The meeting of National Academies of SCIENCES ・ENGINEERING・MEDICINEAt General Atomics in San Diego, February 26, 2018

Research and Development Policy
on Fusion Energy in Japan
Yuichi OGAWAThe University of Tokyo

On behalf of Science and Technology Committee on Fusion Energy
Subdivision on R&D Planning and Evaluation, Council for Science and Technology
In the Ministry of Education, Culture, Sports, Science and Technology (MEXT)Content
1. Brief review of Japanese Fusion Energy Policy andJapanese Fusion Activities
2. New Policy decided on December 18, 2017
- Report on Japan’s Policy to promote R&D for a fusion
DEMO reactor –- Action plan for DEMO R&D 3. Comments on inquiries from NAS

Phased Program on Fusion Research and Development in JapanA phased program : development program proceeds to the next phase on the basisof successful results on the critical path of the present phase concerned.

@ 1st Phase Basic Program formulated in 1968
 Construction of JFT-2 and -2a devices@ 2nd Phase Basic Program formulated in 1975
 Construction of JT-60 device@ 3rd Phase Basic Program formulated in 1992
 A DT burning experimental reactor
ITER is assigned to this experimental reactor
A strategy for DEMO Research and Development
has been updated in 2005 and 2017.

@ 4th Phase Basic Program in 2030s
 DEMOFER has been designed(Domestic Machine)

Revised Scenario for Fusion Reactor Development(Atomic Energy Commission in 2005)
The Atomic Energy Commission in 1992 has considered three devices, i.e., Experimental reactor, DEMO and Proto ,just similar to Fast Breeding Reactor (FBR) development scenario in Japan.

Engineering Demonstration &Economical Feasibility

DEMO

Scientific & Engineering
Feasibility

ITER

Large Tokamaks

high beta,
steady-state
JT-60SA

TFTR/JET/JT-60, JT-60SA,,,

Commercialization

FusionReactorIt is appropriate in the DEMO phaseto aim at realizing steady-statefusion core plasma with high energy
multiplication factor and at thesame time demonstrating power
generation in a plant scale, taking
certain economical performance
into account.
skip of the Proto type reactor
phase.
 One integrated device just before
commercialization

Promotion of Fusion Research and Development
Strategy for Fusion Development (Atomic Energy Commission, 2005)
Third Phase Basic Program

academicdevelopmental

practical

Second Phase

Fourth Phase Program

Decision of DEMO
Construction

JT-60

ITER

Utilization

DEMO

ITER Physics R&D, Improved Core Plasma, Theory

JT-60 : National Centralized Tokamak
Fusion Engineering (Materials, Blanket, Reactor Technologies)

Broader Approach Activities

ITER Technology R&D IFMIF (Irradiation Facility)
Safety Research, Conceptual Design & Engineering Design of DEMO Reactor

Developmental Research

Fusion Science
Basic Research for
Fusion Plasma Science

LHD (Helical)
FIREX (Laser)

Basic Research for Reactor Technologies (Advanced Materials, Blanket, Advanced Reactor Design, etc)

Steady promotion of research in the current phase as “Scientificand Technological Feasibility” of the fusion research and development
Scientific & Technological
Feasibility

Scientific Feasibility

Technological Demonstration& Economic Feasibility-To demonstrate electric power generation-To Improve economic efficiency-To realize burning plasma and long-duration burning-To establish physical and technological basis for DEMO

-To achieve break-even plasma condition

JT-60 (QST)IFMIF
 7 Members (EU, JA, CN, IN, KO,
RF, US) collaboration
 Demonstrate burning plasma(Q>10, 300-500sec)
 ITER Organization assembles
components as in-kind
contribution by 7 Members (JA:Toroidal Field Coils etc.)

ITER(Experimental Reactor)

ITER ProjectJT-60SA (QST)

BA Activities

Academic Research
FIREX(Osaka Univ.)
QST: National Institutes for Quantum and Radiological Science and Technology
NIFS: National Institute for Fusion Science

DEMO Reactor

LHD(NIFS) EU – Japan Bilateral Collaboration in
Japan supporting ITER and DEMO R&D
comprising following activities:• IFERC (DEMO design and R&D)
• IFMIF/EVEDA (Engineering
Validation for fusion material
irradiation facility)• Satellite Tokamak Programme (JT60SA)
 Discussing activities from 2020 onwards

6

Projects Summary

ITER – Japanese In-kind Contribution
 Japan procures components which are indispensable for DEMO development
and lead to strengthening Japanese international competitiveness.
TF Coil

CS Coilmanufacturing of all 49
conductors were completed
42 conductors were alreadyshipped to US. (39 arrived at
US as of the end of Sep. 2017)

Remote Handling

NBI system

Manufacturing Review
will be held in 2018.
ブラ ン ケッ ト
モ ジュ ール

Vacuum
真空容器
Vesselrail

レ ール

マニ ピ ュ レ ータ
Manipulator

9 out of 19 TF Coils and all 19 Coil
Structures are procured by JA.
Completion of WP insulation of the 1st
WP was achieved in January 2017.
 First TF coil will be completed in 2018.

ビ ーク ル

Vehicle All 5 DC generators,
1MV insulatingtransformer and 85 %of the transmission
lines are installed on
the NBTF site in Italy.
The final components
are manufactured in
March/2017.

ECH system
Divertor (Outer Target)
Passed the firstevaluation test of real
scale prototype fulltungsten divertor.

8 out of 24 gyrotron
are procured by JA.
First gyrotron was
fabricated in 2016.
8

Broader Approach Activities
Outline of the Project

Role of the BA Activities

A joint JA-EU fusion research and development project toestablish a technological basis for DEMO as well as to play
supporting and complementary roles for the ITER Project .
Parties: JA, EU
BA Agreement : Effectuated on 1st June, 2007
Site: Rokkasho (Aomori) and Naka (Ibaraki)
Total cost: 92 billion yen, evenly shared by JA and EU(as of value on 5, May, 2005)

DEMO
Commercialization

Broader Approach Activities
Development of Key Fusion
Technologies
for DEMO, etc.

