National Institute for Fusion Science (NIFS)
National Institutes of Natural Sciences (NINS)

External Peer Review Reports in FY2014

March, 2015

External Peer Review Committee, NIFS Advisory Committee

Contents
Chapter1

Background ···················································· 1

Reviews and Proposals ···································· 5
2.1 Summary of the External Peer Review ····························· 5
2.2 Recommendations ···················································· 9

Chapter2

Chapter3

In Closing ······················································11Documents

2014 External Peer Review Presentation Materials

Appendix: Charts of review results

Chapter 1

Background

In order to advance fusion research in universities, the National Institute for Fusion Science (NIFS),
as an Inter-University Research Institute, was established in 1989 with the Large Helical Device(LHD) as the main device. Planned to bear the collective opinion and expectations of the fusion
community and with the special characteristic of generating a heliotron-type magnetic field using a
superconductor, an idea developed in our country, the LHD, together with generating
high-performance plasma by using the helical magnetic field configuration through high-power
heating, is advancing experimental research that aims at clarifying physics and engineering issues in
anticipation of the achievement of a toroidal magnetic field confinement fusion reactor.On the other
hand, parallel with this, theoretical research utilizing large-scale simulations is essential in analysis
of fusion plasmas of great complexity. At NIFS we have introduced the most advanced
supercomputers, and having made these supercomputers available through joint-use with fusion
theory scholars throughout Japan we thus have moved forward with pioneering research.

During this time, there have been changes in the domestic academic research system, and since 2004
NIFS, as an institute in the Inter-University Research Institute Corporation National Institutes of
Natural Sciences, has advanced still further in countrywide joint use and joint research. Upon
incorporation, we developed a six-year mid-term plan, and a system for receiving an annual
evaluation regarding the state of our progress was introduced. This annual evaluation focuses
primarily on management. Regarding research results, NIFS has determined that receiving anevaluation by external experts is important. Under the Advisory Committee, an external peer review
committee is organized and each year an evaluation of research is conducted. The evaluation topics
are decided by the Advisory Committee, and the evaluation is undertaken by the External Peer
Review Committee, which is composed of the external Advisory Committee members and foreign
experts appropriate for the evaluation topics. The External Peer Review Committee reports theresults of its evaluation to the Advisory Committee, and NIFS respects those results, which become
useful for improvement in the next fiscal year’s research activities.

At NIFS, upon the start of the second mid-term goals period that began in 2010, in order to further
strengthen the centripetal force of NIFS as a Center of Excellence (COE) in the field of plasma andfusion research we designed research projects in three areas: the LHD, the Numerical Simulation
Reactor Research, and the Fusion Engineering Research. Looking toward the realization of thefusion reactor, we then initiated research planning that would unify the results of these projects. For
this reason, in FY 2010 we revised the research structure of NIFS. Placing all research staff members
in one research department, we introduced a structure by which each researcher would freely select1the research project in which she/he would participate. Since then, coordination among the LHD
Project, the Numerical Simulation Reactor Research Project, and the Fusion Engineering Research
Project has become much closer, and we have become able to respond to new issues as occasion
demands.

In the Advisory Committee meetings, in order to confirm results of the research project system, we
conducted the external peer review on the LHD Project in 2011, the Numerical Simulation Reactor
Research Project in 2012, and the Fusion Engineering Research Project in 2013. We then assigned
the “Deuterium Experiment Implementation Plan” as the subject for external peer review in 2014. To
serve as members of the external peer review, we selected ten members of the Advisory Committee
who are outside of NIFS and four members from foreign countries. Furthermore, the Experts
Committee on this topic was composed of the External Peer Review Committee and five specialists
outside of NIFS. In this way, we composed the External Peer Review Committee and the Experts
Committee and then conducted the evaluation.

At the first meetings of the External Peer Review Committee and the Experts Committee, whichwere held on September 12, 2014, we discussed how to move forward with this fiscal year’s external
evaluation, and decided upon the perspectives and the specific issues for evaluation. We will
introduce this information below. At the second meetings of the External Peer Review Committee
and of the Experts Committee, which were convened on November 29, 2014, we received from each
person in charge at NIFS a detailed explanation that used viewgraphs to treat the points forevaluation and materials regarding the reports of activities. A discussion session followed.
Subsequently, on January 29, 2015, the third meetings of the External Peer Review Committee andthe Experts Committee were held. Including further discussion with NIFS, these committees
undertook evaluation duties that followed the points and items that had been determined at thecommittee meetings. With the draft version of the evaluation submitted, on February 24, 2015, thefourth External Peer Review Committee meeting and the Experts Committee meeting were held. The
final report was compiled.

This report is composed of the following four parts: Part 1: The Particulars to Present; Part 2:
Evaluations by Item; Part 3: Summary of the Evaluations, and Recommendations; and Part 4:
Conclusion.

