2019F002-EC081-R00

Project of Decommissioning and Contaminated Water Management(Research and Development of Processing and Disposal of Solid Waste)

Applicability evaluation of In-Can Vitrification- FY2019-2020 Achievement –Orano ATOX D&D SOLUTIONS Co., Ltd.
(ANADEC)
This document doesn’t include theinformation related to the unique technologyof the project proponent.

2019F002-EC081-R00

Table of contents
1. Executive summary
2. Background
3. Overview of the FY2019-2020 project
4. Schedule
5. Organization chart
6. Implementation contents
STEP 1:

Expertise analysis of the waste assembly

STEP 2:

Experimental feasibility study of waste treatment and vitrified material
formulations

STEP 3a: Vitrified material performance pilot test FY2018
STEP 3b: Vitrified material performance pilot test FY2019

STEP 4:

CAN material study

STEP 5:Specification and production of the waste surrogates for the pilot tests

STEP 6:

Pilot tests

STEP 7:

Technical and economical evaluation of waste treatments

STEP 8:Regulations and safety

7. Summary and future prospect

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2019F002-EC081-R00

1. Executive summary
From the study performed on the In-Can process, we demonstrate that: Fukushima Effluent Treatment Waste (FETW) can be processed with high Waste
Loading (WL*) as follows:*In this presentation, WL is✓ ALPS slurry: 25% ~ 40%

expressed in oxide massunless otherwise specified✓ Zeolite: over 60%✓ CST: ~30%
✓ Cs-rich waste (Mix of zeolite, CST and sand): 80%

 Higher WL can be further studied, without degrading leaching properties
 A containment of 99,96% for Cs and 99,99% for Sr can be achieved The vitrified materials have a low leaching rate, similar to international standards
glasses of radioactive wastes, The canister can be manufactured with appropriate material, a good cost-benefit
approach
Based on our site owner & operator experience, we propose two Dem&Melt** units toprocess Cs-rich waste and Sr-rich waste*** in 14 years.
**Dem&Melt: Industrial demonstrator of the In-Can process. In operation since November 2020.
***ALPS slurry, Kurion-CST, Evaporator concentrates, ALPS TiO2, ALPS ferrocyanide

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2019F002-EC081-R00

2. Background
History of vitrification technology development
2020
La Hague

2016

2010
2008
2005
2004
2001
1996

Severaltypes
ofvitrification
systemshave been tested anddeveloped. AVM, AVH,
CCIM, In-Can Melter...

1992

1989
1980’s1978
1970’s1960’sDem&Melt pilot start“Dem&Melt program” launch

CCIM in R7

In-Can Melter process pilot starts

In-Can Melter process development starts

PEV+CCIM Industrial Platforms
CFA Platform Development

Mechanical Stirring

La Hague T7 Start-up

La Hague R7 Start-up

CCIM Initial Studies

UP1 AVM Start-up

Two-step Vitrification Process
La Hague

Hot-wall Metallic Induction Melter (PIVER)

Choice of Borosilicate Glass
1950’sMarcoule

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2. Background

2019F002-EC081-R00

Features of the In-Can process
In-Can process: Thermal treatment technology with the feature that a
CAN containing waste and glass frit is heated by surrounding resistive
heater in furnace, and directly used for waste package➢ No need to drain the molten glass➢ No need for a specific “starter” or “finisher” to start or finish the heating process➢ Possible to flexibly control the heating cycle➔Versatile and robust process for radioactive waste

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3. Overview of the FY2019-2020 project

2019F002-EC081-R00

Target and approach
Target: Complete the overall feasibility of the In-Can vitrification by end of FY2020.
STEP-by-STEP approach adopted to achieve the target and to proceed with the project efficiently
STEP
1
2

Items
Expertise analysis of the waste assembly-

Integration of input data and study of testing condition/strategy to treat waste stream one-by-one

Experimental feasibility study of waste treatment and vitrified material formulations-

Melting tests on lab/bench scale and analysis of the vitrified material produced

STEP 3a: Vitrified material performance pilot test FY2018
3a, 3b STEP 3b: Vitrified material performance pilot test FY2019-

4
5

Leaching and mechanical tests on the vitrified material produced by pilot tests

CAN material study-

Theoretical and experimental study of promising CAN material and comparison with Inconel

Specification and production of the waste surrogates for the pilot tests
Pilot tests

6
7

8

-

Demonstration of whole process such as production of vitrified material, volatility and feeding
system testing