Schedule: Until the end of March 2020

【Rokkasho in Aomori 】

ITER

Activities in sites（１） Engineering Validation and Engineering Design Activities for
the International Fusion Materials Irradiation Facility (IFMIF/EVEDA)• Develop prototype accelerator for International Fusion
Materials Irradiation Facility (IFMIF)

Roadmap for
Realization of
Fusion Energy【Naka in Ibaraki】

JT-60SA（３） Satellite Tokamak Programme• Upgrade of JT-60 Tokamak to JT-60SA withsuperconducting magnets and its operation.
• Under high pressure plasma environment,
supporting/complementary experiment for the
ITER and DEMO.
• Operation will start in September 2020.

Discussion for BA Phase-II (beyond Apr. 2020)（２） International Fusion Energy Research Centre(IFERC)a) DEMO Design and R&D coordination Centreb) Computational Simulation Centre, etc.

• BA phase-II Task Group established at BASC-20 isdiscussing scope, schedule, cost and necessary
administrative procedure of JA-EU cooperation from
April 2020 onward.
• The Task Group submitted an interim report to the
BASC-21 in Dec 2017. The Task Group, withgovernment representatives to be newly appointed,
will further discuss those issues, and report to the
BASC-22 in April 2018.
9

Progress in BA Activities
IFMIF/EVEDA (Rokkasho, Aomori)JT-60SA (Naka, Ibaraki)

Injector (~0.1 keV) The Injector achieved 135 mA beam with
sufficient beam quality in 2016.

In Satellite Tokamak Project (JT-60SA), Japan procures key
components for DEMO ; Vacuum Vessel, CS, PF coil, and Assembly& Installation (those are not procured in ITER Project).

RFQ (~5 MeV), RF Power Acceleration by RFQ will startin the beginning of 2018.

SRF Linac (~9 MeV)
 Beam acceleration at 9MeV is
expected in Mar. 2020.
Installation
 RFQ was installed in July 2017.
 Assembly of SRF Linac will start in2018 and installed in 2019.

CS Coil Fabrication of
4 CS modules
will becompleted inMar. 2018.

HEBT
Beam Dump
Building
Auxiary System

IFERC project (Rokkasho, Aomori) Interim report of DEMO design activity was finalized in 2017.
 The Helios super computer was shutdown in Dec. 2016 after
5 year’s successful operation. More than 600 research
papers have been published by this supercomputer so far.
 The infrastructure of the Remote Experiment Center wascompleted in Mar. 2017.

Demo

Helios super computer

REC operation room

PF Coil Fabrication of 6
PF coils werecompleted in2016.
 At present, 3 PF
coils were preinstalled.

Cryostat Top Lid

Vacuum Vessel Manufacturingof 10 VVsectors werecompleted.

Cryostat
Thermal Shield
TF Coil
In-Vessel Components

Cryostat Base
Assembly and Installation
 Assembly and installation of  Installation of Toroidal Field Coilstarted in Dec.2016 and will be
Vacuum Vessel wascompleted in July. 2018.
completed in Aug. 2015.

10

Deliberation Status of BA phase-Ⅱ• BA (Broader Approach) Activities were launched under the BA Agreement between Japan and
EU in 2007. It consists of (1) (IFMIF/EVEDA, (2) IFERC, and (3) Satellite Tokamak Programme (JT60SA).
• As activities after the current BA Activities which will be finished in March 2020 have not been
decided, Japan and EU are considering scope, schedule, cost and necessary administrative
procedure of JA-EU cooperation after April 2020, which is to be positioned as BA phase-Ⅱ.
• BA phase-Ⅱ Task Group established at BASC-20 submitted an interim report to the BASC-21.
• The interim report recommends the following activities in the 5 years of BA phase-Ⅱ by March
2025;(1) advancement of Prototype Accelerator produced in the current phase for the long-duration
operation (IFMIF/EVEDA).
(2) design of DEMO reactor, necessary R&D, computer simulation and the preparation of remotecontrol experiment (IFERC).
(3) development of operation scenario for the ITER and DEMO reactor through the operation of
JT-60SA, and necessary advancement of its devices (JT-60SA).
• The report also says that further discussion is needed for the whole cost and concrete activitiesof the phase-Ⅱ, as well as the share of the cost for each party.
• BA phase-Ⅱ Task Group, with government representatives to be newly appointed, will further
discuss those issues, and report to the BASC-22.
11

Outline and current status of Large Helical Device（LHD）Project
Confining the plasma：

Twist

and

Twisting the external coils ：Helical type
（LHD）
Allow Steady State Operation
for more than one year in principle
Issue ： To realize High Performance Plasma
capable of ignition→ Ion temperature of 120 million ℃（ＬＨＤ）

Doughnut-shaped magnetic
configuration
High current inside the plasma：Tokamak type
（ITER, JT-60SA）
Allow to generate High Performance Plasma

Issue ： To realize Steady State Operation
High efficiency drive of electric current inside theplasmaAdvantage of Helical type ：The adopted confining configuration “heliotron" for the
LHD is the Japanese original idea, and the devices havethe advantages of controllability and Steady State
Operation in comparison with the devices which rely on
the current inside the plasma, such as a tokamak.
Summary of Experimental Achievements in the LHD :- Long pulse operation of 54min. （world record） in 2005
- 12×1014/cc （world record) in 2008
- 120 million℃ of Electron Temperature in 2014
- 120 million ℃ of Ion Temperature in 2017

Inside the vacuum vessel (LHD)

Deuterium Experiment Plan ：Aim for high performance plasma by deuterium experiment which started in March 2017 and obtain prospectfor helical type nuclear fusion reactor design.
12Outline and current status of Fast Ignition Realization EXperiment（FIREX） Project
Laser fusion research is positioned as one of the prioritized fusion projects in Japan along with Tokamak andHelical types, and is promoted by Institute of Laser Engineering, Osaka University as a central institution.
Advantage of Fast ignition type:
Fast ignition type is the method that realizes fusion ignition by compressing thefuel with high energy laser and heat it with High intensity laser. It is expectedthat Fast ignition may make possible an ignition with one-tenth of the energy
compared to central ignition, which realizes ignition only by implosion.

Background and current situation:- Started FIREX-I Project in 2008 for demonstrating the principle of Fast ignition with
implosion laser (Gekko-XII) and Heating laser (LFEX).
- Achieved electron temperature of higher than 22 million degrees.
- Cooperation with the Lawrence Livermore National Laboratory such as exchanging ofresearchers and collaborative research using large laser devices.
The next steps:- Aim to demonstrate the ignition temperature as the original goal of FIREX-I
Project.
- Strengthen international partnerships in anticipation of FIREX-II Project
which will aim to demonstrate self-ignition.
- Promote the research in the field of High Energy Density Science with aview of application to a wide range of fields such as academic, medical, andindustrial fields.