After this report is approved by the NIFS Advisory Committee, the Director General of NIFS willsubmit it to the President of the National Institutes of Natural Sciences (NINS). Subsequently, after
approval by the Education and Research Council and the Administrative Council of NINS, this2

report is expected to be reference material in the reports “2014 Fiscal Year Report on Management
and Achievements” and “National Institutes of Natural Sciences Annual Plan (2015)” to besubmitted to the Ministry of Education, Culture, Sports, Science and Technology. This report will bemade public as a printed text and on the NIFS homepage.

The points for evaluation in the “Deuterium Experiment Implementation Plan” are composed ofrequisite items for evaluation of the research plan and the safety management plan, and of thereadiness of the plans for the LHD Deuterium Experiment, which will advance as an important NIFS
plan in the third mid-term plan that the Inter-University Research Institute Corporation National
Institutes of Natural Sciences will formulate. The appropriateness and the level of achievement willbe the basis of the points for evaluation.

Further, referencing the “Recommendation” in the external peer review regarding safety
management that was implemented in 2009, the following two points were considered in thisevaluation.

1. Are the training and the education of the people who will be responsible at the time of thedeuterium experiment being conducted appropriately?
2. Are the Safety Committee and the Safety Surveillance Committee for Radiation Safety
Management, the organization of the Radiation Control Office, and the systems for responses toemergencies being constructed appropriately?

The topics in the “Deuterium Experiment Implementation Plan” for the fiscal year 2015
evaluation are as follows below.

[1] Research Plan
(1) Is the goal of the deuterium experiment appropriate? Further, do the research plan and theimplementation system for ensuring safety achieve those goals?
(2) Does this plan contribute to the promotion of a comprehensive understanding of toroidal
plasma and heighten its academic value with regard to the realization of fusion energy?
(3) Regarding implementation of the plan, will this achieve a system of joint use and joint
research that enables participation by a wide range of researchers?

[2] Deuterium Experiment Preparation System(1) Moving toward the initiation of the deuterium experiment in 2016, is the preparation of3

equipment and facilities being planned appropriately?
(2) Is the preparation system for the initiation of the deuterium experiment appropriate? Is
preparation of the facilities and devices, including safety equipment, being advanced
appropriately?

[3] Safety Management Planning(1) Is the fundamental concept regarding safety management appropriate at the time of theformulation of the deuterium experiment implementation plan as also based upon the opinions
of local residents?
(2) Are safety management equipment, facilities, and experiment equipment being planned
appropriately for the safe accomplishment of the deuterium experiment and to be managed formaintenance?
(3) In order to safely accomplish the deuterium experiment, are various types of regulations being
formulated appropriately?
(4) Are the operation manual, the radiation management manual, and the emergency measuresmanual being formulated appropriately?
(5) Are the organization of and the system for safety management while the deuterium
experiments are being conducted constructed appropriately?
(6) Are education and training for the safe execution of the deuterium experiments, and nurturingof those responsible for safety management being undertaken appropriately?

[4] Understanding by Society and Citizens(1) Is enhanced understanding of the safety of the deuterium experiment being advanced
appropriately to local residents?
(2) Is promotion of the deuterium experiment plan being designed in conjunction with local
governments?
(3) Is the importance and the safety of fusion research being widely disseminated in society?

4Chapter 2

Reviews and Proposals

Points for evaluation results are summarized based on discussions by the External Peer Review
Committee and the Experts Committee, and several important recommendations are proposed topromote the “Deuterium Experiment Implementation Plan.”

2.1 Summary of the External Peer Review[1] Research Plan

(1)

Is the goal of the deuterium experiment appropriate? Further, do the research plan andthe implementation system for ensuring safety achieve those goals?

From the deuterium experiment, research in high-performativity through improvement ofconfinement, isotope effects, and confinement of high energy ions will advance, andcontributions to the comprehensive understanding of toroidal plasmas are anticipated. Suchgoals as these are appropriate. This is a research plan, which together with expanding theplasma parameter regime through the improvement of confinement and the strengthening ofheating devices, will expand toward new research realms through the maintenance of neutron
diagnostics and high precision diagnostics, and maintenance of the closed divertor. And
combined with the advances in the preparation of securing the safety of the deuterium
experiments, we highly evaluate this plan.
Next, together with deepening further discussion regarding the formulation of concrete
experimental planning, it is necessary to academically verify the isotope effect in improving
confinement in helical devices and to contribute to a comprehensive understanding of toroidal
plasma. The safety measures and the implementation system for advancing with this research
are appropriate. In the future, while adding further examinations that include additional
researchers, it will be desirable to advance while planning continuous revisions of the safety
management system.

(2)

Does this plan contribute to the promotion of a comprehensive understanding of toroidal
plasma and heighten its academic value with regard to the realization of fusion energy?

