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Civil Nuclear Export Showcase 2014
Market Briefings & Seminars

Organization Outline & Present Activities
of
International Research Institute for
Nuclear Decommissioning (IRID)
Kiyoshi OIKAWA Director, IRID
無断複製・転載禁止 技術研究組合 国際廃炉研究開発機構
©International Research Institute for Nuclear Decommissioning
IRID is a Research & Development Consortium
Basic role is:

Fully committing to technology R&D that helps the
decommissioning project of Fukushima Daiichi NPS as an
urgent subject, based on which enhancing the technological
basis for nuclear decommissioning for the future.

Contents of operation are:
✓R&D for nuclear decommissioning
✓Promoting the international/domestic alliance
for decommissioning
✓Human resource development for R&D
Establishment: August 1, 2013
2

©International Research Institute for Nuclear Decommissioning
Overall Relationship
Electric Utilities &
Plant Manufacturers

Council for the Decommissioning of Fukushima Daiichi NPS
(Chaired by the Minister of METI)
Implementation of
Mid-and-long-term Roadmap

Outputs/Outcomes of R&D
program

Expertise for future
decommissioning projects

IRID
Management Functions

TEPCO
Headquarters
F1 Site Operation

Integrated management of R&D projects
Project Group A

Project Group B

Project Group C

R&D project A-1

R&D project B-1

R&D project C-1

R&D project A-2

R&D project B-2

R&D project C-2

Contractors &
Sub-contractors

Advice from international community
3

Joint study/research with partners
©International Research Institute for Nuclear Decommissioning
IRID as “Open Platform” for Collaboration
Board of Directors

Integrated management of
R&D projects
Alliance/
collaborative study
Technological
vendors
Research institutes,
etc.

✓Planning of overall research strategy
✓Coordination & optimization
Needs at site/
Supply of
equipment
Collaborative
study

Project -A
Project -B

International Advisors
Advices from organizational governance &
management aspects

Joint Research/
International
Collaboration

Joint
business
Sharing
results
Technological
advices

✓Discussion on innovative ideas, technologies
and projects
Innovative ideas/

OECD/NEA
- Accident analysis
- Others
IAEA
- Review mission
- Others

International
Expert Group

technology proposals

Business and research institutions all over the world
4

©International Research Institute for Nuclear Decommissioning
Overview of Fukushima Daiichi Units 1-4

 The state of progress for decommissioning varies with each unit.

Unit1: Hydrogen explosion. Cover was installed. *Most of the fuel has fallen down into the PCV.
Unit2: *Fuel debris exist the core part, lower plenum and PCV.
Unit3: Hydrogen explosion. *Fuel debris exist the core part, lower plenum and PCV.
Unit4: Hydrogen explosion. Cover for fuel removal was installed. Started fuel removal at 18 Nov. 2013.
*Fuel debris location is estimated location.

Unit 1

Covering Structure

Spent Fuel Pool
Reactor Building
Primary (SFP)
Containment
Water
Vessel (PCV)
Reactor Pressure Injection
Vessel (RPV)
Fuel Debris
Vent
Contaminated
Water

Unit 2

Unit 4

Unit 3

Blow-out Panel
(now closed)

gantry

Water
Injection

Crawler Crane

Covering Structure
Finished removing rubbles
on the building
Started removing fuels

Water
Injection

5

©International Research Institute for Nuclear Decommissioning
Outline of Mid and Long Term Roadmap
 Mid and long term roadmap was revised in June 2013.
 Phased approach was confirmed.
 The roadmap has shifted into the Phase-2, by having started fuel removal from Unit 4 SFP.
1st half of 2020 30 to 40 years in
2011
2013
(fast case)
December
November
the future
Step 1
Step 2
Phase 1
Phase 2
Phase 3
Period up to the  
Period up to the
Cold shutdown
commencement of the Period up to the
completion of
achieved
commencement of the
removal of the fuel
decommissioning
•Achieve cold shutdown
retrieval of the fuel debris
from the spent fuel
measures
(within 10 years)
•Significantly reduce
pool
(30 to 40 years in the
radiation releases
future)
(within 2 years)
Started first fuel removal
from Unit 4 SFP on Nov. 18, 2013

6

©International Research Institute for Nuclear Decommissioning
Planned Schedule for Unit 1-4
 Removal of fuel at Unit 4 was started from November 2013 (one month earlier than the initial plan).
 Retrieval of fuel debris will be started from the first half of FY 2020 (the earliest case).