Technical and economical evaluation of waste treatments-

Study on layout, secondary waste, CAPEX and OPEX and impact of the challenging waste

Regulations and safety-

Applicability
evaluation of In-Can Vitrification
Study on adaptability of In-Can vitrification to Japanese
regulations- FY2019-2020 Achievement -p. 6

3. Overview of the FY2019-2020 project
Main contents and correlations of STEPs
FY2018 study
12 Lab tests: (Scenario A, B, C and D)
4 Bench tests: (Scenario A, B, C and D)
1 Pilot test:(Scenario B)

STEP 1

Scenario A, B :All-mix
Scenario C :Cs-rich waste
Scenario D :Sr-rich waste

Scenario B

Scenario C

STEP 5, 6
Pilot test
1

STEP 4
CAN material
study
for pilot test 1
CAN material
study
for pilot test 2

Expertiseanalysis of
the wasteassembly

2019F002-EC081-R00

Pilot test
2

STEP 3b

STEP 3aVitrified material
performance
pilot test FY2019

Vitrified material
performance
pilot test FY2018

STEP 7

STEP 8

Technical
andeconomicalevaluationof wastes
treatments

Regulationand safety

CAN material
corrosion /interaction tests

STEP 210 Lab tests .
✓ At early stage of R&D, number of test isimportant to know the whole image✓ Lab test can be easily performed, suitable
for this purpose✓ After lab test, based on the test result,
move on to more practical test withpromising materials / conditions✓ Smaller scale test result reflected tobigger scale test conditions:
Lab → Bench → Pilot

Bench test 2:
preliminary testfor Pilot 2

Bench test
1

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2019F002-EC081-R00

4. Schedule
FY2019
May

Jul.

Oct.

FY2020
Jan.

Apr.

Jul.

Oct.

COVID-19 epidemic

STEP 1. Expertise analysis of the waste assembly:- Waste information gathering- Expertise of strategy of waste assembly

FY2021Jan.

Apr.

Initial schedule
Schedule after COVID 19

STEP 2. Experimental feasibility study of waste treatment and vitrified material formulations:- 10 Lab scale tests (-100g)- 2 Bench scale tests (~1 kg)- Analysis
STEP 3a: Vitrified material performance pilot test FY2018
STEP 3b: Vitrified material performance pilot test FY2019
STEP 4. CAN material study:- Optimization CAN material for pilot test 1- Optimization CAN material for pilot test 2- Test on refractory stainless steel CAN

Project progress was heavily
affectedby
COVID-19
epidemic. But the project
has been completed in theend of April.

STEP 5. Spec. and prod. of the waste surrogate for the pilot test:- Supply of test material for pilot test 1 (based on Sc.C in FY2018)- Supply of test material for pilot test 2
STEP 6. Pilot tests:- Pilot test 1 (~100kg)- Pilot test 2 (~100kg)
STEP 7. Tech. and eco. Evaluation of the waste treatment:- Tech/Cost treatment up to disposal- Technical evaluation of other waste treatment
STEP 8. Regulation and safety:- Adaptability study of In-Can process to Japanese regulation

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2019F002-EC081-R00

5. Organization chart
Project managed by ANADEC and subcontracted to:
CEA for vitrified material durability andformulation expertise, process expertise,lab/bench/pilot tests realization
Orano for engineering studies, technicalexpertise and technical coordination
JGC for Japanese safety studies
ANADEC ensures that:All subcontractors have the required
information on time
The requests from its customer are integrated
in the project, as much as reasonably possible
All documents are submitted on time, andcompliant with specifications after review andvalidation by ANADEC (Final presentations ,Intermediate report, final presentation, final
report)Orano ATOX D&D Solutions Co., Ltd. (ANADEC)

Project Manager

Deputy Manager

Project
Management
team

Technical
team

Project
Management

Technical review
and reporting

Subcontractor 1
Orano cycle
Engineering study, technicalexpertise, technical coordination

Subcontractor 2
CEA

Subcontractor 3
JGC

Vitrified material durability andformulation expertise, process expertise,lab/bench/pilot tests realization

Japanese safety studies

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6. Implementation contents

2019F002-EC081-R00

STEP 1. Expertise of analysis of the waste assembly:
treatment strategies
Based on the waste data inventory, FY2018 achievement* and CEA/Oranoexpertise, strategy of treatment and need of experimental study was defined.
Strategy of treatment* Please see the following document for details:
The summary results of subsidy program (the First solicitation) for the” Project ofDecommissioning and Contaminated Water Management (Research and Developmentof Processing and Disposal of Solid Waste (Research and development on preceding
processing methods and analytical methods))” in the FY2017 Supplementary Budget.

