Report by the Joint-Core Team for the Establishment of Technology Bases
Required for the Development of a Fusion DEMO Reactor- Chart of Establishment of Technology Bases for DEMO -The Joint-Core Team for the Establishment of Technology Bases
Required for the Development of a Fusion DEMO Reactor

Report by the Joint-Core Teamfor the Establishment of Technology Bases
Required for the Development of a Fusion DEMO Reactor– Chart of Establishment of Technology Bases for DEMO –The original version in Japanese: 19 January 2015
The English-language version: 1 March 2015

Joint-Core TeamH.Yamada1, A.Ozaki2, R.Kasada3, R.Sakamoto1, Y.Sakamoto4, H.Takenaga4,
T.Tanaka1, H.Tanigawa4, K.Okano5, K.Tobita4, O.Kaneko1, K.Ushigusa4
1

National Institute for Fusion Science
Japan Atomic Industrial Forum
3
Institute of Advanced Energy, Kyoto University
4
Japan Atomic Energy Agency
5
Keio University
2

Abstract
In accordance with the request of the Working Group on Fusion Research, the Nuclear Scienceand Technology Committee, the Subdivision on R&D Planning and Evaluation, the Council
for Science and Technology, the Ministry of Education, Culture, Sports, Science andTechnology, the joint-core team has worked on strategy for establishment of technology bases
required for development of a fusion DEMO reactor by taking into account the progress of the
ITER project, the BA activities, and academic researches such as the Large Helical Device.
Based upon the previous report on Basic Concept of DEMO and Structure of Technological
Issues (original version in Japanese issued on the 18th, July, 2014), the timeline of researchand development to resolve technological issues has been shown from the integrated view.
This overview is referred to as “Chart of Establishment of Technology Bases for DEMO”. The
highlighted and emergent requirements which have been identified in this Chart are remarked.
This report is documented by the joint-core team of members and experts from the National
Institute for Fusion Science, the Japan Atomic Energy Agency, Kyoto University, the Japan
Atomic Industrial Forum, Inc., and Keio University.
The electric file is available at http://www.naka.jaea.go.jp/english/index.html

Keywords:
fusion DEMO reactor, reactor design, technology bases, technological issues, roadmap,
timeline, critical pathReport by the Joint-Core Teamfor the Establishment of Technology Bases
Required for the Development of a Fusion DEMO Reactor- Chart of Establishment of Technology Bases for DEMO The original version in Japanese: 19 January 2015
The English-language version: 1 March 2015

Agenda1. Introduction .......................................................................................................................... 1
2. Timeline of Research and Development to Resolve Technological Issues ....................... 3
2-1. Most Important Milestones ...................................................................................... 3
2-2. Level of Completion of DEMO Design ................................................................... 5
2-3. Chart of Establishment of Technology Bases for DEMO .................................... 6
3. Highlighted Remarks in Establishment of Technology Bases for DEMO..................... 15
4. Summary ............................................................................................................................. 18

1. Introduction
The Working Group on Fusion Research, the Nuclear Science and Technology Committee, theSubdivision on R&D Planning and Evaluation, the Council for Science and Technology, the Ministryof Education, Culture, Sports, Science and Technology (hereafter referred to as “MEXT”) in the 7thterm (March 2013 – February 2015) has discussed establishment of the function to compose strategy
for the development of a “DEMOnstration fusion reactor” (hereafter referred to as “DEMO”) withintegrated viewpoints towards the next Fourth Phase Program with a core project of DEMO [1],which has the goals of technological demonstration and economic feasibility of fusion energy. Thisfunction will be the core engine for the establishment of technology bases for the development of
DEMO.
Based upon thorough discussions, the Working Group on Fusion Research requested, at the 37th
meeting on 3 July 2013, the Fusion Research and Development Directorate, the Japan Atomic Energy
Agency (hereafter referred to as “JAEA”), and the National Institute for Fusion Science (hereafterreferred to as “NIFS”), which are implementing bodies of large projects, to take the leading role informing the joint-core team for the establishment of technology bases required for the development of
DEMO [2].
The terms of reference of this joint-core team for the establishment of technology bases requiredfor development of DEMO defined by the Working Group on Fusion Research are as follows [2]:1. Mission
To develop strategy for the establishment of technology bases required for the development of
DEMO by taking into account the progress of the ITER project, the Broader Approach (BA) activities
and academic research such as the Large Helical Device (LHD), and standing on the consensus in theJapanese fusion community.
2. Issues
1)

Concept of DEMO premised for investigation

2)

Activities requiring commitment and their goals (research activities, investigation activities)

3)

Scientific and technological review works for the above mentioned activities

3. Notes
1) To conduct wide cooperation and exchange with researchers and technological experts in industry,
government, and academia so as to stand on consensus in the Japanese fusion community. In
particular, expansion of cooperation and exchange between scientific societies is encouraged.
2) In order to refer a political deliberation to the Working Group on Fusion Research, a representativeof the joint-core team is requested to report on the status of activities routinely.

1

In accordance with the request by the Working Group on Fusion Research, the joint-core team,whose members are listed at the end of this report, was launched and has engaged with assigned issues.
The joint-core team has reviewed the analyses in “Future Fusion Research and Development Strategy”(hereafter referred to as “Future Fusion R&D”) determined by the Atomic Energy Commission’s
Advisory Committee on Nuclear Fusion in October 2005 [1] and other reports to date and has taken
into account the most recent scientific and technological achievements and their latest prospects.
Summary of issues in the investigated strategy for the establishment of technology bases required for
DEMO was reported as an interim report at the 38th meeting of the Working Group on Fusion
Research (24 February 2014) [3] (hereafter referred to as the “Interim Report”). Based upon the“Interim Report”, further analysis has been made by the joint-core team by taking account ofcomments at the Working Group on Fusion Research, and complied documentation was reported at the
41st meeting of the Working Group on Fusion Research (24 June 2014) [4]. The report finalized byfurther amendments due to comments on this 41st meeting and required revision dated 18 July 2014
(hereafter referred to as the “Joint-Core Team Report (Basic Concept of DEMO and Structure ofTechnological Issues)”) was submitted to the 42nd meeting of the Working Group on Fusion Research(1 August 2014) [5].
Based upon the basic concept of DEMO and structure of technological issues documented in the“Joint-Core Team Report (Basic Concept of DEMO and Structure of Technological Issues)” [5], thejoint-core team has sorted out tasks regarding the development of the design of DEMO, and theresearch & development programs to resolve the issues and to provide the required evidence tosupport the design into the consistent timeline, as a whole with attention paid to the Working
Break-down Structure (WBS). Then the overview picture to make the linkage of all related programs
visible has been proposed.
The Roadmap of DEMO Development will be defined by the Japanese government in future.
Since the proposed overview picture will make an essential contribution to formulation of thecomprehensive strategy, which will be the main body of the Roadmap of DEMO Development, thisoverview picture is referred to as Chart of Establishment of Technological Bases for DEMO. This
report describes this chart and highlighted remarks recognized in the process to formulate this chart.
The joint-core team has promoted communication with the community in order to fulfil theremarks defined in 3.Notes, 1) of the term of reference and has proceeded with the examination withthe formulation of Chart of Establishment of Technological Bases for DEMO based upon diversified
opinion from the community. The joint-core team has had more than 30 open meetings in these 18
months. Opinions collected after the publication of the “Joint-Core Team Report (Basic Concept of
DEMO and Structure of Technological Issues)” are attached to the present report of theJapanese-language version as reference materials (not available in this English-language report). Also,2

in order to stimulate the future vision in common in the community, the article to describe theprospected direction towards DEMO from the perspective of the administrative authority and thejoint-core team has been published in Journal of Plasma and Fusion Research [6].