Through confinement improvements and elucidation of physics, improvement of MHD
stability and enlargement of the high beta region, confinement of high energy ions,
optimization of the divertor, plasma wall interaction, and diversification of ICRF heating, this5

is a plan that heightens the academic value in achieving fusion, and is highly evaluated.
Through the closed divertor and by applying a perturbation magnetic field, the transportphenomenon in edge plasma will develop, and contributions to the control of particles in coreplasma are expected. This is highly evaluated.
Considering cases in which improved confinement through the isotope effect are insufficient,
it is hoped that there will be elucidation of various confinement improvement methods andthat there will be predictions regarding modeling.

(3)

Regarding implementation of the plan, will this achieve a system of joint use and joint
research that enables participation by a wide range of researchers?

Establishing links with research institutions in Japan and abroad through joint research
projects aiming toward the deuterium experiment, results have been achieved in neutron
diagnostics, tritium recovery, plasma wall interaction, and other fields. We highly praise theformation of a countrywide research network.
That NIFS has held joint meetings for research planning for the deuterium experiment and forsafety management planning with the Fusion Network as well as with the Experts Committeeof The Japan Society of Plasma Science and Nuclear Fusion Research, and that NIFS has held
discussions with a wide range of researchers at symposia and invited lectures in the case ofacademic society are also evaluated highly.

[2] Deuterium Experiment Preparation System(1)

Moving toward the initiation of the deuterium experiment in 2016, is the preparation ofequipment and facilities being planned appropriately?

Aiming toward the deuterium experiment, NIFS is planning appropriately repairs

andimprovements to facilities for establishing the controlled area, reinforcement of the NBI,
development and maintenance of neutron diagnostics, and planning and construction of adiagnostic for the tritium recovery. We highly evaluate this, and also evaluate that NIFS isadvancing appropriately the maintenance execution plans by separating them into three stages.

(2)

Is the preparation system for the initiation of the deuterium experiment appropriate? Is
preparation of the facilities and devices, including safety equipment, being advanced
appropriately?

6

Aiming toward the initiation of the deuterium experiment, we highly evaluate theestablishment of the Division of Deuterium Experiments Management. Under its direction,
preparation of manuals, preparation and improvement of facilities, and the preparation ofsafety facilities were implemented without delay.

[3] Safety Management Planning(1)

Is the fundamental concept regarding safety management appropriate at the time of theformulation of the deuterium experiment implementation plan as also based upon theopinions of local residents?

We judge the fundamental way of thinking regarding safety to be satisfactory. And
implementing a system for monitoring the environment for very small amounts of tritium too
can be praised from an academic perspective. Further, compliance is important, but because
introducing excessive self-regulation together with hindering academic development will also
affect the operation of other RI facilities, it is necessary to make NIFS regulations abundantly
clear and to move forward so that these do not become standards.

(2)

Are safety management equipment, facilities, and experiment equipment being planned
appropriately for the safe accomplishment of the deuterium experiment and for theirmaintenance?

We judge and highly evaluate that the safety management instruments and facilities, and theexperiment equipment will safely perform the deuterium experiment, and that operation andmaintenance are being appropriately planned. Further, we would like the disposal of tritiatedwater to move forward in close cooperation with the Japan Radioisotope Association.

(3)

In order to safely accomplish the deuterium experiment, are various types of regulations
being formulated appropriately?

We highly evaluate that regulations have been sufficiently prepared for safe execution of thedeuterium experiment. Further, regarding the handling of radioactivated materials, we seek
sufficient study. Depending upon the material and the region in the LHD, radioactivatedmaterials are subjects of research, and it is necessary to clarify that it is possible to transfer
them according to law.

7

(4)

Are the operation manual, the radiation management manual, and the emergency
measures manual being formulated appropriately?

Manuals for the safe accomplishment of the deuterium experiments are being basically
prepared, and these are highly evaluated. It may be stated that it is better for times of
emergency to write the division/section and the telephone numbers to contact specifically.
Further, as a more specific evaluation, in treating radioactivated materials, it is thought to benecessary to prepare a manual that includes concrete methods for measurement.

(5)

Are the organization of and the system for safety management while the deuterium
experiments are being performed being constructed appropriately?

The organization of safety management is highly evaluated for having been sufficiently
prepared. However, so that inflexibilities due to bloated organization not occur, it likely will
be necessary to operate while conducting appropriate reviews even after starting operation.

(6)

Are education and training for the safe execution of the deuterium experiments andnurturing for those responsible for safety management being undertaken appropriately?

In addition to the lectures mandated by law, activities such as actually experiencing thehandling of tritium conducted through cooperation with the Toyama University Hydrogen
Isotope Research Center are highly evaluated. It is believed that training in communication ina time of emergency will be conducted and that cultivation of human resources for safely
executing the deuterium experiment are being appropriately planned.