Unit 1

Nuclear Fuel removal from SFPs
(target schedule)
First half of FY2017(the earliest case)
~
Second half of FY2017

Unit 2

Second half of FY2017(the earliest case) ~
First half of FY2023

Unit 3

First half of 2015

Unit 4

November 2013

Fuel debris retrieval
(target schedule)
First half of FY2020
~
Second half of FY2022
First half of FY2020
~
Second half of FY2024
Second half of FY2021(the earliest case)
~
First half of FY2023
ー

(one month earlier than the initial plan)

7

©International Research Institute for Nuclear Decommissioning
Steps for Fuel Debris Retrieval
on the premise of the Existing Flooding Method
 The most reliable method of fuel debris retrieval at present is considered to remove the fuel debris
by keeping them covered with water to reduce the risk of radiation exposure during the work
process.
HP :Technical holding points

Phase 1
2012

Phase 2

Phase 3

By 1st half
in 2020

2013

Step 1: Reactor Building Decontamination
Leaking Location
(Lower PCV) HP
Identified

Step 2:

Enough

Leaking Location

achieved

Identified

HP Water Level HP (Upper PCV)

Step 5:

PCV
Investigation
from outside

PCV Internal Inspection
and Sampling

Step 3:
Lower PCV
Repair

Step 4:
PCV Half
Flooding

Step 6:
Upper PCV
Repair
8

Enough

After
20-25
years

Defueling

HP Water Level

HP Method

achieved

Developed

Step 8:

RPV Internal Inspection
and Sampling
▽Open RPV

Step 7:
PCV/RPV
Full Flooding

Step 9:

Defueling
Debris processing/
disposal methods HP
developed

©International Research Institute for Nuclear Decommissioning
Building Internal Decontamination
DS pit

SFP
Equipment
hatch

RPV

Fuel debris

PCV

airlock

Torus

Steam dryer
Steam-water
separator
Turbine Building

 Development of remotely operated
decontamination devices that meet the
contamination conditions in the field in
order to improve the work environment
such as surveying and repairing leaks in the
PCV to prepare for fuel debris retrieval.

Waterproofing
Leak

High-pressure water jet
decontamination device

Dry ice blast
decontamination device

9

Blasting/collecting
decontamination device
©International Research Institute for Nuclear Decommissioning
Open air Robot for Inspection and Repair of PCV
Device
① Survey robot of
Vent
pipe joint
② Quadruped walking robot
( &Flat vehicle )
③ Robot for surveying the
upper part of the S/C

Characteristics
Approach joints between bent pipes and the D/W from between the vent pipe and concrete wall with
adhering itself to the surface of the outside of the vent pipe
Be used to ascertain conditions inside the S/C, such as the presence of leaks from near the area
beneath the vent pipe.
Check for leaks from structures at the top of the S/C, which is high up (Approx. 3m at its highest), after
accessing it from the catwalk outside the Torus.

① Survey robot of Vent pipe joint
PCV

③ Robot for surveying the
upper part of the S/C
Close-up camera
(with platform)
Extendable mast

PCV
Vent pipe
ベント管
Robot ロボット
adhesion
location
吸着位置

② Quadruped walking robot
Quadruped
walking robot

Vent pipe sleeves
Sand cushion drain
lines

PCV
Ven
t

1

pipe

3

S/C

2

500
mm

900
~
3000
mm

crawlers
Torus survey

4

Flat vehicle
Bellows cover

Approx.

約

6

10

5

Survey robot
©International Research Institute for Nuclear Decommissioning
Submersible Robot
Develops device
Robot for ④ Submersible
robot
surveying
submersed ⑤ Floor walking
torus walls
robot
⑥ Robots for surveying the
bottom part of the S/C

⑥ Robots
for
Surveying the
bottom part of
the S/C

Characteristics
Be used to check for damages at building penetration seals with remotely operated (used in very
narrow places) by an operator viewing a video screen.
Walk on the floor underneath the water and uses ultrasound to check for leaks in distant places.
Check for damages on the outside of the S/C, on structures on the outside and on penetration
pipes, with adhering itself to the outer surface of the S/C ④ Submersible robot
to

Movable camera

Ascent/descent
thrusters

(front, back, left, right)