Academic
Infrastructure

Industrial

Gekko-XII

Medical13

Content
1. Brief review of Japanese Fusion Energy Policy andJapanese Fusion Activities
2. New Policy decided on December 18, 2017
- Report on Japan’s Policy to promote R&D for a fusion
DEMO reactor –- Action plan for DEMO R&D 3. Comments on inquiries from NAS

Fusion Science in National Policy
5th Science and Technology Basic Plan （Cabinet Decision in January 2016)◇Chapter 3 Addressing economic and social issues(1) Sustainable growth and self-sustaining regional development① ⅰ）Ensuring stable energy and improving energy efficiency
・・・Furthermore, we will work on R&D aimed at establishing important energy technologies for the future,such as innovative nuclear fusion and nuclear fuel cycle technologies.
◇Chapter 4 Reinforcing the “fundamentals” for science, technology, and innovation(2) Promoting excellence in knowledge creation① ⅲ）Promoting joint international research and forming world-class research centers
・・・ As a nation, we are making advances in such areas as planning the use and operation of facilities in Japanand overseas for big science projects such as nuclear fusion, particle acceleration, and space development
and utilization, as well as constructing mechanisms to stimulate international joint research with a variety ofoverseas partners. In addition, in order to strengthen bilateral and multilateral collaboration and build mutually
beneficial relationships, we are working to enhance fund-matching partnerships and the operation of jointly
managed overseas research centers while cooperating strategicallywith partner nations with regard to the identification of common problems and similar matters.

Strategic Energy Plan （Cabinet Decision in April 2014）◇Chapter 4. Promotion of strategic technology development (energy-related technologies for which research anddevelopment should be intensively conducted in order to implement measures related to energy supply and demandin a comprehensive and systematic manner in the long-term)
2. Technical challenges to be addressed・・・Besides, GOJ steadily promotes nuclear fusion development activities, including the ITER project, which is being15
implemented through international cooperation, and the Broader Approach Activities from the long-term viewpoint.

A New Report on Japan’s Policy to promote R&D for a fusion DEMO reactor
Science and Technology Committee on Fusion Energy in MEXT(MEXT):

Ministry of Education, Culture,
Sports, Science and Technology

http://www.mext.go.jp/b_menu/shingi/gijyutu/gijyutu2/074/houkoku/1400117.htm

Japan’s Policy to promote R&D for a fusion DEMO reactor
http://www.mext.go.jp/b_menu/shingi/gijyutu/gijyutu2/074/attach/1400127.htm

Committee Members
Yuichi OGAWA(Chair)Noriyasu OHNO
(Vice Chair)
Norio ATSUMI
Michiko IGARASHI
Kiyoshi EBIZUKA
Kunihiko OKANO(TF leader)

Professor, The University of Tokyo
Professor, Nagoya University
General Manager, Nuclear Power Department, The Federation of Electric Power
Companies in Japan (FEPC)
Scientific Journalist
President, The Japan Electrical Manufactures’ Association (JEMA)
Professor, Keio University

Hiroshi OZAKI

General Manager, Nuclear Power Engineering Dept., Fuji Electric Co. Ltd.

Yasuaki KISHIMOTO
Ryosuke KODAMA
Katyuka SATO

Director of Institute of Advanced Energy and Professor, Kyoto University
President of Institute of Laser Engineering (ILE), Osaka University
Senior Managing Director, Japan Atomic Industrial Forum, Inc. (JAIF)
Associate Professor, Graduate School of Technology Management, Ritsumeikan
University
Director-General, National Institute for Fusion Science (NIFS)
Professor, National Institute for Fusion Science (NIFS)

Chikako TAKANASHI
Yasuhiko TAKEIRI
Izumi MURAKAMI
Masahiro MORI
Yoshio UEDA
(Scientific secretary)
Takeshi AKIYAMA(Scientific secretary)

Managing Director, Fusion Energy Research and Development Directorate, National
Institutes for Quantum and Radiological Science and Technology (QST)
Professor, Osaka University
Associate Professor, National Institute for Fusion Science (NIFS)Report on “Japan’s Policy to promote R&D for a fusion DEMO reactor”(December 18, 2017)@Executive Summary@Main Text
1. Background
2. Changes in the Energy Situation and Societal Demands
3. Strategy for Developing Fusion Technology for Demo
Reactors
4. Basic Concept Required for the DEMO Reactor
5. Advancement of Development for Resolution ofTechnological Issues
6. Approach for Transitioning to the DEMO Phase@Table of Check and Review Items ( Issues and Schedule)

Policy on DEMO Development
New Policy on DEMO Development has just been compiled in Dec. 2017 as the revision of thepolicy set by Atomic Energy Commission in 2005. Summary of the New Policy is as follows.
Development Strategy
 Common target for entire community is to achieve technological solution for DEMO with tokamak
 Promote balanced research on helical and laser fusion as alternative or complimentary option in parallel
Basic Concept Required for DEMO
 Steady and stable electric output (Hundreds MWe)
 Availability sufficient for commercialization
 Tritium breeding that fulfills self-sufficiency in fuel
 Inherent safety leveraged by merit of fusion (No chain reaction)
Approach for Development for Resolution of Technological Issues
 Development plan taken into account construction cost, operation scenario etc. as well as technical consistence Technological issues classified under 15 elements as “Action Plan” (see next chart) Building all-Japan framework comprising industry, academia and government
 Nurturing human resources necessary for long-term R&D
 “DEMO Reactor Development Roadmap” will be formulated integrating overall development process including
priorities, international cooperation.

Timeline for Transition to DEMO Phase
2015-

2020-

2025-

2035-

JT-60SAFirst Plasma
1st Interim C&R

ITER
First Plasma
2nd Interim C&R

ITER
DT Operation
Decision on Transition

6. Approach for Transitioning to the DEMO Phase○ The decision to transition to the DEMO phase will be taken in the 2030s when
fusion operation (DT) of ITER is expected. It is necessary that the economic
feasibility of a commercial reactor is foreseeable when transitioning to the
DEMO phase.
○ The Intermediate C&R will be reexamined and implemented in two parts:(1) When JT-60SA is expected to begin operations in around 2020
(2) Within a few years of 2025 when ITER’s first plasma is scheduled (withthe suitability of starting engineering development of the necessarycomponents of the DEMO reactor also determined)○ The Taskforce on DEMO Comprehensive Strategy under the Science andTechnology Committee on Fusion Energy of MEXT will regularly review thetimeline of the action plan and the items and timing of the intermediate checkand review through debates within and outside the fusion science community inlight of the status of the ITER project and the results of the BA activities.
○ To obtain the confidence of the public and make fusion energy the public’s
energy source of choice, outreach activities will be strategically advanced, with aheadquarter established for overall management of activities in Japan, thereby
planning and advancing collaborative activities aimed at optimizing the social
value of fusion energy.