[4] Understanding by Society and Citizens(1)

Is enhanced understanding of the safety of the deuterium experiment being advanced
appropriately to local residents?

In order to plan for enhancing understanding of safety, over nearly the past decade NIFS has
held open meetings for local residents. These open meetings have been held each year at from
20 to 30 places and more than 4,000 people have attended. NIFS has explained the deuterium
experiment and the results of research, and is advancing a shared understanding. And opinions
raised at explanatory meetings are made available on the NIFS homepage. We very highly
evaluate this. Further, NIFS is engaging in public relations such as through brochures and8leaflets, and is participating in science fairs and local events. In particular, in 2013 NIFS held a
Science Classroom and more than 1,000 people participated. That NIFS is actively engaged inthese efforts is highly evaluated.

(2)

Is promotion of the deuterium experiment plan being designed in conjunction with local
governments?

From around 1997, while continuing to consult with the nearby cities of Toki, Tajimi, andMizunami, NIFS has deepened their understanding of its research activities and position
regarding safety. And in 2013, NIFS concluded agreements with Gifu Prefecture and thesethree cities. Further, as joint activities with the Toki City Plasma Research Committee, we canevaluate extremely highly that NIFS is continuing local radiation measurements together withelementary and junior high school teachers.
We also highly evaluate the continuation of regular explanation meetings and research reportmeetings after the conclusion of the agreement. Further, training in information delivery
together with local communities and the establishment at NIFS of the Regional Coordination
Office, which is a system for coordination.

(3)

Is the importance of fusion research and its safety being widely disseminated in society?

An Open Campus is held each year at NIFS, and this is becoming a large event with from
2,000 to 4,000 people attending each time. Further, NIFS conducts outreach not only in thisarea but also in other areas, too. NIFS holds the Fusion Festa in Tokyo at the National
Museum of Emerging Science and Innovation. In 2014, more than 2,000 people attended, andthat this has become a large event where people can learn about fusion research can be highly
evaluated. In addition, the holding of academic lectures for local residents, the production of amail magazine and of mail news, and visitors to NIFS exceeding 4,000 people indicates that
NIFS is pouring strength into public relations activities. Moreover, through cooperation with
the SSH activities and cooperation with internships for junior high and high school students
NIFS is actively engaged in public relations toward youths who will support the next
generations. This can be highly evaluated.

2.2 Recommendations
In this evaluation we have listed our recommendations regarding the path forward based upon thediscussion of the Deuterium Experiment Implementation Plan.
9

(1)Regarding the improvement of confinement that will be accompanied by the deuterium
experiment as well as the maintenance of heating devices and diagnostics instruments, together
with the further deepening of discussion toward a concrete experiment plan formulation, andthrough enhancement of modeling we anticipate contributions toward a comprehensive
understanding of toroidal plasma. We anticipate further continuation and maintenance of thecountrywide research networks for neutron diagnostics, tritium recovery, and plasma-wallinteraction that have been formed through collaborative research toward the Deuterium
Experiment.

(2)

To start the Deuterium Experiment on schedule, and under the Division of Deuterium
Experiments Management we anticipate completion without delay of the preparation andmaintenance plan formulation as well as the maintenance of equipment, reinforcement offacilities, and establishment of a safety management system.

(3)

NIFS also summarizes fusion research performed at universities, and in safely achieving
success in the deuterium experiment, completion also is extremely important. In particular,
while respecting the law, respecting the opinions of local residents, and maintaining awell-balanced sense regarding the development of scholarship, one must respond withflexibility. Further, it is hoped that regarding actual safety management, NIFS will proceedsafety management in a polite and reliable manner by the overlap of appointment terms forsupervisors and by rotating their appointments.

(4)

That NIFS has over a long period of time explained matters to local residents and has
cooperated in communication activities with local governments can be highly evaluated. From
now, too, through results from safety management and continuous practice it is hoped that NIFS
will work toward receiving understanding and support of fusion.

10Chapter 3

In Closing

At the National Institute for Fusion Science, from the beginning of the second mid-term goals period
in 2010, in order to strengthen further the centrifugal power of NIFS as a Center of Excellence in theplasma - fusion field, NIFS composed research projects in the following three fields: the LHD
Project, the Numerical Simulation Reactor Research Project, and the Fusion Engineering Research
Project. Aiming toward realization of the fusion reactor, we started research planning toward
integrating these results. For this purpose, in 2010 NIFS undertook a revision of the research
structure within the Institute. All of the research education staff were set in one research division,and each researcher could freely choose to participate in one of the three projects. These are the
LHD Project, the Numerical Simulation Reactor Research Project, and the Fusion Engineering
Research Project, and their coordination was promoted. It is anticipated that expedient responses will
occur as occasions demand.