-

FY2018:
Mixture of the different waste to validate the glass formulation between several waste
and to optimize the waste loading, the number of the waste packages produced and theprocess operation/design.

-

FY2019-2020:
One-by-one treatment of each FETW to provide an alternative In-Can treatment
methodology for FETW.
The presence of Chloride and alpha nuclides will be considered

Applicability of both mixing and one-by-one treatment has beenstudied. → Possible to provide flexible options to treat FETWs
in the future developments
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6. Implementation contents

2019F002-EC081-R00

Pilot tests

Bench tests

Lab tests

STEP 1. Expertise of analysis of the waste assembly: 10 Lab tests
10 Lab tests selected based on one-by-one treatment strategy:
Aim of tests: Feasibility demonstrations giving the waste loading evaluation, suitable operation
temperature, glass additives to be used and CAN material corrosion (to a lesser extent)
Test

Waste stream Glass additive WL (wt%)
Carbonated ALPS•LAB 1
Glass frit 1***~40
slurry*•Ferric ALPS•LAB 2Glass frit 1***~25
slurry*•Mixed ALPS slurry•
LAB 3
Glass frit 1***~40,
Mix 1* **•Mixed ALPS slurry•
LAB 4
Glass frit 1***~40,
Mix 2* **•Zeolites IONSIV®
•
LAB 5
Glass frit 2***over 60
R9160-G•CST IONSIV®
•LAB 6Glass frit 3***over 30
R9120-B•RN simulation
Sr
Ce for α nuclide simulation
Sr
Ce for α nuclide simulation
Sr
Ce for α nuclide simulation
Sr
Ce for α nuclide simulation
Cs
Ce for α nuclide simulation
Cs and Sr
Ce for α nuclide simulation

CAN corrosion
Visual observation
Visual observation
Visual observation
Visual observation
Visual observation
Visual observation

LAB 7
LAB 8
LAB 9

Test contents from LAB 7 to LAB 10 are not disclosed because the information related to theunique technology of the project proponent are included.

LAB 10*Cl-considered waste used**Material that ALPS carbonate slurry and ALPS ferric slurry are mixed at different rates.
Applicability evaluation of In-Can Vitrification***3 different glass frits used
- FY2019-2020 Achievement -p. 11

Pilot tests

Bench tests

Lab tests

6. Implementation contents

2019F002-EC081-R00

STEP 1. Expertise of analysis of the waste assembly:
2 Bench & 2 Pilot tests
2 Bench tests and 2 Pilot tests selected based on one-by-one treatment strategy:
Bench-scale: Confirm the result of the lab-scale test using small In-Can equipment and the benefit of
the upscale process
Pilot-scale: Check the compatibility of the whole process including feeding, Off Gas Treatment
System (OGTS), vitrified material elaboration, process parameters with pilot-scale equipment
Test

Bench 1

Waste stream

RN simulation

Note

Test contents of Bench 1 is not disclosed because the information related to the unique
technology of the project proponent are included.

Bench 2Mix of ALPS slurry
Mix 1

•
•

Sr
Ce for α nuclide simulation• Corresponding to LAB 3• 75vol% of waste inventory• Cl-considered waste used
• Preliminary test for Pilot 2

Pilot 1

Mix of Zeolite, CST and •Sand•

Cs and Sr
Ce for α nuclide simulation• FY2018 Sc. C: Cs-rich waste• CAN corrosion checked••Sr
Ce for α nuclide simulation• 75vol% of waste inventory• Cl-considered waste used
• CAN corrosion checked

Mix of ALPS slurry
Pilot 2
Mix 1

~1kg
bench-scalecan~100kgpilot-scalecanTesting parameters
updated based on thelab test results

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2019F002-EC081-R00

6. Implementation contents

STEP 2. Experimental feasibility study of waste treatment and vitrified material formulations:Executive summary•

ALPS slurry, zeolite and CST are successfully vitrified (Results are explained in
the following pages.)➢ ALPS slurry: Feasibility confirmed at about 40% WL➢ Zeolites: Feasibility confirmed at over 60% WL➢ CST: Feasibility confirmed at over 30% WL➢ Feasiblity of ALPS slurry mix vitrification were also confirmed at bench scale.

The results obtained are promising as applicability demonstration phase
Some items can be still improved:► Increase of WL (through optimized additives)► Optimization of treatment temperatures► Vitrification feasibility of minor streams.