Check and Review Items

Items① Validation of burn control in the self-heating area by ITER
② Establishment of an operational technique for stationary high-beta
plasma for operation of the DEMO reactor③ Establishment of integrated technologies by ITER
④ Material development for the DEMO reactor⑤ Technical development of reactor engineering for DEMO reactor⑥ Designing the DEMO reactor⑦ Social relations

Schedule@ 1st intermediate C&R ( ~ 2020 : JT-60SA first plasma) => to CDA phase@ 2nd intermediate C&R ( ~ 2025 : ITER first plasma)=> to EDA phase@ Transition to the DEMO reactor stage ( 2030s , ITER DT plasma)Table of Check and Review Items (Technical Issues and Schedule)
Items

Objectives by the 1st intermediate
C&R ( ~ 2020 )Objectives by the 2nd intermediate C&R Judgment criteria for transition to the DEMO
( ~ 2025 )reactor stage ( 2030s )①V alidation of burn ・Create a technical target achievement ・Reflect ITER's collaborative research incontrol in the selfheating area by ITER

plan for ITER.

・ITER maintains fusion power of Q=10 or
higher (for over several hundred seconds) andthe ITER technical target achievement plan.
validates burn control.
・JT-60SA achieves a high-beta noninductive current drive.

・Gain prospects for non-inductive steady
operation by ITER’s achievement of noncurrent drive plasma and integrated② Establishment of an ・Proceed with ITER collaborative ・Have integrated simulations including the inductive
simulations based on ITER's knowledge of burnoperational technique research and preparatory studies on
divertor verified by JT-60SA and othercontrol.
for stationary high-beta stationary high-beta plasma and start projects.
plasma for operation of JT-60SA research.
・JT-60SA validates the stationary operation of a
the DEMO reactor
high-beta (bN = 3.5 or higher) collisionless・Create a plan for JT-60SA divertor
research compatible with the DEMO
plasma regime compatible with the DEMO
reactor's plasma-facing walls.
reactor’s plasma-facing walls.
・Establish ITER's manufacturing
・Launch ITER operation.
・Establish integrated technologies through③ Establishment of technologies for superconductive coils
ITER operation and maintenance and confirm theintegrated technologies and other key components and build an ・Acquire integrated technologies tointegrated
technologicalfoundation
manufacture,
installandadjusttheITER
safety technology.
by ITERthrough the construction of JT-60SA. apparatus.
・Complete the validation of heavy
irradiation data by reactor irradiation of low
・Draw up the structural design criteria.
・Obtain low activation ferrite steel's activation ferrite steel up to 80 dpa.
reactor irradiation data of dosages up to・Establish lithium-securing techniques on a
80 dpa and finalize the materials for・Evaluate the initial irradiation behavior ofMaterial
pilot-plant scale.
④
testing under a neutron irradiation
blanket and diverter functional materials bydevelopment for theenvironment similar to nuclear fusion. reactor irradiation and validate the principles
・Collect initial irradiation data on low
DEMO reactorof lithium-securing technology.
activation ferrite steel and blanket and divertor
・Complete the concept design of thefunctional materials with a nuclear fusion
nuclear fusion neutron source.
・Start the construction of a nuclear fusion
neutron source.
neutron source and create a plan forcollecting material irradiation data.

Table of Check and Review Items (Technical Issues and Schedule) (continued)
Objectives by the 1st intermediate Objectives by the 2nd intermediate C&R
Judgment criteria for transition to the
C&R ( ~ 2020 )( ~ 2025 )DEMO reactor stage ( 2030s )・JT-60SA, LHD, etc. collect the necessary
data relevant to the divertor, including theproperties of the plasma-facing materials.
・Formulate divertor development
・Establish reactor engineering technologies
policies.
that support DEMO reactor design, including
・Create development plans for thesuperconductive coil, divertor, remotesuch items as the superconductive coil, divertor,
remote maintenance, heating/current drive, fuel・Create technical development plans maintenance, heating/current drive, fuel⑤Technical development for reactor engineering requiring early system, measurement/control, etc. for the system and measurement/ control, based on theoutcomes of the development test facilities andof reactor engineering forpreparation, including superconductive engineering technology of a medium- or
coil technology.
plant-sized reactor, and complete thethe performance results of ITER, JT-60SA, etc.
the DEMO reactor
concept designs of these items for thedevelopment test facilities.
・Collect the necessary data for
・ITER collects tritium and validates theblanket design from the cold testingevaluation technique for tritium behavior withfacilities.
・Establish foundation technology for the the nuclear fusion neutron source.
power generation blanket, build ITER-TBM
No. 1, and complete the safety verification
tests on the actual device.
・Complete the DEMO reactor’s concept
・Formulate the overall objectives fordesign that ensures high safety standards ・Acquire social acceptability, confirm
the DEMO reactor.
and economic feasibility by incorporating economic feasibility at the stage of practical use,reactor core and reactor engineeringand complete the DEMO reactor engineering
・Draw up a basic concept design of
DesigningtheDEMO
developments.
design by coordinating reactor core and reactor⑥
the DEMO reactor.
engineering developments.
reactor・Identify issues in developing reactor core・Submit requests regarding reactor
and reactor engineering to establish a・Draw up policies on safety laws andcore and reactor engineering
technological foundation for engineering regulations.
developments.
design and create a development plan.
・Establish a headquarters forpromoting social awareness.
・Proceed with social relations activities toward
・Promote social awareness initiatives andthe construction and operation of the DEMO
⑦ Social relations
conduct social relations activities.
reactor.
・Draw up an awareness activity
promotion plan.