Magnetic
Observation camera wheels

S/C

Inner circumference of S/C

Seismic
resistant
support

m
Exa

ve
tra
bot
f ro ute
o o
r
ple ロボット

l

Up
down

Column
support

Outer circumference of S/C

Camera

PCV
Ven
t pip
e
1

3

S/C

⑤ Floor walking
robot

Vertical thrusters
Horizontal
Thrusters

2

4
6

11

Forward
thrusters
Horizontal
thrusters

5

Taurus
walls

S/C
Tracer
Ultrasound

Taurus
Walls

Ultrasonic
sensor (sonar)
Crawlers

Camera

S/C

Robot

Robot

©International Research Institute for Nuclear Decommissioning
Investigation of the PCV Interior
 Inserting survey equipment through Unit 1 X-100B
✓ A crawler device that can transform and move along gratings stably after being inserted into the PCV
from narrow access pipe (X-100B penetration seal: inner diameterφ100mm).
[PCV cross-section]
X-100B
Existing Guide pipe

[D/W 1FL]

D/W 1F Grating

A enlarged view

X-100B
Existing guide pipe

Cable
Guide pipe

When traveling
along guide pipe
Dosimeter
CCD camera
Thermometer

Running device
A section
PCV

Grating

D/W subfloors

Transformation

X-6
: Survey route
( proposed )

High radiation level

PCV internal survey route (proposed)
12

When traveling on grating

Device concept image
©International Research Institute for Nuclear Decommissioning
Steps for Fuel Debris Retrieval
on the premise of the Existing Flooding Method
 The most reliable method of fuel debris retrieval at present is considered to remove the fuel debris
by keeping them covered with water to reduce the risk of radiation exposure during the work
process.

HP :Technical holding points

Phase 1
2012

Phase 2

Phase 3

By 1st half
in 2020

2013

Step 1: Reactor Building Decontamination
Leaking Location
(Lower PCV) HP
Identified

Step 2:

Enough

Leaking Location

achieved

Identified

HP Water Level HP (Upper PCV)

Step 5:

PCV
Investigation
from outside

PCV Internal Inspection
and Sampling

Step 3:
Lower PCV
Repair

Step 4:
PCV Half
Flooding

Step 6:
Upper PCV
Repair
13

Enough

HP Water Level
achieved

After
20-25
years

Defueling

HP Method

Developed

Step 8:

RPV Internal Inspection
and Sampling

▽Open RPV

Step 7:
PCV/RPV
Full Flooding

Step 9:

Defueling
Debris processing/
disposal methods HP
developed

©International Research Institute for Nuclear Decommissioning
Request for Information (RFI) of
Innovative Approach for Fuel Debris Retrieval

Background of RFI:

To ensure multi-fold approach, as well as to enable
technological breakthroughs, collective knowledge and
experience via interactive platform is to be pursued. This will
also benefit enhancement of safety and decommissioning of
nuclear
Schedule: facilities all over the world.
2013
✓November 29 : Website is open
✓Mid December : Procedure for RFI is to be announced
2014
✓End of January : Deadline of RFI
✓Feb/March
: Review of responses
14
✓

©International Research Institute for Nuclear Decommissioning
Topics for RFI
Topic-A: Internal PCV/RPV Status Investigation
✓A-1: Conceptual study on innovative approaches
✓A-2: Technologies for internal PCV/RPV status investigation

Topic-B: Fuel-Debris Retrieval from PCV/RPV
✓B-1: Conceptual study on Innovative approaches

[Example]
Conceptual idea of retrieving fuel debris from PCV and RPV without submerging PCV, the comparison to
the submersion scenario, etc.
(a) Accessing and removal of fuel debris from Top side of PCV/RPV under water.
(b) Accessing and removal of fuel debris from Top side of PCV/RPV in atmospheric condition.
(c) Accessing and removal of fuel debris from lateral side of PCV/RPV in atmospheric condition.
Innovative approach
(d) Accessing and removal of fuel debris from bottom side of PCV/RPV in atmospheric condition.

✓B-2: Technologies for Fuel-Debris Retrieval

15

©International Research Institute for Nuclear Decommissioning
Program Structure
MAR/APR, 2014

PHASE 1
Theme
A-1
RFI for C/S
B-1
Theme RFI for F/S
A-2
B-2

MAR/APR, 2015

PHASE 2
RFP for C/S
Selection

RFP for F/S
Selection

PHASE 3
RFP

F/S
Funding

R&D project
RFP
Funding
Selection

Selection

(3 to 5 projects)
(3 to 5 projects)

if not selected
C/S or R&D
No Funding

Others

R&D project
Funding

C/S
Funding

Project Workshop #1

(potential)
(potential)

Preliminary/Design
Funding
Selection

RFP

(potential)