2. Timeline of Research and Development to Resolve Technological Issues
2-1.

Most Important Milestones
Fundamental concept for the changeover to the DEMO phase (Fourth Phase Program) is

documented in “Future Fusion R&D”, where “Performance goal by check and review in the interimphase” (hereafter referred to as “Intermediate C&R”) and “Transition conditions to the DEMO phase”(hereafter referred to as “Assessment of Transition Conditions”) are defined as shown in Check andReview Items in Future Fusion R&D (draft) (see Table I). These two points are the most importantmilestones in the timeline.
Table I

Check and Review Items in Future Fusion R&D (draft)from “Future Fusion R&D”, The Atomic Energy Commission’s Advisory Committee on Nuclear
Fusion, October 2005
Performance goal by check andTransition conditions

review in the interim phaseto the DEMO phase

1. Demonstration of burn

 Lay out plans for achieving the Demonstration of maintenance ofcontrol in self-heating

technological goals of experimental

plasma with Q20 (for duration

regime using

reactor based upon the actual ITER

longer than about several 100 s)

Issuesand burn control in ITER

experimental reactor
2. Realization of Lay out plans for achieving the Demonstration of non-inductive

non-inductive

goals based upon the actual ITER

current drive plasma with Q5 (forduration longer than about 1,000 s)

steady-state operation
with Q5 using
experimental reactor
3. Establishment of Complete ITER facilities

 Establishment of integration

integration technology

 Acquire integration technology

technology through the operation

using experimental

related to manufacturing,and maintenance of ITER.

reactorinstallation, and adjustment ofVerification of safety technology

components
4. Establishment of Conduct ITER support research Attainment of sustaining

high-beta steady-stateand preparatory research for

high-beta (n=3.5-5.5) plasma in3

operation method in orderhigh-beta steady-state plasma andcollision-less regime in National

to obtain economicallaunch research using National

Centralized Tokamak.

prospects

Centralized Tokamak

5. Development of Complete establishing Demonstration of tritiummaterials and fusion

technological basis for power

breeding and recovery functions,

technologies related togeneration blanket. Complete

removal of heat and power

DEMO reactor

manufacturing test components togenerating blanket in a low-fluence

be used for the functional test in

DT experiment on ITER

ITER

 Completion of verification of Acquire reactor irradiation data ofheavy irradiation data of reduced

reduced activation ferritic steels up

activation ferritic steels up to a

to 80dpa and determine testlevel of 80 dpa

materials to be used in theirradiation test under neutron
irradiation environment similar tothat of fusion reactor
6. Conceptual design of  Determine the overall goal of Completion of conceptual design

DEMO

DEMO

of DEMO consistent with the Conduct preliminary work on thedevelopment of fusion plasma

conceptual design of DEMO

research and fusion technology

 Make requests for the required
development of fusion plasma
research and fusion technology

As described in the “Joint-Core Team Report (Basic Concept of DEMO and Structure ofTechnological Issues)”, it is relevant to elaborate the timeline of technological development with thepresumption of the Intermediate C&R around 2020 when the first plasma of ITER is expected and theAssessment of Transition Conditions around 2027 when the fusion burning with deuterium and tritium(DT burning) fuels will be demonstrated in ITER.
This means that the ITER project is the ticking clock of the timeline and it is beyond question thatits steady progress is indispensable. Since the progress of the ITER project has a great impact on thedevelopment of the timeline, it is necessary to deepen discussions about an appropriate time andcriteria of Intermediate C&R and the Assessment of Transition Conditions by revisiting the grounds ofthe items described in Table I based upon the common understanding of how much and when theachievement is prospected by the ITER project.

4

2-2.

Level of Completion of DEMO Design
In case commercialization of fusion energy is sought in the middle of the 21st century, the term

between the Intermediate C&R and the Assessment of Transition Conditions should be defined as the
preparation term towards the DEMO phase (Fourth Phase Program) and the start of engineering R&D
at the proper level in response to Intermediate C&R should be promoted for early realization of
DEMO. Intermediate C&R requests the start of the operation of ITER as well as maturity ofconceptual design of DEMO. In “Future Fusion R&D”, the goal at Intermediate C&R is defined as (1)to determine the overall goal of DEMO, (2) to conduct preliminary work on the conceptual design of
DEMO, and (3) to make requests for the required development of fusion plasma research and fusion
technology, as shown in Table I.
During the coming several years until the Intermediate C&R, ITER and JT-60SA are underconstruction, and development on fusion technologies remains on a limited scale. These situations
imply that limited amount of technical information will be provided to the DEMO design activity,
albeit input expected on know-how accumulated throughout the construction of these machines.
However, anticipating that most of all of the R&Ds are embarked upon or expanded after theIntermediate C&R along technical requirements and basic specifications defined by the DEMO design
activity in the coming several years, it is an urgent matter to establish and reinforce the design activity
to address the following issues till Intermediate C&R:
 Operation plan of DEMO* Basic concept and design parameters Components and facilities of DEMO plant and their specifications
 Development of software and databases for DEMO design
 Primary cost assessment (to be rationalized after Intermediate C&R)
 Safety design guidelines
 Management and disposal scenario of radioactive-waste Definition of R&D issues to be implemented for decision on DEMO concept
 Resources procurement strategy including initially loading tritium*) To elaborate upon the operation plan and the life of DEMO based on the technology and data which
need to be developed or accumulated during the in-service period.
Technology and data envisaged: operational technique, validation of plasma prediction codes,
operational characteristics (output stability, controllability, and operational margins), failure data ofplant components and auxiliary facilities, plant operation and maintenance, worker dose data, handlingand management of wastes, environmental monitoring data in normal operation, development ofadvanced technology for commercialization (blanket, divertor and materials).
It will be necessary at the Intermediate C&R that establishment of technological bases to support5the overall goal of DEMO and the conceptual design of DEMO by evidence is predictable. And then,consistency between the design of DEMO and achievement/evidence by the research and development
programs will be needed at the Assessment of Transition Conditions.

2-3.

Chart of Establishment of Technology Bases for DEMO
Based upon examination described in the “Joint-Core Team Report (Basic Concept of DEMO and

Structure of Technological Issues)”, in particular, the structure of technological issues in the following
11 elements of DEMO,(1)Superconducting Coils(2)

Blanket(3)

Divertor(4)

Heating and Current Drive Systems(5)

Theory and Numerical Simulation Research(6)

Reactor Plasma Research(7)

Fuel Systems(8)

Material Development and Establishment of Codes and Standards(9)

Safety of DEMO and Safety Research(10) Availability and Maintainability(11) Diagnostics and Control Systems,
all related research and development programs are organized in the Chart of Establishment ofTechnological Bases for DEMO around the development of the design of DEMO as the primary axis
with attention paid to required evidence to support the maturity of the design of DEMO andconsistency in the timeline.
The stages of the design have been defined based upon the fundamental concept in “Roadmap andTechnological Strategy towards Commercialization of Fusion Energy” [7] by the Fusion Energy
Forum as follows: till the Intermediate C&R: Basic design (Pre-concept)

 till the Assessment of Transition Conditions: Basic design and R&D activity
supporting conceptual design

 till the decision of construction of DEMO

: Engineering design and R&D activity
supporting engineering design

 after the decision of construction of DEMO

: Construction and manufacture design

The outline of the development of the design of DEMO, and newly required facilities andplatforms which have been pointed out in the “Joint-Core Team Report (Basic Concept of DEMO and
Structure of Technological Issues)” are extracted from the entire chart and shown in Fig. 1. Figure 1 is6the summary of Chart of Establishment of Technological Bases for DEMO consisting mainly of major
projects, development of the design of DEMO and newly required R&D facilities and platforms in thefollowings:
 Test facility of large-scale superconducting coils which fulfils the specification of DEMO (Testfacility of superconducting conductor and coils with around 16 T)
 R&D facilities for blanket (development of ITER-TBM (Test Blanket Module), post-irradiation
experiments, development of waste disposal technology)
 Test facility of real-scale performance of NBI (including expansion of ITER NBTF (Neutral
Beam Test Facility1))
 Supercomputer resource Handling facility for large quantities of tritium Lithium plant (collection and purification facility)
 Intensive fusion neutron source, fusion neutron source (including expansion of IFMIF/EVEDA(International Fusion Material Irradiation Facility / Engineering Verification and Engineering
Design Activity))
 R&D facility for large-scale component maintenance.
In addition,
 R&D facility for divertor including innovative concept
is added since it is necessary to elevate the technological maturity of divertor most from the present
level in order to assess technological feasibility of DEMO, as mentioned below.
Notation of Chart of Establishment of Technological Bases for DEMO
By arranging the program packages shown as the structure of the issues in “Joint-Core Team
Report (Basic Concept of DEMO and Structure of Technological Issues)” as tasks which will be
developed to WBS, the overview picture of development of all related programs is made visible.
Notation is as follows:(1) Preparation phase of the task is shown in a light colour bar and its full-scale development isshown in a deep colour bar.
(2) In case there is strong linkage and/or overlap with other elements or tasks in other elements,
linked counter items are documented in the column of “Link to other tasks”.
(3) Milestones are marked by the following symbols.
 open diamond

: completion of preparation for necessary condition of the Intermediate
C&R. Note that further improvement is continued.

 closed diamond : completion of task and meeting the Intermediate C&R.
 open circle

: completion of preparation for necessary condition of the Assessment ofTransition Conditions. Note that further improvement is continued.

1

NBTF is now under construction in Padova, Italy, in order to demonstrate the real full performance of theneutral beam injector for ITER.

7 closed circle

: completion of task and meeting of the Assessment of Transition
Conditions.

(4) Remarks for the task are inserted by the text box without a frame border.
(5) Remarks for the platform such as facility are inserted by the text box with a frame border.
(6) Linkage and interference between tasks in the same element are shown by bidirectional arrows.
Complete picture of Chart of Establishment of Technological Bases for DEMO is shown in Fig. 2.