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2019F002-EC081-R00

6. Implementation contents

STEP 2. Experimental feasibility study of waste treatment and vitrified material formulations:
LAB 1 ~ 4, ALPS slurry tests
No.

LAB 1

LAB 2

LAB 3

LAB 4

Waste ALPS carbonate slurry

ALPS ferric slurry

Mixed ALPS slurry 1

Mixed ALPS slurry 2

WL

~25

~40

~40

~40
After each test, epoxy resin was
filled into the crucible for protectionof the vitrified material during cutting.

Result✓ Solidified and dense vitrified material in the form of a solid mass obtained✓ The vitrified materials obtained mainly consist in vitreous phase containing RNs and Cl.
✓ No major corrosion of the metallic crucible is observed.

► ALPS slurry successfully vitrified with the WL of 25 ~ 40%► Higher WL should be reachable with an optimized glass fritadapted to the waste
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2019F002-EC081-R00

6. Implementation contents

STEP 2. Experimental feasibility study of waste treatment and vitrified material formulations:
LAB 5 ~ 6, Zeolite and CST tests

No.

LAB 5

LAB 6

Waste Zeolite

CST

WL

Over 30

Over 60

Result► Zeolite and CST successfully vitrified with the WL of over 60
and over 30 wt%, respectively

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2019F002-EC081-R00

6. Implementation contents

STEP 2. Experimental feasibility study of waste treatment and vitrified material formulations:
Bench-scale test equipment

DS recirculation loop
Columnwith trays
Gas from
melterDS automatical water feedingboilerDust scrubber (DS)Bench scale test equipment

Waste solid inlet•
Gas extraction pipe
Oven window tap point

Condenser••

Feeding unit (Existing equipment:
not used for these tests)
Melting unit (resistive heating)
Off-gas treatment unit (dustscrubber and condenser)
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2019F002-EC081-R00

6. Implementation contents

STEP 2. Experimental feasibility study of waste treatment and vitrified material formulations:
Bench-scale tests conditions

Bench-scale: Confirm and complement the result of the lab-scale test using small
In-Can equipment and the benefit of the upscale process
Bench 2 (ALPS slurries vitrification)
WL~ 40 %

Massslurry dehydrated surrogate + Glass frit 1~ 1 kg in total

Appearanceof the waste
before test

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2019F002-EC081-R00

6. Implementation contents

STEP 2. Experimental feasibility study of waste treatment and vitrified material formulations:
Bench 2: ALPS slurry vitrification – summary➢ Low Sr volatility: < 0.05% (Ce volatility: < D.L.*)*Detection
limit➢ Microstructure analysis revealed that vitrified material
with a homogeneous appearance obtained.
✓ Very close to the vitrified material on lab-scale test•
Vitrified material on Bench 2

Showing the benefits of the up-scale process✓ Composed of SiO2, Na2O, CaO, B2O3 and Fe2O3,
and also contains the majority of Ce and Sr.
✓ Only few crystals are present along the cruciblewalls and on the vitrified material surface.
➢ No major corrosion observed by SEM and visualinspections

Vitrified material on LAB 3

Success of vitrification of ALPS slurry mix with WL ~40%
► Homogeneous vitrified material► High WL (could be optimized through a dedicated glass fritadapted to the waste)► Very low volatility: <0.05%

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2019F002-EC081-R00

6. Implementation contents
STEP 3a. Vitrified material performance pilot test FY2018
Summary• Performance of “Scenario B” (Treatment of the mix of ALPS slurry, zeolite, CST andsand) vitrified material about compression strength and leaching rate has been
experimentally analyzed. Results are explained in the following pages.
• The microstructure of the vitrified material is very similar regardless of the location,
consisting of a vitreous phase with embedded durable crystals distributed
homogeneously.
• Cs is localized in the vitreous phase and Sr is distributed between the crystal
phases and the vitreous phase.
• The compressive strength were between 40 and 200 MPa, typical value ofborosilicate glasses.
• The leaching test results are typical as borosilicate glasses with a sharp drop of theleaching rate. Cs and Sr leaching rate is very low and Cs is retained in the alteration
layer.