Items

② Establishment of an operational technique for stationary high-beta
plasma for operation of the DEMO reactor[Objectives by the 1st intermediate C&R : ~ 2020]
・Proceed with ITER collaborative research and preparatory studies on stationary highbeta plasma and start JT-60SA research.
[Objectives by the 2nd intermediate C&R : ~ 2025]
・JT-60SA achieves a high-beta non-inductive current drive.
・Have integrated simulations including the divertor verified by JT-60SA and other projects.
・Create a plan for JT-60SA divertor research compatible with the DEMO reactor's plasmafacing walls.
[Judgment criteria for transition to the DEMO reactor stage : ~ 2035]
・Gain prospects for non-inductive steady operation by ITER’s achievement of noninductive current drive plasma and integrated simulations based on ITER's knowledgeof burn control.
・JT-60SA validates the stationary operation of a high-beta (bN = 3.5 or higher)
collisionless plasma regime compatible with the DEMO reactor’s plasma-facing walls.

④ Material development for the DEMO Reactor[Objectives by the 1st intermediate C&R : ~ 2020]
・Obtain low activation ferrite steel's reactor irradiation data of dosages up to 80 dpa andfinalize the materials for testing under a neutron irradiation environment similar to
nuclear fusion.
・Complete the concept design of the nuclear fusion neutron source (A-FNS).
[Objectives by the 2nd intermediate C&R : ~ 2025]
・Complete the validation of heavy irradiation data by reactor irradiation of low
activation ferrite steel up to 80 dpa.
・Evaluate the initial irradiation behavior of blanket and diverter functional materials byreactor irradiation and validate the principles of lithium-securing technology.
・Start the construction of a nuclear fusion neutron source and create a plan forcollecting material irradiation data.
[Judgment criteria for transition to the DEMO reactor stage : ~ 2035]
・Draw up the structural design criteria.
・Establish lithium-securing techniques on a pilot-plant scale.
・Collect initial irradiation data on low activation ferrite steel and blanket and divertor
functional materials with a nuclear fusion neutron source.

⑤ Technical development of reactor engineering for DEMO reactor[Objectives by the 1st intermediate C&R : ~ 2020]・Formulate divertor development policies.
・Create technical development plans for reactor engineering requiring early preparation,
including superconductive coil technology.
・Collect the necessary data for blanket design from the cold testing facilities.
[Objectives by the 2nd intermediate C&R : ~ 2025]
・JT-60SA, LHD, etc. collect the necessary data relevant to the divertor, including theproperties of the plasma-facing materials.
・Create development plans for the superconductive coil, divertor, remote maintenance,
heating/current drive, fuel system, measurement/control, etc. for the engineering
technology of a medium- or plant-sized reactor, and complete the concept designs of these
items for the development test facilities.
[Judgment criteria for transition to the DEMO reactor stage : ~ 2035]
・Establish foundation technology for the power generation blanket, build ITER-TBM No. 1,
and complete the safety verification tests on the actual device.
・Establish reactor engineering technologies that support DEMO reactor design, including
such items as the superconductive coil, divertor, remote maintenance, heating/current
drive, fuel system and measurement/ control, based on the outcomes of the development
test facilities and the performance results of ITER, JT-60SA, etc.
・ITER collects tritium and validates the evaluation technique for tritium behavior with thenuclear fusion neutron source.

All-Japan framework for Fusion DEMO
Power
Generation＜＞

Discuss and decide the policy on fusion R&D, including Road-map

DEMO
Reactor

Review

Draw up/Formulate an Action
PlanShow the policy＜＞

DEMO Concept Design
Total 84 persons*As of Sep 2017
QST 28NIFS
3Univ. 28
NIMS 1
Industry 24＜＞
Providing collaboration-Plan and implement R&D to address
issues- Organize Work Shops

Material

QST,NIFS,Univ.,Industry

Theoretical
AnalysisSuperconducting-grasp the situation of elemental
Sharing information etc. technologies as a whole-Optimize the overall strategy

Plant
engineering
Divertor,
BlanketTritium

Fusion reactor
PlasmaHeating28

Action Plan
Published by Task-force sub-committee on DEMO Comprehensive Strategy
of MEXT in 18 December 2017)

An action plan presented here is the plan toward
construction of a Demo reactor in Japan. A Task-force on
DEMO Comprehensive Strategy was established in MEXT,
and has considered an action plan, so as to provide R&D
issues for the decision to DEMO construction in 2030s.
The action plan will lead works in a Joint Special Design
Team for Fusion Demo established for design and R&D of
the Demo reactor in Japan.

Member s of Task Force sub-committee

Kunihiko Okanoa, Ryuta Kasadab,Yasushi Ikebec, Yasutomo Ishiid1,
Kyoko Obae, Mieko Kashiwagid2,Ryuichi Sakamotof, Naoki Sawag,
Hidenobu Takenagad2, Arata Nishimuraf, Masaru Fukuieh,
Shinsuke Fujiokai, Yoshio Uedai, Tsuyoshi Akiyamaf
aKeio University, Yokohama, Japan : Task Force Leader

bTohoku University, Sendai, Japan : Task Force Sub-Leader

cNational Museum of Emerging Science and Innovation, Tokyo, Japan

d1National Institutes for Quantum and Radiological Science and Technology, Rokkasho, Japan
d2National Institutes for Quantum and Radiological Science and Technology, Naka, JapaneJapan Atomic Energy Agency, Tokai, Japan

fNational Institute for Fusion Science, Toki, JapangMitsubishi Heavy Industries Ltd., Kobe, Japan
hToshiba Corporation, Kawasaki, Japan
iOsaka University, Osaka, Japan

Outline of Action Plan for a DEMO development （rev. 2017.12）
Ⅰ Action Plan for a DEMO development composition table
While viewing the whole, We made a composition table that can list actions at hand for the time being.
【Technical Issue items 】(0) Reactor Design(1) Superconducting Coils(5) Theory and Numerical Simulation Research(2) Blanket(3) Divertor (4) Heating and Current Drive Systems(6) Reactor Plasma Research(8) Material Development and Establishment of Codes and Standards(10) Availability and Maintainability(13) Helical(7) Fuel Systems(9) Safety of DEMO and Safety Research(11) Diagnostics and Control Systems(12) Cooperation with the Society(14) Laser(Image of table)

Basic design ofconcept
２０１５

２０２０~
Action 1♯Field of R&D

Conceptual design Engineering design
２０２５~

２０３５~

Action 2
Action 3

Issue 1(17)○○○○○○○○ーー＞(24)Issue 2 (15)○○○○○ ーー＞(19)

Ⅱ Explanation by Action plan items
Supplementary explanation of each item is attached to the composition table.