R&D project
Funding
Selection
(potential)
Project Workshop #2
RFP

Visit IRID WEB for more information!
http://www.irid.or.jp
http://www.irid.or.jp/fd (for RFI)
16

©International Research Institute for Nuclear Decommissioning
Thank you for your attention

無断複製・転載禁止 技術研究組合 国際廃炉研究開発機構
©International Research Institute for Nuclear Decommissioning

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Market Briefing. Japan part 2. 28th January

  • 1. Civil Nuclear Export Showcase 2014 Market Briefings & Seminars Organization Outline & Present Activities of International Research Institute for Nuclear Decommissioning (IRID) Kiyoshi OIKAWA Director, IRID 無断複製・転載禁止 技術研究組合 国際廃炉研究開発機構 ©International Research Institute for Nuclear Decommissioning
  • 2. IRID is a Research & Development Consortium Basic role is: Fully committing to technology R&D that helps the decommissioning project of Fukushima Daiichi NPS as an urgent subject, based on which enhancing the technological basis for nuclear decommissioning for the future. Contents of operation are: ✓R&D for nuclear decommissioning ✓Promoting the international/domestic alliance for decommissioning ✓Human resource development for R&D Establishment: August 1, 2013 2 ©International Research Institute for Nuclear Decommissioning
  • 3. Overall Relationship Electric Utilities & Plant Manufacturers Council for the Decommissioning of Fukushima Daiichi NPS (Chaired by the Minister of METI) Implementation of Mid-and-long-term Roadmap Outputs/Outcomes of R&D program Expertise for future decommissioning projects IRID Management Functions TEPCO Headquarters F1 Site Operation Integrated management of R&D projects Project Group A Project Group B Project Group C R&D project A-1 R&D project B-1 R&D project C-1 R&D project A-2 R&D project B-2 R&D project C-2 Contractors & Sub-contractors Advice from international community 3 Joint study/research with partners ©International Research Institute for Nuclear Decommissioning
  • 4. IRID as “Open Platform” for Collaboration Board of Directors Integrated management of R&D projects Alliance/ collaborative study Technological vendors Research institutes, etc. ✓Planning of overall research strategy ✓Coordination & optimization Needs at site/ Supply of equipment Collaborative study Project -A Project -B International Advisors Advices from organizational governance & management aspects Joint Research/ International Collaboration Joint business Sharing results Technological advices ✓Discussion on innovative ideas, technologies and projects Innovative ideas/ OECD/NEA - Accident analysis - Others IAEA - Review mission - Others International Expert Group technology proposals Business and research institutions all over the world 4 ©International Research Institute for Nuclear Decommissioning
  • 5. Overview of Fukushima Daiichi Units 1-4  The state of progress for decommissioning varies with each unit. Unit1: Hydrogen explosion. Cover was installed. *Most of the fuel has fallen down into the PCV. Unit2: *Fuel debris exist the core part, lower plenum and PCV. Unit3: Hydrogen explosion. *Fuel debris exist the core part, lower plenum and PCV. Unit4: Hydrogen explosion. Cover for fuel removal was installed. Started fuel removal at 18 Nov. 2013. *Fuel debris location is estimated location. Unit 1 Covering Structure Spent Fuel Pool Reactor Building Primary (SFP) Containment Water Vessel (PCV) Reactor Pressure Injection Vessel (RPV) Fuel Debris Vent Contaminated Water Unit 2 Unit 4 Unit 3 Blow-out Panel (now closed) gantry Water Injection Crawler Crane Covering Structure Finished removing rubbles on the building Started removing fuels Water Injection 5 ©International Research Institute for Nuclear Decommissioning
  • 6. Outline of Mid and Long Term Roadmap  Mid and long term roadmap was revised in June 2013.  Phased approach was confirmed.  The roadmap has shifted into the Phase-2, by having started fuel removal from Unit 4 SFP. 1st half of 2020 30 to 40 years in 2011 2013 (fast case) December November the future Step 1 Step 2 Phase 1 Phase 2 Phase 3 Period up to the   Period up to the Cold shutdown commencement of the Period up to the completion of achieved commencement of the removal of the fuel decommissioning •Achieve cold shutdown retrieval of the fuel debris from the spent fuel measures (within 10 years) •Significantly reduce pool (30 to 40 years in the radiation releases future) (within 2 years) Started first fuel removal from Unit 4 SFP on Nov. 18, 2013 6 ©International Research Institute for Nuclear Decommissioning