► Experimental result revealed that it’s possible to produce a dense
and durable vitrified material on scenario B with 80% WLox.
► This will enable a significant volume reduction of waste andshortening of the operation period necessary to treat the wholewaste inventory.
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2019F002-EC081-R00

6. Implementation contents

STEP 3a. Vitrified material performance pilot test FY2018
1. Microstructural analysis, 2. Compressive test and 3. Leaching test
4 samples are analyzed, 6 main chemical natures of phases confirmed①Bottom②Middle, center③Middle, near wall
④Top

FY2018 Sc. B (All waste)• ALPS slurries• Zeolites• CST• SandWL = 80%
Examples of SEM images and EDS analyses in region ① (Bottom of the vitrified material)• The vitrified material is well densified.
• Cs is mostly located in the vitreous phase.
• Sr is in both vitreous phase and the crystal phases.

Microstructure of the vitrified material obtained is very similar at all location of the vitrified material➔The reactivity between the wastes and the glass frit appears to be homogeneous

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2019F002-EC081-R00

6. Implementation contents

STEP 3a. Vitrified material performance pilot test FY2018
1. Microstructural analysis, 2. Compressive test and 3. Leaching test
Uniaxial compression tests performed on 5 cores, 8 samples
Compression
strength [MPa]Reference value
For B-Si glass* [MPa]

Min

42

22*

Max

200

384**

Ave

101

-

*Ojovan M.I., Lee W.E., 2005. Chapter 17 - Immobilisation of Radioactive
Wastes in Glass. In: Ojovan, M.I., Lee, W.E. (Eds.), An Introduction to Nuclear
Waste Immobilisation. Elsevier, Oxford, p. 213-249.
**Ashby M.F., 2013. Chapter 15 - Material profiles. In: Ashby, M.F. (Ed.),
Materials and the Environment (Second Edition). Butterworth-Heinemann,
Boston, p. 459-595.

⑤B

⑤A

⑤
⑥A

⑥
⑦
⑧
⑨

⑥B
⑥B

⑦A

⑦B

Mechanical strength of the vitrified
material was the same order ofmagnitude as borosilicate glass.

⑧A⑨A

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2019F002-EC081-R00

6. Implementation contents

STEP 3a. Vitrified material performance pilot test FY2018
1. Microstructural analysis, 2. Compressive test and 3. Leaching test
Leaching tests (adapted from MCC-1) performed on 6 samples (taken from 5 cores)
BottomMiddle• NL(B) curve exhibited the typicaltrend of borosilicate glasses.

BottomMiddle• NL(Cs) can be calculated andcompared to NL(B) because B is
located in the vitreous phase and,according to the microstructure
analysis, Cs was also mainly
located in the vitreous phase.

Normalized mass loss of B: NL(B)

BottomMiddleNormalized mass loss of Cs: NL(Cs)➔ Cs was partially retained in thealteration layer►Very good leaching performances►leaching rate is 1.5 times lower than the EA glass►Leaching test results are typical as borosilicate glasses with a sharp
drop of the leaching rate.
►The Cs and Sr leaching rate is very low and Cs is retained in thealteration layer

Evolution of leaching rate of B

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2019F002-EC081-R00

6. Implementation contents
STEP 4. CAN material study

For cost optimization, we selected several materials for possible CAN material
from preliminary study and CEA/Orano feedback and experience. The quantityof material is directly linked to material properties.

•

Following topics were implemented in this STEP.
➢ CAN material study for Pilot 1➢ CAN material study for Pilot 2➢ CAN material corrosion / interaction test•

The most economical balance between material intrinsic cost and quantityof the material per CAN is researched through the study above.

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6. Implementation contents

2019F002-EC081-R00

STEP 5 & 6. Pilot test 1: Summary of result
Pilot 1: Vitrification of Cs-rich waste (Zeolite, CST and Sand, FY2018 Sc. C)
Parameter
Mass of production
Volatility
CAN
WL
Leaching rate
Compression
strength

Result103kg of vitrified material with Cs, Sr, Ce
produced
Cs: 0.04%, Sr: 0.01%
No corrosion observed~ 75%
Same order of magnitude as R7T7 glass
Same order of magnitude as the standard
concrete and typical HL vitrified material✓ Test successfully performed with High WL✓ Low volatility: Cs: 0.04%, Sr: 0.01%✓ Very good performances on chemical durability viewpoint.
Leaching rate with the same order of magnitude as French R7T7
reference glass for high-level waste (~0.2g/m2/d): Result of STEP 3b

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6. Implementation contents

2019F002-EC081-R00

STEP 5 & 6. Pilot test 2: Summary of result
Pilot 2: ALPS slurry mix vitrification (Carbonate 5 : Ferric 1)

Parameter
Mass of production
Volatility
CAN
WL

Result72kg of vitrified material with Sr, Ce
Sr: < 4*10-3 %, Ce: < D.L.
No corrosion observed~ 40%✓ High WL✓ Extremely low volatility of Sr: < 4*10-3%✓ From visual observation, the vitrified material
appears homogeneous.

