Nuclear Damage Compensation and Decommissioning Facilitation Corporation

Current Status of Strategic Planfor Solid Waste Management ofFukushima Daiichi
July 3, 2017

Kazuyuki Kato
Nuclear Damage Compensation andDecommissioning Facilitation Corporation
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International safety principles
on radioactive waste management
 All steps prior to disposal (predisposal) shall be managed safely andsecurely to ensure the safe disposal of waste.
 Processing shall be based on appropriate consideration of thecharacteristics of the waste and of the demands imposed by thedifferent stages in its management (pretreatment, treatment,conditioning, transport, storage, and disposal).
 If waste processing is performed before the waste disposal
requirements are set, it must be remaining possible to process thewaste in a way which meets those requirements once they havebeen set.
Predisposal Management

Segregation

Storage

Processing

Pretreatment, Treatment,Conditioning

Storage

Disposal2

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Recent Advances in Solid Waste Management
 Reduction of solid waste generation is continued.
Incineration of used protective clothing in
Incinerator started to reduce storage volume.
 Waste management plan is reviewed regularly.
 Waste characterization based on collected
analytical data.

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Solid Waste arising from Accident at Fukushima Daiichi
 Waste Characteristics; Different from ordinary waste due to accident⇒ Characterization is important Limited Data (especially for long-lived nuclides) is available because ofcontamination over wide area and high dose environment
 Forecast of waste generation is difficult because decommissioning activities will beclarified gradually
Scatter/dispersion

Water treatment equipment[Debris/felled trees, etc.]

DebrisFallentrees

Soil○ Large quantity and spread overwide area○ Insufficient past experience ofprocessing and disposing oftrees and soil

Contaminatedwater[Secondary waste stemming fromtreatment of contaminated water]

Secondary waste[Waste from Fuel debris Retrieval]○ Large quantity and high dose
○ Access is difficult at present andcollecting raw waste is difficult.

Pipes forreplacement, reservoir,etc.

○ Insufficient past experience ofprocessing and disposal○ Collecting raw waste is difficult.
○ Quantity of some waste and nuclides
can be estimated depending on thefeature of equipment.

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Temporary storage volume of rubble etc.
(As of April 30, 2017)5

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Temporary storage volume of Secondary Waste fromWater Treatment (As of May 18, 2017)6

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Improvement of Waste Management Conditions
 TEPCO HD made plan for Improvement of Waste Management Conditions
based on forecast of waste generation during next 10 years.
 In order to reduce risks during storage, the volume of rubbles will be reduced asmuch as possible, then the wastes will be transferred to inside storage buildings.
Finally, outdoor tentative storage will be eliminated by around 2028.

Forecast of Waste Generation7

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Samples from R/B and T/B have taken (results)
Inside of Reactor Buildings

Inside of RPV• Analyzed rubble and boring cores sampled from 1st and 5thfloor of Unit 1 and 2, and 1st floor of Unit 3 (47 Samples)• No sample so far

Inside of PCVs

Basement of Turbine Building

R/B• Analyzed stagnant water
sampled from Unit 2 and 3(4 samples)
T/B

Spent Fuel Pool

• Analyzed sand and sludge sampledfrom the first basement of Unit 1(5 samples)• Analyzed sludge and water sampledfrom stagnant water in thebasement of Unit 1 (8 samples)• Analyzed sand gravel
sampled from Unit 4(2 samples)

Around Reactor Buildings andtemporal storage facilities• Analyzed rubble around Unit 1, 3 and 4,and rubble from soil covered temporalstorage (25 samples)

Basement of Reactor Building• No sample so far

・Approximately 300 samples have taken・Characterization is insufficient8

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Tendencies of Contamination on R/Bs and T/B
Inside of RPV

Inside of Reactor Buildings（High level contamination is expected tobe occurred with fuel debris and activation
products. No sample so far.）• Fission products (e.g. 137Cs, 90Sr), alpha emitters (e.g.
Pu) and activation products (e.g. Co) were detectedfrom samples from 1st and 5th floor of Unit 1 and 2,
and 1st floor of Unit 3.

Inside of PCVs
• Tendency of higher radioactivity
concentration ratio of 60Co and alphaemitters against 137Cs was observed forstagnant water of Unit 2 and 3 compare
to that of downstream (CentralizedRadiation Waste Treatment Facility)

Basement of Turbine Building
R/B• Tendency of higher radioactivity concentration ratioof 90Sr against 137Cs was observed compare tosamples from inside of R/Bs.
• Tendency of containing Cs, Sr and alpha emitters wasobserved for sedimented sludge.
T/B

Spent Fuel Pool
• Tendency of higher radioactivity
concentration ratio of 60Co (activationproduct) against 137Cs was observed for
Unit 4 compare to samples from insideof other R/Bs.

Around Reactor Buildings• Tendency of similar nuclide
composition of contamination wasobserved for rubble around Unit 1 and3 with samples from inside of R/Bs.

Basement of Reactor Building（Contamination is expected to beoccurred by stagnant water.
No sample so far.）Tendencies of contamination werepresumed based on results ofradiological analysis of samples.
It is necessary to keep on
confirming the tendencies throughsampling and analyzing data
aftertime.

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Improvement of Predisposal Management
 Safe predisposal management is essential to ensure the safe
disposal.
 Collection and storage of waste are basis.
 Stabilization of slurry, sludge etc. is favorable.
 Processing should be performed to meet waste disposal
requirements.
Complete Pictureof 1F Waste

Current status of 1F

Segregation

Storage

DisposalRequirements

Processing
Requirements
Processing

Pretreatment, Treatment,
Conditioning

Storage

DisposalMore stable or safer
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Issues to clarify Complete Picture of 1F Waste
 Promotion of Characterization
Continuation of Sample Collection andAnalysis(sampling from high dose area)
Optimization of Characterization
Representativeness of sample
R&D of Analytical Method
Consideration of Effect by Non-radioactive Material
 Clarification of Waste AmountConfirmation of Decommissioning PlanSelection of Processing Method11

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Improvement of Analytical Capability
 Radioactive Material Analysis & Research Facility

 Analysis facility for radioactive wastes, fuel debris, etc.
 Installed analysis devices to obtain data that can contributeto the appropriate processing of radioactive waste.
 Installed equipment that can obtain basic data of fuel debris,which are high level radioactive waste.
Building No.2
for higher level materials

Administrationbuilding

Source: TEPCO website and photo archive

Building No.1
for Lower level wastes

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Action Policy for Solid Waste Management (draft) Thorough Containment and Isolation
 Processing is to ensure Safe Disposal→ Focus on Predisposal Management because theRealization of Disposal is impossible at this timeReduction of amount of solid waste
Promotion of characterization
Through storage Preceding Processing Technologies in consideration ofDisposal
Stabilization & immobilization may be possibly required before thewaste disposal requirements are set→ Minimize the possibility which does not meet those requirements
once they have been set.

Promotion of R&D based on Action Policy
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Concluding Remarks
 Characteristics of contamination has partiallyestimated based on collected analytical data.
 Focus on characterization, safe storage, andpreceding processing technologies until
disposal would be realized.
 Propose to contribute to the basic concept ofprocessing and disposal for radioactive solid
wastes based on international safety principals
and issues arising from R&D (TechnicalStrategic Plan 2017)14

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Thank you for your attention!

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