  • 7. Planned Schedule for Unit 1-4  Removal of fuel at Unit 4 was started from November 2013 (one month earlier than the initial plan).  Retrieval of fuel debris will be started from the first half of FY 2020 (the earliest case). Unit 1 Nuclear Fuel removal from SFPs (target schedule) First half of FY2017(the earliest case) ~ Second half of FY2017 Unit 2 Second half of FY2017(the earliest case) ~ First half of FY2023 Unit 3 First half of 2015 Unit 4 November 2013 Fuel debris retrieval (target schedule) First half of FY2020 ~ Second half of FY2022 First half of FY2020 ~ Second half of FY2024 Second half of FY2021(the earliest case) ~ First half of FY2023 ー (one month earlier than the initial plan) 7 ©International Research Institute for Nuclear Decommissioning
  • 8. Steps for Fuel Debris Retrieval on the premise of the Existing Flooding Method  The most reliable method of fuel debris retrieval at present is considered to remove the fuel debris by keeping them covered with water to reduce the risk of radiation exposure during the work process. HP :Technical holding points Phase 1 2012 Phase 2 Phase 3 By 1st half in 2020 2013 Step 1: Reactor Building Decontamination Leaking Location (Lower PCV) HP Identified Step 2: Enough Leaking Location achieved Identified HP Water Level HP (Upper PCV) Step 5: PCV Investigation from outside PCV Internal Inspection and Sampling Step 3: Lower PCV Repair Step 4: PCV Half Flooding Step 6: Upper PCV Repair 8 Enough After 20-25 years Defueling HP Water Level HP Method achieved Developed Step 8: RPV Internal Inspection and Sampling ▽Open RPV Step 7: PCV/RPV Full Flooding Step 9: Defueling Debris processing/ disposal methods HP developed ©International Research Institute for Nuclear Decommissioning
  • 9. Building Internal Decontamination DS pit SFP Equipment hatch RPV Fuel debris PCV airlock Torus Steam dryer Steam-water separator Turbine Building  Development of remotely operated decontamination devices that meet the contamination conditions in the field in order to improve the work environment such as surveying and repairing leaks in the PCV to prepare for fuel debris retrieval. Waterproofing Leak High-pressure water jet decontamination device Dry ice blast decontamination device 9 Blasting/collecting decontamination device ©International Research Institute for Nuclear Decommissioning
  • 10. Open air Robot for Inspection and Repair of PCV Device ① Survey robot of Vent pipe joint ② Quadruped walking robot ( &Flat vehicle ) ③ Robot for surveying the upper part of the S/C Characteristics Approach joints between bent pipes and the D/W from between the vent pipe and concrete wall with adhering itself to the surface of the outside of the vent pipe Be used to ascertain conditions inside the S/C, such as the presence of leaks from near the area beneath the vent pipe. Check for leaks from structures at the top of the S/C, which is high up (Approx. 3m at its highest), after accessing it from the catwalk outside the Torus. ① Survey robot of Vent pipe joint PCV ③ Robot for surveying the upper part of the S/C Close-up camera (with platform) Extendable mast PCV Vent pipe ベント管 Robot ロボット adhesion location 吸着位置 ② Quadruped walking robot Quadruped walking robot Vent pipe sleeves Sand cushion drain lines PCV Ven t 1 pipe 3 S/C 2 500 mm 900 ~ 3000 mm crawlers Torus survey 4 Flat vehicle Bellows cover Approx. 約 6 10 5 Survey robot ©International Research Institute for Nuclear Decommissioning
  • 11. Submersible Robot Develops device Robot for ④ Submersible robot surveying submersed ⑤ Floor walking torus walls robot ⑥ Robots for surveying the bottom part of the S/C ⑥ Robots for Surveying the bottom part of the S/C Characteristics Be used to check for damages at building penetration seals with remotely operated (used in very narrow places) by an operator viewing a video screen. Walk on the floor underneath the water and uses ultrasound to check for leaks in distant places. Check for damages on the outside of the S/C, on structures on the outside and on penetration pipes, with adhering itself to the outer surface of the S/C ④ Submersible robot to Movable camera Ascent/descent thrusters (front, back, left, right) Magnetic Observation camera wheels S/C Inner circumference of S/C Seismic resistant support m Exa ve tra bot f ro ute o o r ple ロボット l Up down Column support Outer circumference of S/C Camera PCV Ven t pip e 1 3 S/C ⑤ Floor walking robot Vertical thrusters Horizontal Thrusters 2 4 6 11 Forward thrusters Horizontal thrusters 5 Taurus walls S/C Tracer Ultrasound Taurus Walls Ultrasonic sensor (sonar) Crawlers Camera S/C Robot Robot ©International Research Institute for Nuclear Decommissioning