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6. Implementation contents

STEP 7. Technical and economical evaluation of waste treatments❑ Engineering study and cost evaluation* performed assuming the installation of In-Can*The implementation contents of cost evaluation is not disclosed.
vitrification technology to Fukushima Daiichi NPS► 2 compact vitrification units designed (2 furnaces in each unit):
Cs-rich waste: Waste withhigh Cs activity- Cs rich waste ➔ Dem&Melt unit with remotely-controlled operation and maintenance Sr-rich waste: Waste withless Cs activity and high- Sr rich waste ➔ Dem&Melt unit with contact maintenanceSr activity➔This strategy would allow optimizing costs and duration for waste treatment► CANs to be produced** and duration estimate (depending on strategy):- Cs rich waste ➔ Between 4000 and 4800 CANs to be produced and between 11 and 13 years ofoperation- Sr rich waste ➔ Between 4500 and 5000 CANs to be produced and between 13 and 14 years ofoperation**Calculated based on WL
Dem&Melt units design benefits from mature and proven technologies (from up stream functions todown stream functions ) – Over 40 years of HA operation at La Hague and Marcoule.

Cs rich waste
unit

tested so far and on thesize of Dem&Melt unit etc.

Sr rich wasteevaluation of In-Can Vitrification
Applicability
unit- FY2019-2020 Achievement -p. 26

2019F002-EC081-R00

6. Implementation contents

STEP 8. Regulation and safety: Introduction
Applicability of Dem&Melt In-Can vitrification facility to Japanese safety
requirements for installation to 1F was studied:
Method：1. Based on the laws and regulations referred to in the design of low-level
radioactive waste treatment facilities, items that should be considered in thesafety design of Dem&Melt In-Can Melter facilities are extracted from the laws
and guidelines below.
➢➢➢➢

Laws and regulations for Nuclear Facilities in General
Laws and regulations specific to Fukushima Daiichi Nuclear Power Station
Guidelines set forth by the Nuclear Regulation Authority
Implementation Plan prepared by TEPCO➢(Major non-nuclear laws that may be relevant for the construction of nuclear facilities)

2. Key terms in the statute that are relevant to safety design are summarized.
And then, the applicability and classification are studied.
It was confirmed that there was no problem that was difficult to be solved
assuming the items to be described in the implementation plan.
Dem&Melt In-Can Melter facility is capable of being designed, constructed andApplicability evaluationof In-Can Vitrification
installed meeting the safety requirements in the Japanese
regulations.
- FY2019-2020 Achievement -p. 27

7. Summary and future prospect

2019F002-EC081-R00

Conclusion of the project
Target of FY2019-2020 study:➢ Complete the overall feasibility of the In-Can technology by end of FY2020.
➢ 1F waste can be processed with high WL as follows:✓ ALPS slurry: 25% ~ 40%✓ Zeolite: over 60%✓ CST: ~30%
✓ Cs-rich waste (Mix of zeolite, CST and sand): 80%➢ On pilot 1:✓ Very low volatility achieved: 0.04% for Cs, 0.01% for Sr✓ The vitrified material obtained has good leaching resistance, similar to international standards.

➢ On pilot 2, almost 100% of Sr contained in the CAN➢ Two facilities were conceptually designed to process all wastes in 14 years for areasonable initial cost, low maintenance, and relatively small amount of secondary
wastes.
➢ Dem&Melt facilities are capable of meeting the safety requirements of the Japanese
regulations

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2019F002-EC081-R00

7. Summary and future prospect
Further study after this project

From the results obtained by this project, it was found that studies shown below
can further improve the applicability of In-Can technology.

1. Full-scale test
• To evaluate and demonstrate the applicability of the technology at Full-scale withhigh WL with upgraded feeding system, based on all achievements obtained sofar.
• Target waste is considered to be dewatered ALPS slurry with high WL

2. CAN corrosion-resistance• Study to conclude the best CAN material, from both technical and economical
viewpoint, in accordance with FETW specific features such as high Cl content.

Applicability of In-Can technology would be demonstrated more precisely bythese studies.
Applicability evaluation of In-Can Vitrification- FY2019-2020 Achievement -p. 29