31

31

Phases of Action
Black: Kick off of Yearof Items
Red : Close of items

Basic design of concept

2015

Conceptual design

2020~

Engineering Design

2025~

2035~

0.Demo Design
Concept &Construction plan

(2015)S: Phys.& eng. guideline→(2019)(2015)S: Basic design of concept →(2019)(2016)S/TF: Fuel cycle strategy -----------------(2017)Q/N/U/S: Integrated simulator ------(2018)S/D: Cost evaluation ---------------------

Equipment Design

Safety Policy

Database of Physics,
Engineering &Materials(2015)S/Q: Basic design of SC→(2019)(2019)S/Q: Demo TBM targets →(2019)(2017)S/D: Equip. config. w/BOP →(2019)(2020)S/D: Conceptual design→(2026)--------------------------------------------------> (2026)--------------------------------------------------> (2026)(2023)S/Q/F: Rev. of target plasma →(2026)---------------------------------------------------->(2021)S/D: Conceptual Design of BOP →(2026)(2027)D/S: Design of Demo core parts→(2035)---------------------------------------------------> (2031)(2029)G/TF: Decision of candidate site →(2031)(2032)G: Site assessment→(2035)(for site asses.)(2027)D/S: Design of plant, build..& Equip→(2031)(2027)A/S: Regulation & standard→(2031)(after decision of standard & site candidates)(2032)D/S: Design plant/build./equip→(2035)→(2019)(2020) S/D: Asses. of Safety aspect --------------(2020)S/D: Asses. of Safety aspect→(2026)(2020)TF/S: Draft for safety regulation →(2026)---------------------------------------------------> (2031)(2027)G/TF: Safety regulation→(2035)(2032)G: Safety assessment →(2035)(2016)Q/U/F/S: Demo Phys. DB -----------------(2016)Q/U/F/S: Eng. & Materials DB ----------------------------------------------------------------->(2026)------------------------------------------------------>(2026)(2027)Q/S: Update Eng.& materials DB→(2031)
w/ results by JT-60SA(2032)Q/S: Update material DB→(2035)
w/ 14MeV heavy irradiationdata(2016)S/D: Draft of safety policy

Organization expected to be in charge
G : Japanese Government
S : Joint Special Design Team for DEMO
Q : QST (Dep. of Fusion)
N : NIFS
U : Universities
D : Industries
F : Fusion Energy Forum

C1～C5 : See the list (right)
A : Academies
I : ITER team in JP
M: National Institute of material Science
Qw: QST(West)
TF: Task Force
HQ: Head Quarter for Outreach

List of Center and Labs
C1：Ins. of Laser Engineering Osaka University
C2 : Institute of Advanced Energy Kyoto University
C3 : Plasma Research Center. University of Tsukuba
C4 : Res. Ins. for Applied Mechanics Kyushu University
C5 : Hydrogen Isotope Research Center Univ. ToyamaPhases of Action
Black: Kick off of Items
Red : Close of items

Basic design of concept

2015

8.Fusion Materials &Standard, Code(1)Structure Materials
for Blanket (Blk)Engineering Design
2035~

2025~

2020~

Clarification of material spec. for Demo / Proposal of technical spec. for structure material
Mass-production technology / Blk structure production technology
Reliability evaluation & code of small specimen testing technology
Environment data of jointed cover parts

FNS:Fusion Neutron
SourceConceptual design

Irradiation data by fission reactors
Irradiation test by A-FNS

Evaluation of fusion neutron irradiation effects/irradiation-induced degradation model/Establishment of standards for structure design
Decision for utilization of advanced Blk materials
Expansion of database for advanced Blk materials

Low activation Ferritic
Steel(15)Q/S/U: Clarification of material spec.
& technical spec. for Demo --(15)Q/D: Mass-production -------------------------(15)Q/D: Establishment of Blk structure
production technology ---(15)Q/D/A: Reliability evaluation & code ofsmall specimen testing technology ---(15)Q: Environment data of jointed cover partsby cold test --(15)Q: 80dpa data by fission reactor
(19)(15)Q: Environment data of jointed
cover parts ---(15)Q/N/U: Evaluation of effects of He &fusion neutron irradiation, establishment ofdegradation model ---(15)Q/D/A: Policy towards structural designcode based on irradiation results---(15)Q/D/A: Academic activity towards
material codes ----

Advanced Blk Materials(15)S/Q/N/U: Decision for utilization ofadvanced Blk materials ---(15)Q/N/U: Expansion of database foradvanced Blk materials -------------------------------------------------------------> (26)---------------------------------------------------------> (26)---------------------------------------------------------> (26)---------------------------------------------------------> (26)----------> (22)(20)Q: Verification of 80dpa data by

Fission reactor (26)--------------------------------------------------------------->-------------------------------> (31)(30)Q: Irradiation test by A-FNS--------------------------------------------------------------->----------------------------------------------------------> (35)(27)Q/D/A: Structural design code based on theirradiation results(35)(35)---------------------------------------------------------> (26)--------------------------------------------------------------->----------------------------------------------------------> (35)---------------------------------------------------------> (26)--------------------------------------------------------------->----------------------------------------------------------> (35)Phases of Action
Black: Kick off of Items
Red : Close of items

Basic design of concept

2015

8.Fusion Materials &Standard, Code(2)Other materials

Conceptual design

2035~

2025~

2020~

Optimization of production and recycling of functional
breeding materials

Engineering Design

Evaluation of irradiation effect by fission reactor

Test by A-FNS

Evaluation of mech. data & establishment of production for breeders (ITER-TBM #2)
Securement technology for Lithium (Li)Test by A-FNS

Devel. of irradiation resistant Div materials, evaluation of irradiation effects by fission reactor(3)Fusion Neutron
Source (FNS)

Irradiation effect database for diagnostics /control materials, by fission reactor

Evaluation of radiation database for diagnostics /control materials,
by fission reactor