The NIFS Advisory Committee introduced external peer reviews for the LHD Project in 2011, for
the Numerical Simulation Reactor Research Project in 2012, and for the Fusion Engineering
Research Project in 2013. Then, in the fiscal year 2014 NIFS initiated an external peer review of theDeuterium Experiment Implementation Plan. The external peer review members include 10
Advisory Committee members from outside the Institute and four foreign researchers. The Experts
Committee is composed of the External Peer Review Committee and five specialists for the topics.
They have undertaken the evaluation.

At the First External Peer Review Committee and Experts Committee meetings held on September
12, 2014, there was discussion of how to proceed in conducting this year’s external evaluation. It
was decided that the committees would evaluate the following points.

[1] Research Planning(1) The appropriateness of the deuterium experiment’s goals; the implementation system for a
research plan that will achieve its goals and an implementation system for safety protection(2) Plans for raising the academic value(3) Joint use; joint research system[2] Deuterium Experiment Preparation System(1) Maintenance planning for equipment and facilities(2) The preparation system and facilities and equipment maintenance11[3] Safety Management Planning(1) Fundamental ways of thinking about safety management(2) Safety management equipment and facilities; planning regarding experiment equipment(3) Appropriate formulation of regulations(4) Appropriate formulation of manuals(5) Formulation of organization and system(6) Education and training as well as appropriate planning for the nurturing of the person in
charge for safety management[4] Understanding by Society and Citizens(1) Enhancing the understanding of the safety of the deuterium experiment among local
residents(2) Coordination with local governments(3) Informing society of the importance and the safety of fusion research

Subsequently, at the second External Peer Review Committee and Experts Committee meetings held
on November 29, 2014, members received a detailed point-by-point explanation of the evaluation’s
perspective and the points for evaluation from the person in charge at NIFS, and aquestion-and-answer session was held subsequently. Moreover, on January 29, 2015, the third
External Peer Review Committee and Experts Committee meetings were held. Including additional
discussions with NIFS, there also was a point-by-point discussion that followed the topics ofevaluation decided by the External Peer Review Committee, and a summation. When all of the texts
for the evaluation had been gathered, on February 24, 2015, the fourth meetings of the External Peer
Review Committee and the Experts Committee were held and the final report compiled.

A result of this external evaluation of the deuterium experiment plan is the conclusion that, regarding
all of the items above, nearly all of the items may be highly evaluated. In particular, regarding theenhancement of the understanding of safety and cooperation with local governing bodies, weevaluate this extremely highly. This may be called a result of the Institute’s continuous efforts. In the
future, we look forward to continuing activities. We can highly evaluate the ongoing compositionand preparation of appropriate regulations and manuals as well as the construction of organizations
and systems, but we anticipate further effort.

Furthermore, at the third External Peer Review Committee and Experts Committee meetings held on
January 29, 2015, there was further discussion regarding ways of thinking about safety management
12and the treatment of radioactivated materials. In addition to receiving explanations of the Institute’s
approaches to safety management, we received an explanation through additional materials
regarding negotiations with local governments and citizens. In addition, we received several days
later a report that summarized the fundamental way of thinking regarding the treatment ofradioactivated materials, too. As a result of discussions that referenced these explanations andmaterials, we have concluded that the fundamental way of thinking regarding safety management
and the treatment of radioactivated materials is appropriate.

Finally, we have summarized below recommendations regarding how to move forward from now
with the deuterium experiment implementation planning.

(1) Referencing improvement of confinement that is accompanied by the deuterium experimentand the preparation of both heating devices and diagnostic equipment, through deepening
further discussion of concrete experiment planning formulation together with enhancing
modeling we anticipate that this will contribute to a comprehensive understanding of toroidal
plasma. We anticipate further continuation and support of research networks throughout
Japan that focus on neutron diagnostics, tritium recovery, and plasma-wall interaction
constructed through joint research aimed at the deuterium experiment.

(2) To begin the deuterium experiment on schedule, and under the Division of Deuterium
Experiments Management, we anticipate completion without delay of the formulation of
preparation implementation planning, the preparation of equipment, the improvement offacilities, and the establishment of the safety management system, all of which are aimed at
the deuterium experiment.

(3) NIFS has the standing as an inter-university research institute that summarizes research infusion studies at universities, and succeeding safely in completing the deuterium experimentis extremely important. In particular, while respecting laws and regulations, respecting theopinions of local residents, and maintaining an awareness of a good balance of academic
development, it is important to respond flexibly. Further, regarding the actual safety
management, it is expected that the appointment period for supervisors will be overlapped
and that new supervisors will be appointed appropriately, and that this will proceed politely
and steadily.

