris removal started

Period till end ofdecommissioning

FY ２０１６

FY ２０１７(Middle Period)

FY ２０１８

FY ２０１９FY ２０２０(Late Period)

FY ２０２１
Within 10 years

Fuel Debris Removal Start(First unit) ▽After 30-40
After 20-25 yearsyears

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Milestones for Fuel Debris Removal (Defueling)
Phase 1

Phase 3Phase 2

Within 10years

2012 2013
Leaking Location(Lower PCV) HP
Identified?

Step 2:PCV Investigationfrom outside

Sufficient
HP Water Levelachieved?

Leaking Location
HP (Upper PCV)
Identified?

Step 5:PCV Internal Inspectionand Sampling

EnoughHP Water Levelachieved?

After
20-25years

Defueling
HP MethodDeveloped?

Step 8:RPV Internal Inspectionand Sampling▽Open RPV

Step 3:Lower PCV
Repair

Step 4:PCV Half
Flooding

Step 1: Reactor Building Decontamination

Step 6:Upper PCV
Repair

Step 7:
PCV/RPVFull Flooding

Step 9:
Defueling

Debris processing /disposal methods HP
developed?
HP ：Technical holding points.

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Step 1: Reactor Building Decontamination
Spent Fuel
Pool
Fuel debris

RPVPCV

Torus

From water
treatment facilities
Decontamination
Devices
To watertreatment
facilities

Decontamination of the area is essential to following procedures.
• Research and technology development of high-pressure washing,coating, scraping, etc.
• Combined usage of shielding
Major Challenges and Difficulties:- High dosages (~ 5 Sv/h ).
- Obstacles such as rubble scattered in R/B.
- Smaller space due to the compact design of BWR4

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Steps 2&3: Identification and Repair of the PCV Leakage Points
Spent Fuel
Pool

Spent Fuel
PoolCooling Water

Penetrations
RPV

Cooling Water

RPV

Investigation
Device

PCV

PCV

Torus

Leakage

To watertreatment
facilities

Torus

Stopping
Leakage

RepairDevice
The intake source
for cooling waterloop will beswitched to thetorus (from T/B)
after stopping interbuilding leakage

Leaking locations will be investigated from outside the PCV
and will be repaired
Major Challenges and Difficulties:• High dose rate and humidity of PCV inside.
• Most "suspicious locations" are underwater with poor visibility.
• Repair work has to be conducted while highly radioactive coolingwater is running for continuous fuel cooling19

Steps 4&5: Flooding of the Lower PCV, and Inspection & Sampling
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Spent Fuel
Pool

Spent Fuel
Pool
RPV
Flooding

Water
cooling/
treatment
facilities

RPV
CameraSampling

PCV

PCV
Torus

Observation
DeviceTorus- Once the PCV gains its boundary, water will be filled (flooding)- The distribution and characteristics of the fuel debris will beinvestigatedMajor Challenges and Difficulties:• High dose rate, limited accessibility and poor visibility.
• Leak-tight penetration is required for the investigation device once
PCV flooding is achieved.
• Subcritical assessment

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Steps 6&7: Upper PCV repair, Flooding of Entire Reactor
WellContainer
Overhead Crane

Spent Fuel
Pool

Penetrations

Repair Devices(remote control)

Flooding

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RPV Upper CoverSpent Fuel
Pool

Repair Devices

From water
treatment facilities
RPVTo water treatment
facilities

Torus
PCV
Torus

1) Filling entire PCV/RPV with water after repairing upper PCV
2) R/B container and overhead crane will be installed for defueling.
3) RPV/PCV top heads will be removed after sufficient water is attained

Major Challenges and Difficulties:• High dose rate, limited accessibility.
• Seismic stability after flooding has to be maintained considering water mass.
• Prevent radioactive substances release from PCVs
• Subcritical assessment

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Step 8: Internal RPV Inspection& Sampling

Truck

Spent Fuel
Pool

Expansive Pipe

Debris Container

Camera, Cutting,Drilling, Gripping, andSuction Devices

PCV
Torus

Condition of RPV internal and Fuel debris will be investigatedMajor Challenges and Difficulties:• High dose rate, limited accessibility and poor visibility.
• Development of necessary devices• Subcritical assessment• Store the removed debris

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Step 9: Defueling from RPV and PCV
Fuel Debris Container

Removal

PCV
Torus

Fuel debris and RPV internal structure will be removed
Major Challenges and Difficulties:•Fuel debris is assumed to have fallen onto the complicated RPV bottom structure(BWR structures are much more complicated than those of PWRs)•Debris may have fallen even out of the RPV (debris remained in PRV in TMI-2)•Diversity of neutronic, mechanical and chemical properties of debris as a mixture
with different types of metals and concrete•Subcritical assessment• Store the removed debris

23R&D Issues for Radioactive Waste Processing andDisposal
1. Properties Investigation and Characterization• Properties differ from conventional waste, such as rubble, sludge, anddecontaminated waste liquid (nuclide composition, chloride content, etc.)• Basic information needs to be assessed for the development of each technologies

Examples of differences with conventional waste• Main nuclides: Co-60, C-14, etc.
→Fukushima Daiichi: Cs-137, Sr-90, etc.
• Sodium concentration is 5 times that of the TMI casedue to 50-90% contamination by seawater→Lower Cesium absorption performance, increased
waste generation• Presence of sludge and other materials of unknown
chemical composition→Need to identify these materials through analysis
Outputs• Radioactive concentration of each type of nuclide• Component content• Physicochemical characteristics, etc.

