The 1st International Forum on the Decommissioning of the Fukushima Daiichi Nuclear Power Station-Commemorating 5 years since the Great East Japan EarthquakeApr.10-11, 2016

Overview of Radioactive Waste Management in JapanAnd R&D Activities for Fukushima Daiichi

Toru OGAWA
Collaborative Laboratories for Advanced Decommissioning
Science (CLADS)
Japan Atomic Energy Agency (JAEA)
Tokai, JapanThe 1st International Forum on the Decommissioning of the Fukushima Daiichi NPS, Apr. 10-11, 2016

Contents

 Classification and Disposal Concepts ofRadioactive wastes in Japan Disposal Practice and Plan in Japan
 R&D of Fukushima Daiichi Radioactive
WastesThe 1st International Forum on the Decommissioning of the Fukushima Daiichi NPS, Apr. 10-11, 2016

1

Contents

 Classification and Disposal Concepts ofRadioactive wastes in Japan Disposal Practice and Plan in Japan R and D of Fukushima Daiichi Radioactive
WastesThe 1st International Forum on the Decommissioning of the Fukushima Daiichi NPS, Apr. 10-11, 20162

Classification of Radioactive Waste in JapanClassification

ExampleOrigin of Waste

Disposal(example)

High-level radioactive waste (HLW)

Canister

Reprocessing facilities

Geological

Lowlevelradioactivewaste(LLW)

Relatively
High Radioactive
WasteControl Rods, CoreInternals

Power Reactors

Sub-surface

RelativelyLower
Radioactive
Waste

Liquid waste,
Filters,
Used Equipment,
Expendables

Very Low-Level
Radioactive
Waste

Concrete, Metals

Waste Containing Transuranic
Nuclides(TRU Waste)

Parts of Fuel Rod,
Liquid waste,
Filters

Reprocessing Facilities,
MOX Fuel Manufacturing
Facilities

GeologicalSub-surface
Concrete Pit TypeUranium Waste

Expendables,
Sludge,Used Equipment

Enriched and Fuel
Manufacturing Facilities

Sub-surface
Concrete Pit TypeTrench Type(or Geological)

Most Waste from
Dismantling

Sources as shown in theabove

Reuse
Disposal as generalwastesWaste fromPowerReactors

Waste below the Clearance Level

Concrete Pit TypeTrench TypeThe 1st International Forum on the Decommissioning of the Fukushima Daiichi NPS, Apr. 10-11, 2016

3

Disposal Concept of Radioactive Waste in Japan
Several types of disposal facilities have been designed according to the radioactivity
levels of the wastes.
Demonstration Test of Very Low-Level
Concrete Waste Disposal (Trench Type) arisingfrom decommissioning of JPDR (JAEA,Tokai)

Overview of the Disposal
Facility Before Installation ofthe VLLW

http://www.jaea.go.jp/english/04/ntokai/backend/backend_01_04.html

Overview of the Disposal
Facility Covered with Soil(1997)

http://www.jaea.go.jp/english/04/ntokai/backend/backend_01_04_01.html

The 1st International Forum on the Decommissioning of the Fukushima Daiichi NPS, Apr. 10-11, 2016

4

Contents

 Classification and Disposal Concept ofRadioactive wastes in Japan Disposal Practice and Plan in Japan R and D of Fukushima Daiichi RadioactiveWastes
The 1st International Forum on the Decommissioning of the Fukushima Daiichi NPS, Apr. 10-11, 2016

5

Disposal Facilities of Radioactive Waste fromNPS
No.2 Disposal facility

No.1 Disposal facilityJapan Nuclear Fuel Limited
Low-level Radioactive Waste Disposal Center in Rokkasho, Aomori
Total of 284,763 low-level waste drums has been received as of Jan.31, 2016.
http://www.jnfl.co.jp/business-cycle/llw/llw-center.html

The 1st International Forum on the Decommissioning of the Fukushima Daiichi NPS, Apr. 10-11, 2016

6

Waste Packages to No. 1 & 2 Disposal Facility
No.1 disposal facility

No.2 disposal facility

Waste

Concentrate,
Spent IEX, etc.,

Metal, Plastic, etc.,

BinderCement, Bitumen, Plastic

CementContentThe 1st International Forum on the Decommissioning of the Fukushima Daiichi NPS, Apr. 10-11, 20167

Outline of Sub-surface Disposal
I.