(4) We can highly evaluate NIFS’ explanations for local residents and cooperation activities withlocal governing bodies over these many years. From now, through achieving safety13management and constant effort, it is hoped that this endeavor will gain understanding andsupport for fusion

14

Documents

2014 External Peer Review Presentation Materials

M２

The Deuterium Experiment
I l
Implementationt ti PlanPl

Yasuhiko Takeiri
National Institute for Fusion Science2014 NIFS External Review (Nagoya, November 29, 2014)

1/16

Large Helical Device (LHD) Projectx The world-largest helical system, and the world-largest SC fusion machine
x Intrinsic advantage and engineering capability of steady-state operationx Complementary/alternative role to tokamak approach

The goal of the Large Helical Device project
9 Establish scientific basement for a helical fusion reactor
H.Yamada䝥䝷䝈䝬ⱝᡭኟ䛾Ꮫᰯ
National
for Fusion
Science
9 InstituteComprehend
physicsof toroidal plasmas ᖹᡂ㻞㻞ᖺ㻤᭶㻝㻝᪥ භ⏥䝇䜹䜲䞂䜱䝷
2/16

１

Objectives of Large Helical Device Project- defined in the basic plot in 1989 To clarify the physics and engineering problems important for helicalfusion reactor plasmas by studying currentless plasmas in the next
large-scale fusion experimental device of the university program.
((1)) Realize p
plasma with a highg fusion triple
p productpand
conduct extensive confinement study requisite for afusion reactor.
(2) Realize beta exceeding 5 % and explore related
physics.
experimentand((3)) Employ
p y divertor, conduct longg pulsepp
accumulate basic data for steady state operation.
(4) Investigate high energy particles in helical fields andconduct simulation experiment of alpha particles in areactor plasma.
(5) Conduct complementary study to tokamak anddeepen comprehensive understanding of toroidal
Photo by J. Nishizawa
plasmas.
from “Build the Future”

3/16

LHD has worked very well for 16 years.
9 Operation for 16 yearsÎ engineering base of a large-scale superconducting andcryogenic system for fusion reactor development< LHD basic dimension >• Outer diameter
13.5 m• Cold mass
820 ton• Total weight1500 ton• Magnetic field
3T• Magnetic
Mti energy 0.77
0 77 GJ
Several-month-long operation,
17 times since 1998
• Operational time of He
compressor : 75,000 hours
Î Duty > 99 %• Coil excitation number: 1,545 times• Plasma discharges: 122,000 shots(Plasma generation every 3 min)Heating capability
NBI 28MW
ECH 4.6
4 6 MW
ICH
3.5 MWA large number of opportunities
for diversified collaboration on physics

4/16

Demonstration of steady-state-operation ofhigh-performance fusion plasma
LHD has shown steady andencouraging development ofplasma performance in these 16
years since the initial operation.
Power (NBI) (MW)
P

20

15
10

10

ECH

5

Elecctron tempe
erature
(keV)

ICH
0
20

0
10

15
Te

10

5
㼀㼕

5

Ion ttemperaturre(keV)

Two major keys to realize fusion energy
1. Control of burning plasmas
Î ITER
2. Steady-state operation
Î LHD and JT-60SA

NBI

Power (ECH,ICH) (MW
P
W)

30

0

0

1998 2000 2002 2004 2006 2008 2010 2012 2014

year

5/16

Achieved plasma parameters encourage
the further next step.
Plasmaparameters
Ion
temperature

Achieved

Target8 1 keV
8.1
k V

10 keVk V

at 1u1019m-3

at 2u1019m-3

Fusioncondition

20 keVElectrontemperature

at 2u1018m-3

10 keV

13.5 keVat 2u1019m-3> 10 keV> 1u1020m-3

at 1.4u1019m-3

Denisty

1.2u1021m-3

4u1020m-3

with Te of 0.25
0 25 keVwith Te of 1.3
1 3 keV5.1%
Beta

at 0.425 T

5%

3.7%

at 1-2 T> 5%
at > 5 T

at 1 T

54min. 28sec (500kW)
Steady-statepoperation(1keV䚸4u1018m-3)

1 hour47min. 30sec. ((1,200,
kW))䠄䠄3,000,
kW䠅䠅

Steady-state((1 yyear))(2keV䚸1u1019m-3)

Achieved in 2013

Innovative discovery to enable breakthrough Î acceleration of research
9 Steady
St d andd stablet bl highhi h bbetat d
due tto self-stabilization
lf t bili ti off iinstabilityt bilit9 Super-high density plasmas beyond 10 times the conventional fusion condition
9 Impurity hole to pump out impurity automatically, etc.
6/16

Objectives of the LHD deuterium experiment

1.To
1To realize highhigh-performance
performance plasmas by confinement
improvement and to provide a wide range of plasma
parameter space relevant to the reactor plasmas.
As a consequence, scientific research area will be expandedwith an increase in the variety of experiments.