Sludge sample(made by JAEA)

Zeolite sample

The installation of a hot lab near 1F must also
be considered, as large volumes of high-dose,
untransportable samples are expected to begenerated accompanying decontaminationand fuel debris removal.

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R&D Issues for Radioactive Waste Processing andDisposal
2. Long-term storage technologies• Impact of chloride (corrosion) and high radioactivity (heat, hydrogen, surface radiation)• Duration of storage: how long should it be?
• Is treatment necessary before storage?
Cross section B , A, C

Facility for secondary waste storage after water
treatment (example)
Water inlet

A-A cross section
Temperature
distribution

B-B cross section
Hydrogen
distribution

Flotation as aresult oftemperature
increaseWater outlet

Temperature of zeolite layer
Approx. 170˚C max.

Evaluation of temperature and hydrogen distribution in a KURION
absorption vessel (by JAEA)

Output: Long-term storage method for each type of waste

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R&D Issues for Radioactive Waste Processing andDisposal
3. Processing technologies• Can technologies used for existing processing technologies be applied?
Examples of waste package

Drums

Examples of solidification

Square vessels
Basic flow in a cementing facility

Outputs• Treatment methods for storage• Methods for production of waste packages• Performance of waste packages

Source: Japan Atomic Industrial Forum Inc. (ed.), Radioactive
Waste Management: Technical Development and Plans in Japan,
July 1997, p.81.

26R&D Issues for Radioactive Waste Processing andDisposal
4. Disposal technologies• Fundamental new technologies on the existing disposal concept• Extract and address issues related to safety evaluation and find a solution

Existing concept
Low-level radioactive waste

High-level
radioactive waste

Trench disposal Pit disposal Yoyusindo Geologicaldisposal disposal Ground

Example of an engineered barrier(Yoyusindo disposal)
Backfill with clay-mixed soil
Waste package(1.6 x 1.6 x 1.6, metal vessel)

surfaceNon-solidified waste(concrete, metals,etc.)

Solidified waste(uniform solids,metals, etc.)

Pit disposal: Waste packages (drums,etc.) are placed in a concrete structure(pit) installed several meters below theground surface, integrally solidified
with a cement-based filling material,and buried.

Concrete pit (0.7m)
Low diffusion layer(0.6m)

Activated metals,
resin, TRU waste, etc.
High-level
radioactive waste(vitrified waste, TRUwaste, etc.)

Low permeability
layer (1m)Approx. 13.5m
Approx. 18m

Output: Waste disposal methods (required burial depth, construction of an engineered barrier, etc.)

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Technological challenges in conducting a wide array of
government-led R&D projects require wisdom and expertisefrom international communities, which indicate potential areas
for international cooperation.
The knowledge and technologies gained from these R&D
projects will be valuable common assets for the improvementof decommissioning processes and become a knowledge
base for further enhancing safety at nuclear facilities all overthe world.
Government and TEPCO Council on Mid-to-Long-Term
Response for Decommissioning held an International
Symposium on March 14, 2012 in Tokyo. This event wasorganized in cooperation with the IAEA and OECD/NEA.

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１．Challenges for Defueling:1) Development of Remote Equipment and Devices
 Short-termMonitoring devices for the R/B under high dose enviroment• remote-controlled UAVs, etc.

Sensing devices for water surface in the S/C and PCV toidentify location of leaks
Remote-controlled robots running in the water to repair leaks• Identify self location in the water• Automatic treatment of long-length communication cable• Sensor for the shape and water-flow

 Mid-term
PCV repair devices and defueling equipment

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１．Challenges for Defueling:2) Accident analysis for evaluating the core status
 Short-term
Accident progression analysis and benchmark study, byusing existing and improved integral severe accident codes(cf. TMI-2 experience of OECD/NEA joint research)
Database/information portal to make accident data readily
available to the international community.
Assessment on the validity of severe accident codes andleading greater confidence in the code predictive capabilities
 Mid-termFurther analysis applying various models and methodologies
Collection of physical data during sampling and defueling31

１．Challenges for Defueling:3) Characterization and Sampling of Fuel Debris
 Short-term
Simulated fuel debris for evaluating its characterization
Creating and updating database by making use of theexperience of the TMI-2 debris study
Management and storage of fuel debris, and development of
a new accountancy method
 Mid-term
Sampling and analyzing actual fuel debris
Deployment of defueling equipment, devices, and storage.

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2. Challenges for Radioactive Waste Treatment

 Short-termDevelopment of analysis techniques and methods for thecharacterization of accident-origin solid waste• Pre-treatment of solid radioactive waste• Simplified and standard methodologies• Regulatory and institutional framework

Management and processing secondary waste storage after
water treatment
 Mid-termExploring possibility for building a research center forinternational collaborative research program
Researchers/experts exchanges with international community

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3. Challenges for Improving the Work Environment Short-termTechnologies and systems to reduce the doses of workers• Dose reduction management, including shielding• Improving materials for workers’ suits

Studying methodologies for increasing human performance• Advancing human health and performance innovations forseverely challenging environments• Designing a better work environment

 Mid-term
Address human resource needs for the mid-to-long term

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Conclusion
In addressing the challenges we are facing, we arecommitted to the international community to make available
information and data from the accident and decommissioning
processes, through international collaboration projects.
With lessons learned from the Fukushima Daiichi accident, It
is our responsibility to work together with international
community for further improving decommissioning processes
and knowledge-base for the safety at nuclear facilities.

Please visit our website:www.meti.go.jp/english/earthquake/nuclear/decommissioning