The waste is disposed of at a depth atwhich underground facilities can beconstructed (e.g. about 50-100m fromsurface), taking underground conditions
into consideration.

II. Rocks with the ability to prevent
radionuclide transport are selected.
III. A disposal facility which has the ability tocontain radionuclides, such as aconcrete vault, is constructed.
IV. Considering the decrease in radionuclide
concentrations due to decay, thedisposal facility is managed for a periodof several 100 years.

Second Progress Report on Research and Development for TRU Waste Disposal in Japan- Repository Design, Safety Assessment and Means of Implementation in the Generic Phase -The 1st International Forum on the Decommissioning of the Fukushima Daiichi NPS, Apr. 10-11, 20168

Concept of Disposal Facility of HLW

http://www.numo.or.jp/en/jigyou/geological.html

The 1st International Forum on the Decommissioning of the Fukushima Daiichi NPS, Apr. 10-11, 2016

9

Policy orientation responding torecommendations by Science Council of Japan (SCJ)
SCJ Recommendation to Japan
Atomic Energy Commission (JAEC):JAEC Recommendation to theGovernment:

1.

1.

2.

3.

4.

5.

6.

Social consensus on the nuclear energy
policy should be pursued before talking
about geological disposal of HLW;
The limitation of scientific andtechnological capability should berecognized and scientific autonomy for
scientific deliberation should be secured;A policy framework should be rebuilt
centered on temporary storage and total
volume control of the waste;
Socially acceptable procedures should bepursued, formulating policies based on theprinciple of fair burden-sharing;Multi-step procedures should be pursued
to build consensus by establishing venues
for discussion andNeed for long-term tenacious efforts tosolve the problems should be recognized.

2.

3.

4.

To clarify the amount and nature of HLW in
association with nuclear fuel cycle policies to be
pursued in the post-Fukushima accident era,noting that one repository under planning will be
sufficient for several decades of nuclear power
generation;
To review the safety of geological disposal of
HLW based on the latest knowledge of scienceand technology and geology in particular, andshare the result with the public as well aslearned societies;
To make it clear that its efforts to realize final
disposal of HLW be promoted step-by-step,
assuring reversibility and retrievability so that thecourse of action can be modified based on the
result of consensus with the public and risk
assessments to be emerged in the future;
To take initiative in sharing information andexchanging opinions with the public throughregular meeting with citizens and municipalities.

Shunsuke Kondo, “Current Status of Program for Geological Disposal ofhigh-level radioactive waste (HLW) in Japan”, Sep. 2014.

The 1st International Forum on the Decommissioning of the Fukushima Daiichi NPS, Apr. 10-11, 201610

Contents

 Classification and Disposal Concept ofRadioactive wastes in Japan Disposal Practice and Plan in Japan
 R & D of Fukushima Daiichi Radioactive
WastesThe 1st International Forum on the Decommissioning of the Fukushima Daiichi NPS, Apr. 10-11, 201611

Waste Resulting from Accident
at Fukushima Daiichi NPS(1)Radioactive waste from operation
volume Around 3% of wholedecommissioning waste

Radioactive waste from accident
Huge amount by internal andexternal contamination* of R/B andT/BScatter/dispersion

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

DebrisFallentrees

ContaminatedwaterSoil○ Large quantity and spread overwide area
○ Insufficient past employment ofprocessing and disposing of trees
and soil○ Mainly surface contamination by
scattering and dispersion, partly by
seeping contaminated water[Secondary waste stemming fromtreatment of contaminated water]

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

Pipes forreplacement, reservoir,etc.