2.To
2T studyt d theth mass ddependenced(i(isotopeteffect)ff t) ini ththeplasma confinement, leading to the establishment of amodel for the burning experiment using deuterium andtritium.
3.To demonstrate that the confinement capability ofhigh-energy ions is relevant to the burning plasmas inhelical systems.
7/16

Annual Plan for LHD Deuterium ExperimentFirst 6 years

Second 3 years

FY

1st year

2nd – 6th year

7th – 9th year

After
10th
year

Experiments

Preliminary Exp.
(C
(Commissioning)i i i )

Plasma Exp.
For Target
Parameters

Integrated HighP f
Performance
Exp.
E

PostLHD
Project

5.55x1010 Bq (1.5 Ci)(Integrated yield)---

Maximum
Annual Yield
of Tritium
Maximum
AnnualDischarge of
Tritium
Maximum
Annual Yieldof Neutron

3.7x1010 Bq (1 Ci)(Integrated yield)

3.7x103
7x109 Bq (0.1
(0 1 Ci) (Integrated yield)

2.1x102
1x1019(Integrated yield)

3.2x103
2x1019(Integrated yield)

---

---

LHD deuterium experimentpwill start after the supposedpp
3-yearsyppreparation.
p
Post-LHD project will be directed to researches for the basic plasma science and theplasma application as well as the reactor design, with hydrogen plasma experiments.
8/16

Device Upgrade Plan for the LHD Deuterium Experiment
Tritium Removal System

Monitor

M it
MonitorIntegrated Radiation
Monitoring System
Control
SystemMonitorUpgrade of
Diagnosticsg

RemoteControl
MonitorMonitorStack

ECH and ICH
UpgradeNBI UpgradeUpgrade of Vacuum
Pumping System
ᾛᾗᾓClosed Helical
Divertor

Access Control System

Neutron Diagnostics
System9/16

Schedule for LHD deuterium experiment (tentative)- ConcludingC
l di theth Agreements
A
t for
f the
th LHD deuteriumd t iexperimentit withith
local government bodies on March 28, 2013.
- Deuterium experiment will start in 2016, and during the planned 9years’ experiments, 10keV of the Ti should be achieved.
Target
FY2014FY2015FY2016 – FY2024
FY2013in
D-Exp.
Deuterium Experiments ((9 yyears))
Preparationpfor D-exp.
p (3( years)y)㻴㻙㻱㼤㼜㻚

㼁㼜㼓㼞㼍㼐㼑㻌㼒㼛㼞㻌㻴㼑㼍㼠㼕㼚㼓㻌㻿㼥㼟㼠㼑㼙㻔㻔㻺㻮㻵㻘㻌㻱㻯㻴㻘㻌㻵㻯㻾㻲㻕㻕㼁㼜㼓㼞㼍㼐㼑㻌㼒㼛㼞㻌㻰㼕㼍㼓㼚㼛㼟㼠㼕㼏㼟㻌㻿㼥㼟㼠㼑㼙㻔㻺㻔㻺㼑㼡㼠㼞㼛㼚㻌㼐㼕㼍㼓㼚㼛㼟㼠㼕㼏㼟㻘㻌㼑㼠㼏㻚㻕㼐㼕㼕㻕㻵㼚㼟㼠㼍㼘㼘㼍㼠㼕㼛㼚㻌㼛㼒㻌㻿㼍㼒㼑㼠㼥㻌㻱㼝㼡㼕㼜㼙㼑㼚㼠㼟㻔㻔㼀㼞㼕㼠㼕㼡㼙㻌㼞㼑㼙㼛㼢㼍㼘㻌㼟㼥㼟㼠㼑㼙㻘㻌㼑㼠㼏㻚㻕㻕㻾㼑㼙㼛㼐㼑㼘㼕㼚㼓㻌㼛㼒㻌㻮㼡㼕㼘㼐㼕㼚㼓㻌㼍㼚㼐㻌㻲㼍㼏㼕㼘㼕㼠㼕㼑㼟

Deuterium Experiments
PreliminaryExp
perimentsforCommissio
oning㻸㼑㼓㼍㼘㻌㻸㼕㼏㼑㼚㼟㼑

CalibraationExperimentsforN
NeutronDiaggnostics

Agreements
for D-exp.