8

2010s
14

15

2020s
16

17

18

Ongoing(projects

19

20

21

22

23

24

Start operation

ITER

25

2030s
26

27

28

29

30

31

32

33

34

35

Start DT operation

Construction

ITER%TBM

TBM #1

TBM #2

TBM #3

TerminateBA)(except)for)JT%60SA)
Start operation

JT%60SA

Construction

Start deuterium experiment

LHD

Research(and(development(toward(DEMO
DEMO)Reactor)design

Intermediate C&R
Basic design (Pre-concept)

Assessment of transition conditions
Basic design

Engineering design

Const.
Manufact.
designConst-ructionTest)facility)of)large)scale)superconducting)coils))(16)T%grade)test)for)conductor)
Test)facility)of)large)scale)superconducting)coils))(16)T%grade)coil)R&D)facilities)for)blanket)of)ITER%TBM,)post%irradiation))experiments,)development)of)waste)disposal)technology)Test)facility)of)real%scale)performance)of)NBI))(including)usage)of)ITER)NBTF)

Cold test
NBTF const.
(ITER)

Tritium experiments using a fusion neutron source
Post-irradiation experiments with a module scale

NBTF operation (ITER)

NBI test for DEMO reactor

Supercomputer)resource)after)the)present)BA)activities
Handling)facility)for)large)quantities)of)tritium
Lithium)plant)(collection)and)purification)facility)
Fusion)neutron)sources)including)usage)of)IFMIF%EVEDA

DesignConstruction

IFMIF)or)equivalent)intense)fusion)neutron)sources

Design・Construction

Operation

Concept・Design
Construction

Demonstration of operation

20 dpa irradiation
Design・ConstructionR&D)facility)for)large%scale)component)maintenanceR&D)facility)for)divertor)including)innovative)concepts

Fig. 1

Summary of Chart of Establishment of Technological Bases for DEMO consisting of major projects,
development of the design of DEMO and newly required R&D facilities and platforms.
9Inter.'C&R

Link to other task

2010s
14

15

Engineering'
DesignConst.'&'manufact.'
Design2020s
16

0 Reactor.System.Design
0.1

Phase'
trans.

Basic'Design

17

18

19

20

21

22

23

Pre=CDA

Conceptual.design

24

25

2030s
26

27

28

CDA

29

30

31

32

33

34

35

EDA

Intermediate*C&R*

0.1.1 Design'guidelines'and'requirements

Required*performance*

0.1.2 Reactor'concept

Detailed*conceptual*design*

0.1.3 Maintenance'and''torus'configuration

1. Magnet
10. Maintenance0.1.4 Component'and'equipment'design'

3. Divertor
2. Blanket, etc.

0.1.5 Plasma''physics'design

6. Reactor Plasma
4. Heating&CD
5. Theory&Sim.
11. Diag&Control

0.1.6 Plant'and'auxiliary'systems'concept

7. Fuel systems
10. Maintenance0.1.7 Safety'guidelines

9. Safety

0.1.8 Physics,'engineering'and'materials'DB

8. Materialincl.*DEMO=TBM*and*advanced*divertor*

0.1.9 Initial'cost'estimate

Technical*specs*
Development*targets*
Other*items*

0.2

Other*items*

Start*substan1al*scale*R&D*

Engineering.design
0.2.1 Plasma'physics'design・Diagnostics'and'control

6. Reactor Plasma
4. Heating&CD
5. Theory&Sim.
11. DIag&Control

0.2.2 Reactor'design

1. Magnet
10. Maintenance0.2.3 Component'and'equipment'design'

3. Divertor
2. Blanket, etc.

0.2.4 Plant'and'building'design

7. Fuel systems
10. MaintenanceStart*full=scale*R&D*

Detailed*specs*

0.2.5 Power'generation'system'design
0.2.6 Physics,'engineering'and'materials'DB

8. Material
6. Reactor Plasma

0.2.7 Secondary'cost'estimate
0.2.8 Design'rules,'codes'and'standards

Design*standard*for*structure*

0.2.9 Safety'requirements・Analysis・Assessment

Dra^*standard*

9. Safety

Basic*research*

0.2.10 Safety'regulations

Introductory*inves1ga1on*

Development*targets*

Regula1on*policy*

Other*items*

0.3

Construction.and.manufacture.design

Consolida1on

0.3.1 Operational'scenario・Diagnostics'and'control

6. Reactor Plasma
4. Heating&CD
5. Theory&Sim.
11. Diag.&Control

0.3.2 Reactor'design

1. Magnet
10. Maintenance0.3.3 Component'and'equipment'design'

3. Divertor
2. Blanket, etc.

0.3.4 Plant'and'building'design

7. Fuel
10. Maintenance

Final*design*

0.3.5 Power'generation'system'design
0.3.6 Materials'DBaccumulation'of'14MeV'n'irradiation'data
0.3.7 Safety'assessment

8. Material
6. Reactor Plasma
9. Safety

0.3.8 Safety'regulations
Complete*legisla1on*

0.3.9 Construction'site'assessment・Site'selection

Select*candidate*sites*

Link to other task

2010s
14

15

Decide*construc1on*site*

2020s
16

17

18

19

20

21

22

23

24

25

Complete*licensing*

2030s
26

27

28

29

30

31

32

33

34

35

1 Superconducting.coils
1.1Superconducting.coils.(TF,.PF,.CS)
1.1.1 Conceptual'design

Reactor design 0.1.3, 0.1.4

1.1.2 Engineering'design

Reactor design 0.2.2, 0.2.3

Pre=conceptual*design*Reﬂect*the*lessons*learned*from*the*construc1on*of*ITER*and*JT=60SA**

Conceptual*design**
Reﬂect*the*lessons*learned*from*the*opera1on*of*ITER*and*JT=60SA**

Review*the*issues**based*upon*the*outcomes*of*
the*pre=conceptual*design*and*the*prospect*of*material*development*

1.1.3 Decision'on'R&D'strategy
1.1.4 Superconducting'materials

 1.1.4.1$$Nb3Sn$(Improve$Jc)

Reﬂect*the*lessons*learned*from*ITER*

 1.1.4.2$$Nb3Al$(Increase$production$length)

Collabora1on*with*the*development*
for**other*purposes*

to*use**in*TF*

 1.1.4.3$$NbTi$$(PF) 1.1.4.4$$ReBCO$(Utilization)

Development*for*performance*improvement*for*a*commercial*reactor*
Target*Jc:*
J >800 1000A/mm2*@13

Reﬂect*the*lessons*learned*from*ITER*
Collabora1on*with*the*development*
for**other*purposes*

use*as*applicable,*such*as*bus*bars*

1.1.5 Conductor'performance'improvement'(TF,'CS,'PF)

Reﬂect*the*lessons*learned*
from*ITER*

 1.1.5.1$$Conductor$test$facility

Preliminary*study*

U1lize*exis1ng*facili1es*for*ITER*

Upgrade*the*exis1ng*
facili1es*as*necessary* 1.1.5.2$$Conductor$test$sample$manufacturing/testing
1.1.6 Structural'material'development'(High'strength)

Preliminary*study*

1.1.6.1$$JJ1$(TF)

Reﬂect*the*lessons*learned*from*ITER*

 1.1.6.2$$JK2$(CS)Reﬂect*the*lessons*learned*from*ITER*

 1.1.6.3$$SUS316LN

Reﬂect*the*lessons*learned*from*ITER*

16T*for*TF?,*what**about**CS*and*PF?*Development*for*performance*improvement*for*a*commercial*reactor*

 1.1.6.4$$Innovative$$high$strength$material

Target*current*ra1ng:*
100kA*@13 16T*for*TF?,*what**about**CS*and*PF?*

Coil*test*at*appropriate*scale*might*be*required*before*the*ﬁnal*selec1on*of*materials*when*higher*magne1c*ﬁeld*is*necessary*and/or*innova1ve*conductor*is*a*candidate*

Design*stress:*
800MPa*for*TF?,*what**about**CS*and*PF?*Development*for*performance*improvement*for*a*commercial*reactor*

1.1.7 Insulation'materials

Preliminary*study*

 1.1.7.1$$Radiation$resistant$insulation$materials

Reﬂect*the*lessons*learned*from*ITER*

 1.1.7.2$$Radiation$resistant$resin

Reﬂect*the*lessons*learned*from*ITER*

Neutron*ﬂux:*?*n/m2	
Max.*Dose*:*?*Gy*

based*upon*the*outcomes*of*the*conceptual*design*and*material*development*

1.1.8 Final'selection'of'materials'to'be'used
1.1.9 Production'technologies'development

 1.1.9.1$$Mass$production$of$superconducting$materials

including**produc1on*demonstra1on* 1.1.9.2$$Mass$production$of$superconductors

including**produc1on*demonstra1on* 1.1.9.3$$Coil$manufacturing$technologies

including**model*coil*manufacturing* 1.1.9.4$$Mass$production$of$structural$materials$(Coil$case)including**produc1on*demonstra1on* 1.1.9.5$$Support$structure$manufacturing$technologies$(Coil$case)including**model*manufacturing* 1.1.9.6$$Coil$test$facility
1.1.10 Manufacturing'design