Test by A-FNS

Compilation of fusion materials handbook

Design & construction of A-FNS

Operation of A-FNS(15)Q: Optimization of production andrecycling of functional breeding materials ----(18)Q: Evaluation & production of irradiation
resistant Div materials ----------> (22)(23)Q: Irradiation effects by fission reactor -------------------------------------------------------------------->(18)Q: Securement technology for lithium ------------------------------------------------------------------->(15)N/U: Irradiation effect by fission reactor (18)Q/N/U: Development & evaluation ofirradiation resistant materials -------------------------------------------------------------> (26)-------------------------------------------------------------->----------------------------------------------------------> (35)Materials fordiagnostics & Control(15) Q/S: Database construction of irradiation
effects (19)(20)J/N/U: Evaluation of irradiation resistantmaterials (35) --------------------------------------------------------------> (35)Others(15) Q/N/U: Compilation of fusion materials
handbook (19)--------------------------------------------------------------->------------------> (30)Functional Breeding
Materials(Neutron breeder &Tritium Multiplyer)
Divertor Materials

Fusion Neutron Source(FNS)(15) Q: Design & construction of A-FNS------------------> (30)------------------> (30)(30)Q: Irrad. test by A-FNS (35)----------------------------------------------------------> (35)(30) Q/U: Operation of A-FNS (35)Content
1. Brief review of Japanese Fusion Energy Policy andJapanese Fusion Activities
2. New Policy decided on December 18, 2017
- Report on Japan’s Policy to promote R&D for a fusion
DEMO reactor –- Action plan for DEMO R&D 3. Comments on inquiries from NAS

Inquiries from NAS Committee(1)the Japanese strategic plan for the development and demonstration of fusionenergy,=> Report on “Japan’s Policy to promote R&D for a fusion DEMO
reactor” (December 18, 2017)(2) any lessons learned from the formulation of the Japanese strategic plan,(3) your views of role of international partnership in fusion energy research,
including participation in the ITER project and research plans for JT-60SA,(4) the value of various magnetic confinement concepts in a synergetic scenario forfusion reactor development,(5) any strategic approaches that might further strengthen or accelerate fusionenergy development as an economical energy source of electricity.

(2) any lessons learned from the formulation of the Japanese
strategic plan
@ A phased program : development program proceeds to the next
phase on the basis of successful results on the critical path of thepresent phase concerned.
@ International collaboration (bi-lateral, multi-lateral) becomes very
important; i.e., US/Japan collaboration program since 1979,
ITER project, EU/Japan BA activities.
@ Toward 4th phase (i.e., DEMO phase), the strategy has been
intensively discussed at the committee of MEXT including many
experts from a wide field, and the R&D program to DEMO has
been updated in 2005 and 2017.
@ Toward to the transition to DEMO phase ( ~ 2030s), the Checkand Review will be carried out in ~2020 (JT-60SA First Plasma)and in ~2025 (ITER First Plasma).

(3) Your views of role of international partnership in fusion energy research,
including participation in the ITER project and research plans for JT-60SA@ Long history of US/Japan bi-lateral collaboration since 1979;( DIII-D, HFIR, JIFT, etc. )=> A fruitful scientific outcome=> Contribution to human exchange and young talent training@ EU/Japan bilateral collaboration has been strongly promoted
through BA activities such as JT-60SA, IFMIF/EVEDA and IFERC.
@ multi-lateral cooperation era such as ITER
@ Bi-/multi- lateral international cooperation for DEMO R&D,
including burning plasma physics in ITER, high-beta study in JT60SA and material development with IFMIF, might be effective foraccelerating fusion reactor development and for saving investment
cost.

(4) the value of various magnetic confinement concepts in asynergetic scenario for fusion reactor development@ Helical system has an advantage for steady-state operation, and
LHD has demonstrated a 54 min. operation with a power levelof 1 MW. Since 3-D effect such as RMP coil to suppress giant
ELMs becomes important in tokamak plasmas, knowledge andexperiences in helical plasmas would contribute to these 3-D
physics in fusion plasmas.
@ Since many technical issues in action plan are common between
tokamak and helical, we have no distinction among various
magnetic concepts.

Synergetic development scenario

ELM
control

ITER

In-vessel coil
 Magnetic island,
stochastic field

Synergetic effect between tokamak and helicalplasmas on the scenario of fusion reactor
development

(5) any strategic approaches that might further strengthen or accelerate fusionenergy development as an economical energy source of electricity@ The committee consists of the experts of a wide field; i.e., fusion
community, industry, electric utility, technology management
specialist and journalist.
@ Comprehensive analysis of introduction of fusion energy into theworld electric power market has been carried out.
@ A support from public is quite important and indispensable,
because fusion energy development needs a relatively large budget
and a long development period. An importance of outreachactivities for fusion energy development is assessed at thecommittee, and the performance of outreach activities is included
as one of the check & review items.

Committee Members
Yuichi OGAWA(Chair)Noriyasu OHNO
(Vice Chair)
Norio ATSUMI
Michiko IGARASHI
Kiyoshi EBIZUKA
Kunihiko OKANO(TF leader)

Professor, The University of Tokyo
Professor, Nagoya University
General Manager, Nuclear Power Department, The Federation of Electric Power
Companies in Japan (FEPC)
Scientific Journalist
President, The Japan Electrical Manufactures’ Association (JEMA)
Professor, Keio University

Hiroshi OZAKI

General Manager, Nuclear Power Engineering Dept., Fuji Electric Co. Ltd.

Yasuaki KISHIMOTO
Ryosuke KODAMA
Katyuka SATO

Director of Institute of Advanced Energy and Professor, Kyoto University
President of Institute of Laser Engineering (ILE), Osaka University
Senior Managing Director, Japan Atomic Industrial Forum, Inc. (JAIF)
Associate Professor, Graduate School of Technology Management, Ritsumeikan
University
Director-General, National Institute for Fusion Science (NIFS)
Professor, National Institute for Fusion Science (NIFS)

Chikako TAKANASHI
Yasuhiko TAKEIRI
Izumi MURAKAMI
Masahiro MORI
Yoshio UEDA
(Scientific secretary)
Takeshi AKIYAMA(Scientific secretary)

Managing Director, Fusion Energy Research and Development Directorate, National
Institutes for Quantum and Radiological Science and Technology (QST)
Professor, Osaka University
Associate Professor, National Institute for Fusion Science (NIFS)

Introduction of fusion energy into the world energy market
TOKIMATSU, K., et al., Studies of breakeven prices and electricity supply potentials of nuclear
fusion by a long-term world energy and environment model, Nuclear Fusion 42 (2002), 1289.