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

*: Contamination due to activation products and waste generated fromoperation may be included.

The 1st International Forum on the Decommissioning of the Fukushima Daiichi NPS, Apr. 10-11, 201612

Waste Resulting from Accident
at Fukushima Daiichi NPS(2)R&D items to minimize uncertainty in waste processingand disposal
Generation of waste [quantity, type, period]
Handling (collecting/classifying) [difficulty]
Characterization [sufficiency of information, difficulty of sampling,representativeness of sample]
Technologies for processing and packaging waste
Burial and disposal methods and safety assessment
 Waste generated from operation has its own problem but is fairly under control.
• Information on basic properties of waste, including quantity at present, future change, activity and chemical
substances contained in individual waste is identified.
• Both unprocessed and processed wastes are appropriately stored and managed in accordance with the current
regulations.
• Regulations and standards, as well as disposal method and safety assessment method, have been in place.

 Many uncertainties poses important technical problems in the disposal of wastes from the accident atFukushima Daiichi. Solving these uncertainties and bringing the wastes under control are the major goalsof technology development.

The 1st International Forum on the Decommissioning of the Fukushima Daiichi NPS, Apr. 10-11, 201613

Strategy and Roadmap
Technical Strategic Plan 2015 for Decommissioning ofthe Fukushima Daiichi Nuclear Power Station of Tokyo
Electric Power Company （formulated April, 2015）- To provide a firm technical basis for the government’s Mid-and-Long-TermRoadmap.
- To serve as an aid for smooth and steady implementation ofdecommissioning.

Mid-and-Long-Term Roadmap（revised June, 2015）
FY 2017- Basic concept of processing and disposal for solid radioactive wastes.
FY 2021- Prospects of a processing/disposal method and a technology related to its
safety.
The 1st International Forum on the Decommissioning of the Fukushima Daiichi NPS, Apr. 10-11, 201614

Whole Structure of R&D for Decommission of Fukushima
MEXT promotes basic research and provides advanced research infrastructures in order to- realize technical breakthroughs with scientific knowledge based on mechanisms or principals;- establish an under-one-roof research hub, with advanced research facilities, where industry,
academia and government cooperate with each other;- facilitate human resource development beyond the field of nuclear science in a long-term perspective

Forefront

Applied Development- Coping with existing
technologies- Technical Needs derived
from Fukushima site

- Applying new technology
to the site

- Advanced research facilities
Advanced Research Infrastructure
Basic Research- Research database- Scientific Research basedon mechanism or principal- Human resource development

The 1st International Forum on the Decommissioning of the Fukushima Daiichi NPS, Apr. 10-11, 2016

researchers and knowledge
under one roofTEPCO15

Flow Chart and Research Items on Disposal ofRadioactive Waste
Analysis on radioactive nuclide in waste

Characterization••Analysis on concentrations ofradioactive nuclide
Physical properties and chemicalcomposition

Hydrogen generationfrom the waste[H2] ≤1.51%(less thanexplosive limit)

Long term storage•JAEA staff collecting
rubble near 4th reactor

Assessment of safety on long termstorage- Safety of hydrogen gas- Corrosion of container- Stability of waste

Analytical work on 3H, 14C

Measurement of thermal conductivity of waste

Conditioning （processing for disposalpackage）••

Technical research on conditioning
Basic test for technical assessment- Vitrification- Geopolymer solidification

Calculated result onhydrogen concentration

Basic test for technicalassessment on
conditioning

Disposal••Measurement of effective thermal
conductivity of zeolite layer

Investigating disposal concept
Disposal safety assessment⁃ Domestic and international researchon disposal concept and safetyassessment techniques, and theirapplicability

The 1st International Forum on the Decommissioning of the Fukushima Daiichi NPS, Apr. 10-11, 2016

Vitrification

Geopolymer
solidification

16

Inventory estimation based on analytical results

 The inventory of the cesium
adsorption vessel isestimated using analytical
data of the contaminatedwater.
 The inventory of theundetected nuclide at the
inlet of the equipment iscalculated on thepresumption that thedetection limit of thenuclide is considered theupstream concentration.
 They can be compared withradioactive concentration ofeach nuclide equivalent toreference dose in an
examination of the disposal
concept.