Reactor design 0.3.2, 0.3.3

Fig.2

Chart of Establishment of Technological Bases for DEMO (1)
10

1.2

Coil.support.structures
1.2.1 Conceptual'design

Reactor design 0.1.3, 0.1.4

1.2.2 Engineering'design

Reactor design 0.2.2, 0.2.3

Pre=conceptual*design*
Reﬂect*the*lessons*learned*from*the*construc1on*of*ITER*and*JT=60SA**

Conceptual*design**
Reﬂect*the*lessons*learned*from*the*opera1on*of*ITER*and*JT=60SA**

1.2.3 Decision'on'R&D'strategy

Review*the*issues**based*upon*the*outcomes*of*
the*pre=conceptual*design*and*the*prospect*of*material*development*

1.2.4 Structural'material'development'(High'strength)

based*upon*the*outcomes*of*the*conceptual*design*and*material*development*

1.2.5 Final'selection'of'materials'to'be'used
1.2.6 Manufacturing'technologies'development

including**model*manufacturing*

1.2.7 Manufacturing'design

1.3

Reactor design 0.3.2, 0.3.3

Cryogenic.System
1.3.1 Conceptual'design

Reactor design 0.1.4, 0.1.6

1.3.2 Engineering'design

Reactor design 0.2.3, 0.2.4

1.3.3 Manufacturing'design

Reactor design 0.3.3, 0.3.4

Link to other task

Conceptual*design**
Reﬂect*the*lessons*learned*from*the*opera1on*of*ITER*and*JT=60SA**

Pre=conceptual*design*
Reﬂect*the*lessons*learned*from*the*construc1on*of*ITER*and*JT=60SA**

2010s
14

2020s

15

16

17

18

19

20

21

22

23

24

2030s

25

26

27

28

29

30

31

32

33

34

35

2 Blanket
2.1

Design.of.DEMO.blanket.system

2.2

Expansion.of.basic/reference.data
2.2.1 Compatibility,'vapor'pressure,'water/vaporchemical'
reaction'rate'etc.
2.2.2 Compile'data'base'for'use'in'the'design'activities
properties'of'packed'pebble'bed'etc.

Reactor design 0.1.3

Const.*&*manufact.*Design

Safety 9.2.3

Design*support*by*
experiments*and*compliant**
with*standards/criteria*

Reactor design 0.1.4
Safety 9.2.3

2.3

Validated.reference.data.base.
Data.base.supporting.design.standards

2.4

Demonstration.of.integrated.functions.of.blanket.
system.in.fusion.environment

Reactor design 0.1.8
Code & standards 8.1.5

2.4.1 PreYconceptual'design'of'DEMO'blanket'and'tritium'system

Experimental*
valida1on*of*data**

Reactor design 0.1.4

2.4.2 Conceptual'design'of'blanket'system

Feedback*from*R&D*

SupportEngineering*design*

2.4.3 Test'plans'for'TBM'system'and'additional'test'facilities
2.4.4 Confirmation'of'soundness'to'heat'and'pressure'loads,'and'of'
response'to'EM'loads
2.4.5 Proven'manufacturing'technology'for'blanket'system
2.4.6 Complete'technological'bases'of'blanket'system'including'design'and'manufacturing'technology

2.5

Demonstration.of.tritium.breeding.and.recovery

1st*TBM*and*ancillary*systems*

2nd*TBM*

Reactor plasma 6.13
Material 8.1.2

demonstra1on*of*electric*
power*genera1on*

Theory&Sim. 5.2
Fuel systems 7.1

2.5.2 Understandings'of'tritium'behavior
Establishment'of'tritium'technology

ITER*D,*T*phase

ITER*H*phase

supplement**to*TBM*experiments*

2.5.1 Design'and'schedule'of'irradiation'and'tritium'experiments

Sophis1cated*understandings*about*
responses**of*cooling*and*T*recovery*
systems*and*tri1um*behavior*

TPL,*Tri1um*facility*in*Rokkasho*
Cold*test*facili1es*

2.6

Prospect*for*tri1um*breeding*capability*in*DEMO*

Heat*load,*corrosion*and*safety*experiments,*in=vessel*

experiment*in*JT60SA*

T*breeding*and*recovery*test*using**
neutron*source*

Blanket*fabrica1on*technology,*dissimilar*material*welding,*coolant*ﬂow*
through*complicated*channels,*transfer*and*recovery*of*hydrogen*and*heat,*etc.*

Development.of.advanced.blanket.system
2.6.1 Examination'on'blanket'functions'and'properties'with'small'test'devices.

Simultaneous*examina1on*of*plural*func1ons,*technologies*and*phenomena,*and*acquisi1on*of*fundamental*design*data*

2.6.2 Integrated'circulation'loop'tests'
simulating'reactor'conditions
2.6.3 Development'of'heat'exchange'technologies'and'technological'
investigation'on'power'generation'system
2.6.4 Investigation'on'DEMOYTBM'design,'offering'of'preliminary'
design'and'their'comparison

Reactor design 0.1.4

2.6.5 Expansion'of'fundamental'and'standard'data

Including*ITER=TBM*and*collabora1on*with*other*
par1es*Integrated*demonstra1on*of*structural*soundness,*thermal*hydraulics,*tri1um*
breeding*and*recovery*

Selec1on*of*advanced*blanket*and*heat*exchange*concepts*to*be*priori1zed*for*
DEMO=TBM*

2.6.6 Integrated'demonstration'under'reactor'conditions''with'small'
mockYup'

3 Divertor
3.1

Plasma.operation.scenario
3.1.1 Understanding'of'physical'mechanism'which'dominate'divertor' Reactor Plasma 6.7, 6.8,
6.9
operation

Accelerate*detachment*experiments*in*JT=60SA*
Pay*aaen1on*on*diﬀerence*in*plasma*facing*materials*

3.1.2 Verification'and'validation'of'detachment'plasma
3.1.3 Development'of'theoretical'modeling'for'detachment'plasma
JT=60SA

3.1.4 Understanding'of'impurity'effects'on'fusion'output
3.1.5 Demonstration'of'plasma'operation'scenario

Theory&Sim. 5.1.2
Reactor Plasma 6.13

3.1.6 Development'of'theoretical'simulation'for'burning'plasma

3.2

Theory&Sim. 5.1.1, 5.1.2,
5.1.3

Development.of.theoretical.simulation.for.burning.
plasma3.2.1 Decision'of'consistent'fusion'output'with'divertor'heat'flux

Experiment*with*tungsten*
divertor*in*JT60=SA*and*ITER*
Simula1on*based*on*
plasma*experiments*
in*exis1ng*device*

Simula1on*based*on*plasma*experiments*in*JT=60SA*and*ITER*

Consistent*fusion*output*
with*divertor*heat*loadReactor design 0.1.1

3.2.2 Understanding'of'heat'removal'property'of'divertor'
components'(steady'&'transient)3.2.3 Clarification'of'heat'removal'property'of'low'activation'material
3.2.4 Demonstration'of'heat'removal'property'of'W'&'Cu'divertor'
under'actual'condition

Plasma*experiment*in*ITER*
and*tungsten=ized*JT=60SA*

3.2.5 Development'of'innovative'cooling'system

3.3

Make*urgent*start*as*
an*alterna1ve*plan

Material.development
3.3.1 Understanding'of'material'property'of'plasma'facing'components

Comprehensive*evalua1on*of*resistance*to*neutron*
irradia1on*of*copper*alloy

3.3.3 Clarification'of'neutron'irradiation'effects'on'divertor'materials

Particle.exhaust
3.4.1 Understanding'of'hydrogen'behavior'on'plasma'facing'components

Reactor Plasma 6.9, 6.10

3.4.2 Understanding'of'hydrogen'behavior'under'actual'condition

Reactor Plasma 6.9, 6.10

3.4.3 Development'of'feasible'vacuum'pump'under'DEMO'reactor'
conditions

Reactor design 0.1.1

3.4.4 Establishment'of'consistent'particle'exhaust'scenario'with'heat'removalTheory&Sim.5.1.3

Understanding*of*physical*
mechanism*as*fundamental*study

Establishment*of*evalua1on*method*
for*resistance*to*neutron*irradia1on

Demonstra1on*of*stable*long=term*opera1on
Inves1ga1on*based*on*exis1ng*knowledge

Technical.specification
4.1.1 To'clarify'technological'specifications'of'heating'and'current'
drive'systems