Electricity in the world (TWh)FusionCoal

1st fusion reactor@ In the case of 550 ppmv CO2 concentration constraint.
@ Future energy demand is assumed to be the case of IS92a.
@ In nuclear fusion the cost of electricity (COE) in the introduction year (i.e., 2050)
is assumed to be 65 mill/kWh,43

⑦ Social relations[Objectives by the 1st intermediate C&R : ~ 2020]
・Establish a headquarter for promoting social awareness.
・Draw up an awareness activity promotion plan.
[Objectives by the 2nd intermediate C&R : ~ 2025]
・Promote social awareness initiatives and conduct social relations activities.
[Judgment criteria for transition to the DEMO reactor stage : ~ 2035]
・Proceed with social relations activities toward the construction and operationof the DEMO reactor.

Thank you for your attention !

Appendix(Executive Summary)1. Background○ Over 10 years have passed since the formulation of the“Future Fusion Research and Development Strategy”(formulated by the Japan Atomic Energy Commission’s
Advisory Committee on Nuclear Fusion in October 2005,
hereinafter referred to as Fusion R&D Strategy).
Amid various changes over the years, the Science andTechnology Committee on Fusion Energy of MEXT believed
it necessary to prepare a new report on the course of researchand development of the DEMO reactor, considering theinternal and external factors surrounding fusion research anddevelopment.

2. Changes in the Energy Situation and Societal Demands○ Since the accident at Tokyo Electric Power Company’s Fukushima Daiichi
Nuclear Power Plant, people have been losing confidence in nuclear power. The
principle of nuclear fusion differs from that of nuclear fission and can be said tobe intrinsically safe. However, the accident mentioned above should be a lesson
for those who are involved in nuclear fusion since it deals with neutron andradioactive substances as is the case with nuclear fission.
It should be understood while establishing the fusion DEMO reactor that thereactor is expected to have an even higher level of safety than the current levelof nuclear safety technology because it would not be possible to introduce afusion DEMO reactor in Japan without first obtaining the confidence of the
public.
○ This research and development should be advanced focusing on the economic
rationality of fusion technology compared with other greenhouse gas emission
reducing technologies, such as renewable energy and nuclear power, while also
being positioned as a revolutionary technology capable of changing thecorrelation between economic development and the emission of greenhousegases.

3. Strategy for Developing Fusion Technology for Demo Reactors○ The common objective set for the entire fusion community including industry,
academia and the government is to develop a technology that fulfills theconditions required for transitioning to the fourth phase of fusion scienceand development process with a tokamak, which is the most advanced
reactor type at present.
○ With safety at the DEMO reactor as a major premise, the technicalpracticality of reactor engineering should be demonstrated and research
conducted to achieve a realistic reactor in line with the economic situation at
the period of commercialization.
○ Comprehensive activities characterized by a degree of diversity should be
advanced to promote the acceleration of research and development and toresolve various issues. While striving for steady progress on the tokamak
reactor, research on helical and laser systems which are complementary andalternative to tokamak as well as other innovative concepts should also be
conducted in parallel.

4. Basic Concept Required for the DEMO Reactor○For commercialization of fusion energy, the objective of the DEMO reactor isto(1) realize a steady and stable electric output of over several hundred
thousand kilowatts,(2) availability sufficient for commercialization,(3) overall tritium breeding that fulfills self-sufficiency in fuel.
○ To achieve the basic concepts mentioned above, it is necessary to(1) ensure safety base on ALARA,(2) achieve an acceptable level of construction costs,(3) design a flexible blanket and divertor.
○ Additionally, during the operational development phase of the DEMO reactor,
it is also important to realize(1) particle control and plasma control,(2) a practical maintenance scenario and availability,(3) high performance of the blanket and divertor.

5. Advancement of Development for Resolution of Technological Issues○ In formulating the development plan, issues and development targets should be
identified based on the finalized technical specifications, keeping in mind plant
construction and operation costs, the operation scenario, as well as technicalconsistency. The development plan should classify the technological issues that
include superconducting coils, and organize and analyze the progress of each issue
and the connection between issues as an action plan.
○ With a view to steadily resolving such technological issues, there is a need tostrengthen research and development by building an all-Japan framework comprisingindustry, academia and government. To make this effective, the Rokkasho site should
be upgraded as the central hub for developing the DEMO reactor.
○ To promote long-term research and development, the necessary human resources forresearch and development of the DEMO reactor must be nurtured through close
collaboration among industry, academia and government by promoting organic
cooperation of the ITER project, BA activities and advanced academic research. A
reactor design framework comprising diverse human resources with multiple
perspectives will be drawn up as well through various collaborations that include thehumanities and social sciences, along with promoting participation from other fields.

5. Advancement of Development for Resolution of Technological Issues(continued)○ For promoting international collaboration, issues that Japan must resolve
alone and issues it must resolve through international collaboration should
be distinguished strategically and rationally. Moreover, from the perspectiveof international contribution, Japan must play a leading role amid thedevelopment of DEMO reactors around the world.
○ Safety guidelines and safety requirements for the fusion DEMO reactor,
which is required to have high intrinsic safety, must be promptly formulated
from the viewpoint of the public and the environment. This should be done incooperation with experts from various fields in Japan and abroad, promoting
comprehensive fusion safety research.
○ To build a framework for the technical base, a DEMO reactor development
roadmap will be formulated integrating the overall development process,including development priorities, milestones and areas for international
collaboration, along with the action plan.

6. Approach for Transitioning to the DEMO Phase○ The decision to transition to the DEMO phase will be taken in the 2030s when
fusion operation (DT) of ITER is expected. It is necessary that the economic
feasibility of a commercial reactor is foreseeable when transitioning to the
DEMO phase.
○ The Intermediate C&R will be reexamined and implemented in two parts:(1) When JT-60SA is expected to begin operations in around 2020
(2) Within a few years of 2025 when ITER’s first plasma is scheduled (with thesuitability of starting engineering development of the necessarycomponents of the DEMO reactor also determined)○ The Taskforce on DEMO Comprehensive Strategy under the Science andTechnology Committee on Fusion Energy of MEXT will regularly review thetimeline of the action plan and the items and timing of the intermediate checkand review through debates within and outside the fusion science community inlight of the status of the ITER project and the results of the BA activities.
○ To obtain the confidence of the public and make fusion energy the public’s
energy source of choice, outreach activities will be strategically advanced, with aheadquarter established for overall management of activities in Japan, thereby
planning and advancing collaborative activities aimed at optimizing the social
value of fusion energy.