The average concentration of used vessels(Bq/t)The inventory of a secondary waste generated from contaminated water treatment isestimated using the analytical data of the contaminated water between upstream anddownstream of the equipment.

Sr-90

Cs-137◆ Calculated from the water concentration gap between upstream and downstream of the equipment (6 nuclides) .
▲ Calculated as all nuclide in contaminated water is considered to adsorb (1 nuclide).
○ Same as above case, but the determination limit is used to calculate (18 nuclides).
× Calculated based on the fuel composition (7 nuclides)※1―（Red）The radioactive concentration of each nuclide equivalent to reference dose for the concrete pit disposal※2.
―（Green）The radioactive concentration of each nuclide equivalent to reference dose for the sub-surface disposal※2.

Nuclides※1 The value calculated by the rate of nuclide composition in the fuel（JAEA-Data/Code 2012-018）.
※2 Nuclear Safety Commission，“Upper Bounds of Radioactive Concentration in Burial of Low-Level Radioactive Solid Waste (in Japanese)”, May 2007.
Thisincludes the resultsof “Developmentof technology for treatmentof accident
waste” subsidized
to JAEAand IRID
by the Agency for Natural Resources and Energy.
Thefigure1st InternationalForumon the Decommissioning
ofandthedisposal
FukushimaDaiichi
NPS, Apr.
10-11,
201617

Radioactivity concentration of 90Sr (Bq/g)

Radioactivity of 137Cs vs 90Sr for rubbles at
Fukushima Daiichi NPS
Around Unit-1
Around Unit-3

1031%

Around Unit-4

0.1%

In Unit-1 Building

0.01%

In Unit-2 Building
In Unit-3 Building

10１

10-1

(Open symbols represent 90Sr< the detection limit)(Radioactivity concentration is Corrected on March11, 2011 )

10-3
100

102

104106

Radioactivity concentration of 137Cs (Bq/g)
Radioactivity concentration for rubbles sampled around each Unit and in the building of each Unit

Correlation of Radioactivity of 137Cs vs 90Sr was found.
This figure
includes the resultsof “Developmentof technology for treatmentof accident
waste” entrusted
to JAEA
and IRID
by the Agency for Natural Resources and Energy.
The
1st InternationalForumon the Decommissioningof andthe disposal
Fukushima
Daiichi
NPS, Apr.
10-11,
201618

International Collaboration
 Collaboration research and information exchange with international organization andresearch institutes in many countries

Internationalorganization andcountries

Institutes

International Organization

OECD/NEA、IAEA

United States of America

DOE、NRC、ANL、INL、LANL、LBNL、ORNL

EuropaEngland：NNL、 France：CEA、 IRSN、 Germany：KIT、Czech Republic：NRI/CVR、 Sweden：KTH、Europa：ITU、Ukraine：ISP-NPP

Finland：VTT、

1st CLADS Decommissioning Workshop and Seminar-International Collaboration towards Advanced Decommissioning of Fukushima-Daiichi NPP～November 10-11, 2015 at Tokai, Ibaraki～Around 130 participants including 19 experts from abroad

The 1st International Forum on the Decommissioning of the Fukushima Daiichi NPS, Apr. 10-11, 201619

Summary Wastes generated from nuclear facility are classified
into three categories as High-level radioactive waste(HLW), Low-level radioactive waste (LLW), and WBCL
(Waste below clearance level).
 LLW disposal facilities for wastes from NPS havebeen in operation.
 R & D on the Fukushima Daiichi radioactive wastes
are intensively conducted by JAEA/CLADS under thedomestic and international collaborations.
The 1st International Forum on the Decommissioning of the Fukushima Daiichi NPS, Apr. 10-11, 201620