Fig.2

Reactor design 0.1
Diag.&Control 11.3
Reactor Plasma 6.1

Neutron*irradia1on*test*facility*for*the*equipment*of*NBI*and*ECH*systems*

Chart of Establishment of Technological Bases for DEMO (2)11Experiment*with*tungsten*divertor*
in*JT60=SA*and*ITER
Absence*of*prospec1ve*candidate,*make*urgent*start.*
ITER*knowledge*provides*limited*sugges1on.*

Clariﬁca1on*of*required*par1cle*exhaust*proper1es*

4 Heating.and.Current.Drive.Systems
4.1

Accelera1on*of*R&D*considering*
advisability*of*tungsten*divertor*

Understanding*of*marginal*
performance*of*exis1ng*
Cu*alloy*and*new*material*
development

3.3.2 Improvement'of'resistance'to'neutron'irradiation'of'copper'
alloy

3.4

New*R&D*facility

Inves1ga1on*based*on*characteris1cs*of*device*developed*for*DEMO*reactor*

4.2

ECH
4.2.1 To'develop'ECH'system'for'ITER

ITER

4.2.2 To'develop'multiplesYstage'energy'recovery'technology'for'gyrotron
4.2.3 To'develop'mirrorYfree'waveguideYinjectorYtype'launcher'system
4.2.4 To'develop'fast'variable'frequency'technology
4.2.5 To'develop'gyrotron'with'higher'frequency
4.2.6 To'develop'maintenance'scenario

4.3

Maintenance 10.1

NBI
4.3.1 To'develop'HV'power'supply'and'bushing'for'ITER

ITER

R&D*for*DEMO*NBI*

4.3.2 To'develop'largeYbore'ceramic'insulation'ring

ITER

R&D*for*DEMO*NBI*

4.3.3 To'develop'RF'ion'source'for'ITER

ITER

R&D*for*DEMO*NBI*

4.3.4 To'establish'beam'focusing'technology'required'for'installing'
the'neutron'shield'structure'in'beam'line

Maintenance 10.1

4.3.5 To'develop'highYefficiency'neutralizer
4.3.6 To'develop'electrode'material'with'low'work'function
4.3.7 To'develop'maintenance'scenario

Maintenance 10.1

4.3.8 To'develop'integrated'performance'of'mockYup'NBI

Neutral*Beam*Test*Facility*for*ITER*(NBTF)*

Link to other task

5 Theory.and.Numerical.Simulation.Research
5.1

2010s
14

NBTF*for*DEMO*(Domes1c*or*Italy)*

2020s

15

16

17

18

19

Helios*(BA)*

20

21

22

23

24

25

2030s
26

29

30

31

32

33

34

35

ITERJT=60SA

5.1.1 Development'of'integrated'fusion'plasma'simulation'code

Reactor Plasma 6.3, 6.11

5.1.2 Development'of'integrated'burning'fusion'plasma'simulation'code

Reactor Plasma 6.3, 6.11

5.1.3 Development'of'integrated'DEMO'plasma'simulation'code

Reactor Plasma 6.3, 6.9

Development*of*simula1ons*for*turbulent*transport*and*macroscopic*non=linear*phenomenon*/*Integrated*modeling,*including*the*developed*simula1ons,*considering*MHD,*microinstability,*macroinstablity,*atomic*
and*molecular*process,*plasma*material*interac1on*etc.*/*Valida1ons*by*comparing*with*experiments**
Integrated*modeling*considering*a*par1cle*hea1ng,*
instability*triggered*by*high*energy*par1cle*etc.*in*addi1on*
to*5.1.1*/*Valida1ons*by*comparing*with*experiments**

Plant.Simulation
5.2.1 Improvement'of'interface'of'engineering'codes'
Development'of'engineering'code'such'as'molecular'dynamics'
analysis'in'materials

Reactor design 01
Fuel Systems 7.1
Blanket 2.4

5.2.3 Development'of'integrated'code'for'DEMO

Reactor design 02
Fuel Systems 7.1
Blanket 2.4

5.2.4 Development'of'integrated'fusion'reactor'code

Reactor design 02
Fuel Systems 7.1
Blanket 2.4

control*logic,*actuators*etc.*/*Valida1ons*by*comparing*
with*experiments**

Combina1on*with*thermal*analysis,* ******ITER/ITER=TBM/Neutron*source*
electromagne1c*force*analysis,*stress*
analysis,*neutronics*analysis*/*Development*of*engineering*codes**Reactor design 01

5.2.2 Improvement'of'base'code'for'DEMO

5.3

28

Computer*resource*a^er*BA*

Fusion.Plasma.Simulation

5.2

27

Expansion*of*man=machine*interface*
and*improvement*of*model*/*Valida1ons*
by*comparing*with*experiments**
Control*logic*and*actuators*
etc.*/*Valida1ons*by*comparing*
with*experiments**
Design*integra1on*as*a*
power*plant*etc.*/*Valida1ons*by*comparing*
with*experiments**

Operational.Control.Simulation

ITERJT=60SA

5.3.1 Development'of'operational'control'simulator'which'enables'to'
predict'plant'behavior

Diag.&Control 11.7, 11.8

5.3.2 Improvement'of'operational'control'simulator

Diag.&Control 11.9

5.3.3 Improvement'of'operational'control'actuator

Diag.&Control 11.9

Real*1me*process*etc.*
Control*logic*and*actuators*etc.*
Improvement*of*control*logic*
and*actuators*etc.*

6 Reactor.Plasma.Research
6.1

To.develop.physics.design.and.to.identify.reactor.
parameters

Reactor Design 0.1
Heating&CD 4.1

6.2

To.develop.DEMO.physics.DB

Diag.&Control 11.1

6.3

To.develop.physics.model.and.to.promote.further.
development.of.performance.prediction.codes

Theory&Sim. 5.1
Diag.&Control 11.1

6.4

To.demonstrate.highSbeta.steadySstate.operation

6.5

To.demonstrate.highSdensity.operation.with.high.
confinement

6.6

To*accumulate*data*of*ITER*and*other*tokamaks*strategically*in*REC*

To*accelerate*the*increase*of*hea1ng*
power**in*JT=60SA*

ITER,*JT=60SA

Fuel System 7.1

ITER,*JT=60SA

To.demonstrate.particle.control.technique.(D,.T,.He,.
Impurities)

Divertor 3.1

ITER,*JT=60SA

6.7

To.demonstrate.operation.without.large.ELMs

Divertor 3.2

ITER,*JT=60SA

6.8

To.demonstrate.control.technique.of.disruption

6.9

To.obtain.PWI.basic.data.on.Tungsten

Divertor 3.3

6.10

To.clarify.issues.on.Tungsten.divertor.property.for.
long.time

Divertor 3.3

6.11

To.develop.control.simulator

6.12

To.demonstrate.integrated.plasma.performance.to.
be.extrapolated.to.DEMO

6.13

To.demonstrate.burning.control.in.selfSheating.
regime

6.14

To.realize.nonSinductive.steadySstate.operation.with.
Q>5

ITER,*JT=60SA
To*organize*the*framework*to*op1mize*intrinsic*advantage*of*each*domes1c*plasma*experimental*device*
To*carry*out*the*LHD*deuterium*experiments*with*upgraded*hea1ng*
power*and*the*extended*pulse*length*early.*
To*upgrade*to*tungsten*divertor*in*JT=60SA*at*an*appropriate*1me.*

LHD,*JT=60SA

Theory&Sim. 5.3
Diag.&Control 11.2, 11.3

JT=60SA

Theory&Sim. 5.3
Diag.&Control 11.3

To*promote*development*of*control*simulator*applicable*in*the*early*phase*of*
JT=60SA*opera1on,*and*to*examine*demonstra1on*test*of*the*simulator*in*ITER*

ITER,*
It*is*important*to*show*the*prospect*for*plasma*control*technique*based*upon*
JT=60SA the*technologies*available*and*feasible*in*DEMO.*

Blanket 2.4.6

ITER

Need*to*clarify*the*content*of*the*item*“demonstra1on*of*burning*control*in*
self=igni1on*regime”*in*transi1on*condi1on.*ITER

To*be*conﬁrmed*it*at*an*appropriate*1me*in*accordance*with*the*progress*of*
ITER*project*