  • 12. Investigation of the PCV Interior  Inserting survey equipment through Unit 1 X-100B ✓ A crawler device that can transform and move along gratings stably after being inserted into the PCV from narrow access pipe (X-100B penetration seal: inner diameterφ100mm). [PCV cross-section] X-100B Existing Guide pipe [D/W 1FL] D/W 1F Grating A enlarged view X-100B Existing guide pipe Cable Guide pipe When traveling along guide pipe Dosimeter CCD camera Thermometer Running device A section PCV Grating D/W subfloors Transformation X-6 : Survey route ( proposed ) High radiation level PCV internal survey route (proposed) 12 When traveling on grating Device concept image ©International Research Institute for Nuclear Decommissioning
  • 13. Steps for Fuel Debris Retrieval on the premise of the Existing Flooding Method  The most reliable method of fuel debris retrieval at present is considered to remove the fuel debris by keeping them covered with water to reduce the risk of radiation exposure during the work process. HP :Technical holding points Phase 1 2012 Phase 2 Phase 3 By 1st half in 2020 2013 Step 1: Reactor Building Decontamination Leaking Location (Lower PCV) HP Identified Step 2: Enough Leaking Location achieved Identified HP Water Level HP (Upper PCV) Step 5: PCV Investigation from outside PCV Internal Inspection and Sampling Step 3: Lower PCV Repair Step 4: PCV Half Flooding Step 6: Upper PCV Repair 13 Enough HP Water Level achieved After 20-25 years Defueling HP Method Developed Step 8: RPV Internal Inspection and Sampling ▽Open RPV Step 7: PCV/RPV Full Flooding Step 9: Defueling Debris processing/ disposal methods HP developed ©International Research Institute for Nuclear Decommissioning
  • 14. Request for Information (RFI) of Innovative Approach for Fuel Debris Retrieval Background of RFI: To ensure multi-fold approach, as well as to enable technological breakthroughs, collective knowledge and experience via interactive platform is to be pursued. This will also benefit enhancement of safety and decommissioning of nuclear Schedule: facilities all over the world. 2013 ✓November 29 : Website is open ✓Mid December : Procedure for RFI is to be announced 2014 ✓End of January : Deadline of RFI ✓Feb/March : Review of responses 14 ✓ ©International Research Institute for Nuclear Decommissioning
  • 15. Topics for RFI Topic-A: Internal PCV/RPV Status Investigation ✓A-1: Conceptual study on innovative approaches ✓A-2: Technologies for internal PCV/RPV status investigation Topic-B: Fuel-Debris Retrieval from PCV/RPV ✓B-1: Conceptual study on Innovative approaches [Example] Conceptual idea of retrieving fuel debris from PCV and RPV without submerging PCV, the comparison to the submersion scenario, etc. (a) Accessing and removal of fuel debris from Top side of PCV/RPV under water. (b) Accessing and removal of fuel debris from Top side of PCV/RPV in atmospheric condition. (c) Accessing and removal of fuel debris from lateral side of PCV/RPV in atmospheric condition. Innovative approach (d) Accessing and removal of fuel debris from bottom side of PCV/RPV in atmospheric condition. ✓B-2: Technologies for Fuel-Debris Retrieval 15 ©International Research Institute for Nuclear Decommissioning
  • 16. Program Structure MAR/APR, 2014 PHASE 1 Theme A-1 RFI for C/S B-1 Theme RFI for F/S A-2 B-2 MAR/APR, 2015 PHASE 2 RFP for C/S Selection RFP for F/S Selection PHASE 3 RFP F/S Funding R&D project RFP Funding Selection Selection (3 to 5 projects) (3 to 5 projects) if not selected C/S or R&D No Funding Others R&D project Funding C/S Funding Project Workshop #1 (potential) (potential) Preliminary/Design Funding Selection RFP (potential) R&D project Funding Selection (potential) Project Workshop #2 RFP Visit IRID WEB for more information! http://www.irid.or.jp http://www.irid.or.jp/fd (for RFI) 16 ©International Research Institute for Nuclear Decommissioning
  • 17. Thank you for your attention 無断複製・転載禁止 技術研究組合 国際廃炉研究開発機構 ©International Research Institute for Nuclear Decommissioning