7 Fuel.Systems
7.1

Fuel.cycle.system
7.1.1 Determination'of'specifications'for'fuel'cycle'system

Reactor design 0.1
Reactor Plasma 6.1

7.1.2 Verification'of'specifications'for'fuel'cycle'system

Reactor design 0.1
Reactor Plasma 6.6

7.1.3 Establishment'of'technologies'for'fuel'cycle'system

Blanket 2.5
Divertor 3.4
Safety 9.3

7.1.4 Demonstration'of'technologies'for'fuel'cycle'system'in'DEMO

Blanket 2.5
Divertor 3.4
Simulation 5.2
Safety 9.3

7.1.5 Establishment'of'technologies'for'fuel'cycle'system'in'DEMO

ITER/JT=60SATPL/Rokkasho/Univ.*of*Toyama*

Blanket 2.5
Divertor 3.4
Safety 9.3

7.1.7 Demonstration'of'technologies'for'tritium'safety'handling'and'accumulation'of'its'experiences

Blanket 2.5
Divertor 3.4
Safety 9.3

7.1.8 Establishment'of'technologies'for'safety'tritium'handling'in'
DEMO

Blanket 2.5
Divertor 3.4
Safety 9.3

Veriﬁca1on*of*fuelling*scenario*
using*ITER*and*JT=60SA*

Development*of**component*technologies*
such*as*impurity*removal*and*isotope*
separa1on*

ITER

Blanket 2.5
Divertor 3.4
Safety 9.3

7.1.6 Establishment'of'technologies'for'safety'tritium'handling

Fig.2

Determina1on*of*fuelling*scenario*/*es1ma1on*of*fuel*inventory*

Veriﬁca1on*of*integrated*system*
technology*in*ITER*

Large*Scale*Facility*

TPL/Rokkasho/Univ.*o<f*Toyama*

Demonstra1on*of**technologies*for*detri1a1on*
system*and*material*accountancy*

ITER

Accumula1on*of*experiences*of*
tri1um*safety*handling*in*ITER*

Large*Scale*Facility*

Chart of Establishment of Technological Bases for DEMO (3)12

Veriﬁca1on*of*technologies*with*large*scale*handing*

Accumula1on*of*the*safety*tri1um*
handling**experiences*in*large*
scale*facility*7.1.9 Accumulation'of'data'base'for'development'of'equipment'
treating'tritium

Blanket 2.5
Divertor 3.4
Safety 9.3

7.1.10 Accumulation'of'experiences'of'equipment'operation'treating'tritium

Blanket 2.5
Divertor 3.4
Safety 9.3

7.1.11 Establishment'of'manufacturing'technologies'for'equipment'
treating'tritium'in'DEMO

Blanket 2.5
Divertor 3.4
Safety 9.3

Accumula1on*of**base*data*such*as*tri1um*
materials*interac1ons*

TPL/Rokkasho/Univ.*of*Toyama*

Large*Scale*Facility*

7.1.12 Construction'of'large'scale'facility

7.2

Veriﬁca1on*of**equipment*trea1ng*
tri1um*contained*gas*and*water.*

ITER

Veriﬁca1on*of*equipment*trea1ng*
tri1um*contained*gas*and*water*in*large*scale*facility.*

Large*Scale*Facility*

Securing.Lithium
7.2.1 Examination'of'process'to'secure'lithium'6

Rokkasho*

7.2.2 Establishment'of'concept'for'lithium'6'plant

Lithium*Plant*

7.2.3 Accumulation'of'plant'operation'experiences

7.3

Lithium*Plant*

Securing.Initial.Loading.of.Tritium
7.3.1 Examination'of'process'for'securing'initial'loading'of'tritium
7.3.2 Preparation'of'securing'initial'loading'of'tritium

ITER

7.3.3 Investigation'of'startYup'scenario'without'initial'loading'of'tritium

Reactor design 0.1

Link to other task

2010s
14

2020s

15

16

17

18

19

20

21

22

23

24

2030s

25

26

27

28

29

30

31

32

33

34

35

8 Material.Development.and.Establishment.of.Codes.
and.Standards
8.1

ReducedSactivation.ferritic.(RAF).steel
8.1.1 To'establish'mass'production'technologies'of'RAF'steel
8.1.2 To'establish'blanket'structure'fabrication'technologies

Blanket 2.4

8.1.3 To'clarify'requests'to'the'structural'materials'for'DEMO'fusion'
reactor

Reactor design 0.1.8

8.1.4 To'present'technical'specifications'of'blanket'structural'materials'for'DEMO'fusion'reactor

Reactor design 0.2.6
Blanket 2.4

8.1.5 To'initiate'preparatory'activities'for'materials'standardization'in'academic'societies'and'so'on

Reactor design 0.2.8

8.1.6 To'obtain'data'of'joining/coating,'effect'of'electromagnetic'
force,'and'compatibility'with'coolants

Blanket 2.4

8.1.7 To'obtain'data'of'joining/coating,'effect'of'electromagnetic'
force,'compatibility'with'coolants,'and'the'irradiation'effect'on'
these'properties

Blanket 2.4

ITER=TBM
To*clarify*requests*to*the*structural*materials*
for*DEMO*fusion*reactor.*
To*present*technical*speciﬁca1ons*of*blanket*
structural*materials*for*DEMO*fusion*reactor.*Standardiza1on*of*structural*material*for*DEMO*blanket.*To*clarify*Irradia1on*matrix**
of*fusion*neutron*source.*

JAEA*(BA=Rokkasho),*NIFS(Fusion*
Tech.*Project),*Universi1es,*JOYO,*JMTR,*HFIR*etc.*

8.1.8 To'establish'the'validity'of'material'data'obtained'by'SSTT
To*standardize*small*
specimen*tes1ng*
technologies*(SSTTs).*8.1.9 To'standardize'small'specimen'testing'technologies'(SSTTs).
8.1.10 To'obtain'80'dpa'irradiation'data'by'using'fission'reactor

HFIR,*JAEA*(BA*Rokkasho)*

8.1.11 To'validate'the'80'dpa'irradiation'data'by'using'fission'reactor

Reactor design 0.2.6, 0.2.8
Availability 10.1.4

8.1.12 To'enhance'understanding'of'the'impact'of'transmutation'
helium'using'fusion'neutron'source

Reactor design 0.2.6, 0.2.8
Availability 10.1.4

8.1.13 To'clarify'fusion'neutron'irradiation'effect

Reactor design 0.3.6
Availability 10.1.4

8.1.14 To'establish'degradation'models'based'on'irradiationYfield'
correlation'theory

Reactor design 0.2.8
Availability 10.1.4

8.2

Advanced.materials
8.2.1 To'clarify'the'uses'of'advanced'materials'and'to'enhance'the'material'database

To*understand*irradia1on=induced*
degrada1ons.*
Fusion*neutron*sources*(incld.*
IFMIF=EVEDA)*

20dpa*irradia1on*

To*understand*He*eﬀect*up*to*20dpa.*
Valida1on*of*reliability*under*
high=dose*irradia1on.*IFMIFIntense*fusion*neutron*sources*
JAEA(BA=Rokkasho),*Helios*(Rokuchan),*
NIFS(Fusion*Tech.*Project),*University’s*Fusion*Material’s*Facili1es*(HVEM@Hokkaido*U.,*Oarai=
RI*facility@Tohoku*U.,*DuET&MUSTE@KyotoReactor design
Blanket 2.6

Statement*of*availability*of*
DEMO*advanced*materials.*

9 Safety.of.DEMO.reactor.and.Safety.research
9.1

Safety.regulation.and.order

9.2

Reactor design 0.2.10

Preliminary*prepara1on*

arrangement*of*laws*and*regula1ons*

Arrangement.of.safety.related.engineering.issues
9.2.1 Establishment'of'failure'scenario'of'inYvessel'component
9.2.2 Assessing'damage'of'inYvessel'components

Reactor plasma 6.8

9.2.3 Arrangement'of'safety'characteristics'of'DEMO'plant

Blanket 2.2.1, 2.2.2
Material 8

9.3

Safety.analysis.and.assessment
9.3.1 Development'of'computer'simulation'codes'to'estimate'damage'of'inYvessel'component'by'plasma

Prac1ce*in**ITER,*JT=60SA*and*LHD*experiments*
Es1ma1on*by*exis1ng*codes*
Proposi1on*of*guideline*
to*secure*safety**
Predic1on*of*experiments,*
Valida1on*of*code*

Theory&Sim. 5.2.2

Feedback*from*ITER*
experiments*

9.3.2 Development'of'computer'simulation'codes'for'safety'analysis
9.3.3 V&V'experiments

Veriﬁca1on*of*TBM*
experiment*

9.3.4 Safety'assessment'of'DEMO'plant
9.3.5 Guidelines'for'both'plasma'control'and'securing'soundness'of'inY
vessel'components
9.3.6 Guideline'to'ensure'DEMO'plant'safety'and'consistent'design'conditions

9.4

Es1ma1on*of*chemical*
reac1on*and*dust*behavior*
Es1ma1on*code*validated*by*
experiments*

MatchingReactor design 0.2

Assessment.of.environmental..effect.of.tritium
9.4.1 Assessment'and'control'of'tritium'release'to'the'environment

ITER*D,*T*phase

Improvement*and*sophis1ca1on*of*data*

9.4.2 Develop'the'guideline'of'the'safety'design'of'DEMO

10 Availability.and.maintainability
10.1

DEMO.reactor.design

10.1.1 Determination'of'maintenance'method,'reactor'structure'and'parameters

Reactor design 0.1.1, 0.1.2,
0.1.3

10.1.2 Investigation'and'selection'of'components'to'be'maintained,'
method'and'working'process

Reactor design 0.1.1, 0.1.2,
0.1.3

10.1.3 Optimization'of'maintenance'process'and'reactor'shutdown'
periodReactor design 0.1.3, 0.1.6

10.1.4 Investigation'of'back'end'process'(amount'of'waste'and'
disposal'process)'

Reactor design 0.1.3
Material 8.1

10.1.5 Standard'definition'for'disposal'and'reuse'of'radioactive'waste'(preparation'for'laws'and'regulations)''

10.2

Development.of.maintenance.technologies

10.2.1 MediumYscale'R&D'on'maintenance'technologies'to'support'
conceptual'design'of'DEMO'
10.2.2 Development'of'functional'materials'and'devices'aiming'at''
integrated'dose'of'200'MGy

Speciﬁca1on*decision*

Maintenance*technologies*for*ﬁssion*reactors,*remote*and*robot*
technologies*in*industry*

10.2.3 FullYscale'R&D'in'maintenance'technologies'for'DEMO

10.3

Accumulation.of.maintenance.technologies

Handling*of*radioac1ve*large*components,*hot*cell,*decontamina1on,*inspec1on*and*repair*of*devices,*detailed*inves1ga1on*on*waste*disposal,*detailed*design*of*
equipment*and*building*in*ITER*

10.3.1 Equipment'handling'and'inspection'in'nuclear'facility
10.3.2 Accumulation'of'technologies'for'remote'handling,'inspection'
and'maintenanceFig.2

Accumula1on*in*ITER*and*JT=60SA*

Chart of Establishment of Technological Bases for DEMO (4)13

Support*10.3.3 Database'of'failure'rate

10.4

Accumula1on*in*ITER*and*JT=60SA*

New.facility

10.4.1 Construction'of'new'facility'for'development'of'largeYscale'maintenance'technologies'and'R&D'activity

Reactor design 0.1.3

Link to other task

2010s
14

15

2020s
16

17

18

19

20

21

22

23

24

25

2030s
26

27

28

29

30

31

32

33

34

35

11 Diagnostics.and.Control.Systems
11.1

Database.and.Modeling11.1.1 To'accumulate'data'of'plasma'response'property'for'use'of'model'validation

11.2

Theory&Sim. 5.1
Reactor Plasma 6.2, 6.3

ITER,*JT=60SA

Development.of.diagnostics

11.2.1 To'focus'diagnostics'to'be'applicable'to'DEMO

Reactor design 0.1
Reactor Plasma 6.11

11.2.2 To'develop'diagnostics'and'their'analysis'codes

Reactor Plasma 6.11

ITER,*JT=60SA,*LHD

11.2.3 To'develop'radiationYproofed'components'in'parallel'with'evaluation'of'lifetime'of'diagnostics
11.2.4 To'show'prospects'for'accuracy'of'equilibrium'control'under'
DEMO'relevant'electroYmagnetic'condition

11.3

Irradia1on*test*Facility*

Reactor design 0.2

JT=60SADevelopment.of.control

11.3.1 To'define'operation'standard'point'and'surrounding'allowable'
operating'regime

Reactor design 0.1
Reactor Plasma 6.11

11.3.2 To'develop'operational'control'simulator'(offline)

Theory&Sim. 5.3
Reactor Plasma 6.11
Heating&CD 4.1

JT=60SA

11.3.3 To'develop'realYtime'operational'control'simulator

Theory&Sim. 5.3
Reactor Plasma 6.11

JT=60SA

11.3.4 To'validate'simulator'using'experimental'data

Reactor Plasma 6.11

ITER,*JT=60SA

11.3.5 To'establish'practical'and'reliable'control'logic

Reactor Plasma 6.11

ITER,*JT=60SA

Fig.2

Chart of Establishment of Technological Bases for DEMO (5)

14

3.

Highlighted Remarks in Establishment of Technology Bases for DEMOAt the Assessment of Transition Conditions towards the next Fourth Phase Program with a core

project of DEMO, validity of plan, overall maturity of technological bases, clarity of implementing
bodies, and appropriateness of a system for cooperation and coordination among participating sectors
are needed to be sufficient as a whole from the integrated view. Chart of Establishment ofTechnological Bases for DEMO visualizes all of the related programs and provides a complete pictureof related processes. It is expected that the strategic PDCA cycle will be developed by making full useof this chart.
Principal matters of weight which have been recognized in formulating Chart of Establishment ofTechnological Bases for DEMO are remarked upon below. These matters are summarized into thefollowing 4 points.
(1) The ITER project is the definite critical path and its steady accomplishment is indispensable.
(2) Besides the ITER project, they are “reinforcement of DEMO design activity” and “strategic
acceleration of research and development of divertor” that are the present critical paths and should
be grappled with most urgently with more investment of resources than at present.
(3) From the prospect around the Assessment of Transition Conditions, “Test Blanket Module (TBM)”
and “fusion neutron source” are cited for critical paths to determine the complete timeline.
(4) A framework for implementation throughout industrial, governmental and academic sectors inJapan is necessary for establishment of technological bases for DEMO and actions to make thisframework effective, in particular, making the best use of human resources, should be taken.
Reinforcement of DEMO design activity
DEMO design activity exchanges close links with technological issues in 11 elements from anearly stage of the baseline design of a DEMO concept. For this reason, the development organization
for the DEMO design needs to be expanded devoting a notable scale of resources and to be urgently
enhanced to timely define the development targets, required performance and technical specificationsof each technological issue, and to boost necessary research and development without delay. In
particular, intensive design work is necessary for divertor, breeding blanket, remote maintenance, andsafety issues considering the integrity of the overall system design in that the details of research anddevelopment in these technologies are dependent upon the DEMO design.
Strategic acceleration of research and development of divertor
There is quite a large gap between the envisioned operational condition of DEMO and the present
scientific understanding and technological maturity. Therefore, in addition to significant reinforcementof the DEMO design activity in this field, the strategic acceleration of research and development
targeting the milestones of the Intermediate C&R and the Assessment of Transition Conditions isurgently indispensable.

15 Prototype tests and model validation by using the LHD and JT-60SA
 Promotion of basic and focused studies by using laboratory devices
 Improvement of numerical model and validation by experiments
 Proof-of-principle and performance extension tests of innovative concepts
 Effective utilization of empirical knowledge, which can be acquired by manufacturing andprocurement of the ITER divertor.
With respect to the above, it is necessary to formulate a strategic plan focused on resolution oftechnological issues in an integrated manner including international collaborations, and to implement
the plan. For example, the European analysis has pointed out that the JT-60SA gains higher-priority bychanging wall materials to DEMO relevant tungsten than carbon in the report “R&D Needs andRequired Facilities for the Development of Fusion as an Energy Source” [8]. As mentioned in the“Joint-Core Team Report (Basic Concept of DEMO and Structure of Technological Issues)”, it is to berequired to change the divertor materials to tungsten at an appropriate time, in order to establish a
detachment control technology, which is consistent with the DEMO design. Furthermore, divertor
research and development facility beyond the presently available facility will be necessary in Japan toaddress the divertor issues including innovative concepts.
Test Blanket Module
With regard to development of ITER-TBM, a TBM Arrangement was signed in November 2014,
and a Final Design Review is planned in 2018 as an important milestone. While the development
activities for ITER-TBM is enhanced mainly by JAEA recently, development of integrated functional
test facilities (heat load, irradiation, and tritium behaviour) and demonstration test plan of performanceby using the facilities as well as cooperation with other parties related to advanced concepts still
remain insufficient. The related activities should be reinforced with the cooperation among universities,
research institutes and industries to resolve the issues and to ensure the completion of transition
conditions before the Assessment of Transition Conditions. With regard to irradiation test facilities,
development of the post-irradiation experiment (PIE) of ITER-TBM, remote handling technology anddisassembling and treating technology of large-scale activated components should be noted in addition
to the irradiation tests and PIE with a module-scale related to the tritium experiments using a fusion
neutron source. Also, with regard to arrangement of development of an advanced blanket concept for
DEMO-TBM, not only the third ITER-TBM developed by Japan but also cooperation with otherparties which plan a different concept for ITER-TBMs should be considered.
Fusion neutron source
Before the Assessment of Transition Conditions, it is necessary to experimentally validate theprediction model based upon the knowledge related to the material which will be available by thattime in order to confirm the range of application of the prediction model. It is required for thisvalidation to determine a detailed irradiation plan of fusion neutron source to be built in response to
the outcome of the IFMIF-EVEDA in time so as to be operated in a manner consistent with the16maturity of related technologies which should be reached before the Assessment of Transition
Conditions and with the data acquisition plan required to the subsequent engineering design activities
of DEMO. In other words, it is necessary to determine early on the design of the test cell in order toallow data acquisition related to the material reliability and the functional demonstration of thesubcomponent essential to the manufacturing design of DEMO. This determination should be done
from the integrated view based upon the results from IFMIF-KEP (Key Element Technology Phase)and IFMIF-EVEDA together with related missions such as ITER-TBM and computer simulation, as
well as the role of a fusion neutron source. Therefore, it is important to make full use of facilities
prepared by the BA activities and upgrade their capability. Also, the development of the IFMIF or anequivalent intensive fusion neutron source should be advanced with an expanded view of cooperation
with other parties in order to explore the development of long-life and advanced blankets to make sureof economic feasibility in DEMO.
On actions to implement the framework for execution throughout Japan
A framework for implementation throughout Japan is indispensable to make the most of theeffectiveness of human resources and to enable further development for the establishment oftechnological bases for DEMO. This requires a system for research institutes, universities andindustries to share the recognition of perspectives on issues and strategy in common, and to promoteresearch and development together towards resolution of issues, namely, “establishment of co-creation
platform of industry, academic and government”. In particular, the following two points of view arehighlighted.
(1) The Rokkasho Fusion Institute, JAEA is the base of BA activities with the IFMIF-EVEDA
prototype accelerator, radio-isotope treatment facility including tritium, beryllium, etc., supercomputer and experimental facility of remote handling. This site should be developed as thecentral core base for development of DEMO. In addition to expansion of facilities and equipment
for research and development, enhancement and development of logistics to promote convening
human resources throughout industry, education and research, and government in Japan isnecessary under the present circumstances that public transportation and accommodations are notsufficient. The Institute should pay special considerations to accept researchers and engineers. For
example, logistical assistance of transportation and accommodation for visitors and developmentof provisions of benefits with respect to commuting injuries are essential for visitors to accomplish
duties safely and with security. From the perspective of wide communication with other energy
research fields, the Institute, as an institute constituting the Rokkasho next generation energy park2,
is expected to define common tasks in cooperation with other fields and stimulate collaboration inorder to establish complementary relation of fusion energy with renewable energy.
2

Next generation energy parks are programs, which are certified by the Ministry of Economy, Trade andIndustry, to promote understanding about future environmentally friendly energy through increasing
opportunities for citizens to see or touch next generation energy such as renewable energy.

17

(2) Not only the Rokkasho Fusion Institute, JAEA but also other organizations taking part indevelopment of DEMO should actively introduce a cross-appointment system to promoteparticipation of researchers and engineers belonging to other organizations and to enhancemobility and diversity of human resources. Retainment of concurrent position enables continuous
long-term engagement and reinforcement of bases for research and development in bothorganizations, which leads to security and development of world-class research by the Japanesefusion community. Furthermore, there is the merit for dispatching organizations, such asuniversities, as the researcher’s salary will be paid by other organizations and the university may
then use the salary saved for educational purposes. This program thus enables training of young
researchers who can contribute to expanding further the fusion community and to achieving fusionenergy in the future.

4. Summary
The joint-core team has progressed with examinations of planning for the development of DEMO
since the team’s formation in July, 2013 along with the term of reference defined by the Working
Group on Fusion Research, which are the Interim Report on summary of issues (the 38th meeting of
the Working Group on Fusion Research, 24 February 2014) and the report on Basic Concept of DEMO
and Structure of Technological Issues (the 41st meeting of the Working Group on Fusion Research, 24
June 2014). And the present report introduces a chart which visualizes development of all of therelated programs in a timeline and provides an overview picture of all related processes. It is expectedthat the fusion-related community of industry, education and research, and government will closely
examine this chart, and share recognition of perspectives on issues and future direction in common,
which will lead to joint activity and accomplishment throughout Japan. In particular, definition of theroadmap of the development of DEMO, planning of research and development programs after the BA
activities which will end in 2017, and reinforcement of joint usage and collaborating research systems
and role-sharing with NIFS and universities are anticipated as a consequence.
The planning of research and development programs after the completion of the BA activities
should not be limited only to the present framework of Japan-EU cooperation, but also should beconsidered with determining what program is appropriate in sequential cooperation with EU, what
program should be undertaken only by Japan, and what programs are appropriate in other internationalframeworks through revisiting the original concept of “broader approach”.
In order to define the roadmap of development of DEMO in future, there remain two importanttasks which the joint-team has not completed. These are socio-economic examination of fusion energy
and review of alternative approaches of helical magnetic fusion system and laser fusion system. With
regard to the former task, those who are engaged in research and development of fusion energy should

18

recognize correctly the contemporary trend that implementing bodies are requested to be accountable
to society regarding the outcome from large-scale projects and outreach activities. With regard to thelatter task, it should be noted that the important decisions are made based upon comprehensive
assessment of overall progress of fusion research and development, and that the review of alternative
approaches is primarily important to form significant solidarity to grapple with development of
DEMO by the Japanese fusion community. The joint-core team hopes that these two tasks will be
addressed in the Working Group on Fusion Research in the next term.
Along with the methodology of backcasting 3 , the joint-core team has formulated Chart ofEstablishment of Technological Bases for DEMO which visualizes an overview picture with paying
attention to definition of plans based upon evidence and precise understanding of the current status
and realistic prospect of research and development, and to consistency between global strategy andindividual implementation in the workplace. The joint-core team sincerely hopes that development of
concrete actions and programs as well as policy are earnestly promoted so as to lead to implementationof the plan documented in Chart of Establishment of Technological Bases for DEMO and to enableeffective PDCA cycle.

3

Backcasting is the methodology to identify the goal backward from the desirable future and then to
define the action which should be taken now.

19

References[1]

http://www.aec.go.jp/jicst/NC/senmon/kakuyugo2/siryo/kettei/houkoku051026_e/index.htm[2]

http://www.mext.go.jp/b_menu/shingi/gijyutu/gijyutu2/056/shiryo/attach/1338911.htm [inJapanese].

[3]

http://www.mext.go.jp/b_menu/shingi/gijyutu/gijyutu2/056/shiryo/1345741.htm [in Japanese].

[4]

http://www.mext.go.jp/b_menu/shingi/gijyutu/gijyutu2/056/shiryo/1349978.htm [in Japanese].

[5]

http://www.mext.go.jp/b_menu/shingi/gijyutu/gijyutu2/056/shiryo/1350763.htm [in Japanese].
“Joint-Core Team Report (Basic Concept of DEMO and Structure of Technological Issues)” inJapanese is also available at
http://www.naka.jaea.go.jp/kankoubutu/PDF/goudoukoa_201409.pdf
http://www.jspf.or.jp/2015/genkeiro/140718.pdf
The report in English is available at
http://www.naka.jaea.go.jp/english/report/201501report.pdf
http://www.jspf.or.jp/2015/genkeiro/140718en.pdf[6]

S. Sakamoto and H. Yamada, “Towards Development of Demonstration Fusion Rector from
Now on” [in Japanese], Journal of Plasma and Fusion Research, Vol. 90, 821 (2014).

[7]

http://www.naka.jaea.go.jp/fusion-energy-forum/files/member/iter_ba/3_roadmap.pdf [inJapanese].

[8]

R. Cashmore et al., “R&D Needs and Required Facilities for the Development of Fusion as an
Energy Source” (2008) Report of the Facilities Review Panel.

20

Member of Joint-Core Team
Members
Ryuta KASADA(Kyoto University)

Akira OZAKI(Japan Atomic Industrial Forum)

Ryuichi SAKAMOTO(National Institute for Fusion Science)

Yoshiteru SAKAMOTO (Japan Atomic Energy Agency)
Hidenobu TAKENAGA (Japan Atomic Energy Agency)
Teruya TANAKA(National Institute for Fusion Science)

Hisashi TANIGAWA(Japan Atomic Energy Agency)

Hiroshi YAMADA(National Institute for Fusion Science): Leader

Experts
Kunihiko OKANO(Keio University)

Kenji TOBITA(Japan Atomic Energy Agency)

Secretariat
Osamu KANEKO(National Institute for Fusion Science)

Kenkichi USHIGUSA(Japan Atomic Energy Agency)

Observers
Akio KOMORI(National Institute for Fusion Science)

Masahiro MORI

(Japan Atomic Energy Agency)

Katsusuke SHIMIZU(Japan Atomic Industrial Forum)

Yasumi MARUSUE(Japan Atomic Industrial Forum)21