㻴㻙㻱㼤㼜㻚

㻯㼘㼛㼟㼑㼐㻌㻴㼑㼘㼕㼏㼍㼘㻌㻰㼕㼢㼑㼞㼠㼛㼞㻌㼣㼕㼠㼔㻌㻯㼘㼛㼟㼑㼐
㻴㼑㼘㼕㼏㼍㼘 㻰㼕㼢㼑㼞㼠㼛㼞 㼣㼕㼠㼔㻼㼡㼙㼜㼕㼚㼓㻌㻿㼥㼟㼠㼑㼙㻺㻮㻵㻦㻌㻝㻤㻹㼃㻌㻔㻢㻜㻙㻤㻜㼗㼑㼂㻘㻌㻞㼟㼑㼏㻕㻝㻠㻹㼃㻌㻔㻝㻤㻜㼗㼑㼂㻘㻌㻞㼟㼑㼏㻕㻱㻯㻴㻦㻌㻢㻹㼃㻙㻟㼟㼑㼏㻘㻌㻝㻹㼃㻙㻯㼃㻔㻣㻣㻳㻴㼦㻌㻒㻌㻝㻡㻠㻳㻴㼦㻕㻵㻯㻾㻲㻦㻌㻢㻹㼃㻙㻡㼟㼑㼏㻘㻌㻞㻙㻟㻹㼃㻙㻯㼃㻺㼑㼡㼠㼞㼛㼚㻌㻰㼕㼍㼓㼚㼛㼟㼠㼕㼏㼟㻺㼑㼡㼠㼞㼛㼚
㻰㼕㼍㼓㼚㼛㼟㼠㼕㼏㼟㻴㼕㼓㼔㻙㻱㼚㼑㼞㼓㼥㻌㻼㼍㼞㼠㼕㼏㼘㼑㻌㻹㼑㼍㼟㼡㼞㼑㼙㼑㼚㼠㻟㻙㻰㼕㼙㼑㼚㼟㼕㼛㼚㼍㼘㻌㻹㼑㼍㼟㼡㼞㼑㼙㼑㼚㼠㻴㼕㼓㼔㻙㻭㼏㼏㼡㼞㼍㼏㼥㻌㻹㼑㼍㼟㼡㼞㼑㼙㼑㼚㼠㻰㼕㼢㼑㼞㼠㼛㼞 㻰㼕㼍㼓㼚㼛㼟㼠㼕㼏㼟㻿㼠㼑㼍㼐㼥㻙㻿㼠㼍㼠㼑㻌㻰㼍㼠㼍㻌㻭㼏㼝㼡㼕㼟㼕㼠㼕㼛㼚㻼㼃㻵㻌㻸㼍㼎㼛㼞㼍㼠㼛㼞㼥Ti = 10keV
at 2u1019 m-3
Wp = 3.8MJ
at 1u1020 m-3<ȕ> ~ 3%at T(0)~5keV
nTW~1.4u1020
m-3 keV s
3MW Heatingfor 1 hour
10/16

Towards Realization of Fusion Energy by Magnetic Confinement
2012

2022

2032

2042

Large Helical Device (NIFS) helical system
Maximizing performanceÎ Innovative & Basic Research2022

JT--60SA (JAEA) tokamak
JT
Construction

Operation Î demonstration of steadysteady-state2019

Irradiation test byintensive neutron source

ITER tokamak
Construction

Operation Î

2020
Choice of the first
DEMO ?

DEMO

demonstration ofburning plasma
2027

Engineering Design and R&D

2037

Operation

towards
practical
implemen-tationConstruction Îpower generation

Electric power output : 1GW

11/16

Issues of Evaluation (1)1 Research Plan
1.
(1) Is the goal of the deuterium experiment appropriate? Further, do
the research plan and the implementation system for ensuringsafety achieve those goals?
(2) Does this plan contribute to the promotion of a comprehensive
understanding of toroidal plasma and heighten its academic meritwith regard to the realization of fusion energy?
(3) Regarding implementation of the plan,
plan will this achieve a systemof collaborative use and collaborative research that enables
participation by a wide range of researchers?

Î Presentation by Y. Takeiri
12/16Issues of Evaluation (2)2. Deuterium Experiment Preparation System(1) Moving toward the initiation of deuterium experiments in Heisei
28 [2016], is the preparation of equipment and facilities being
planned appropriately?
(2) Is the preparation system for the initiation of deuterium
experiments appropriate? Is preparation of the facilities, including
safetyy equipment,q p, and machinery
y beingg advanced appropriately?
pp pyÎ Presentation by Y. Takeiri
13/16

Issues of Evaluation (3)3. Safety Management Planning(1) Is the fundamental concept regarding safety management appropriate at
th titime off thetheth formulationfl ti off theth deuteriumd t iexperimentit execution
ti planlas also based upon the opinions of local residents?
((2)) Are safetyy managementgequipment,q p, facilities,, and experimentpequipment
q pbeing planned appropriately for the safe accomplishment of thedeuterium experiment and to support management?
(3) In order to safely accomplish the deuterium experiment,
experiment are various
types of regulations being formulated appropriately?
((4)) Are the operationpmanual, the radiation managementgmanual, and theemergency measures manual being formulated appropriately?
(5) Are the organization and the system for safety management when the
deuterium experiments are being conducted being constructed
appropriately?
(6) Are education and training for the safe execution of the deuterium
experiments, and nurturing for those responsible for safety management
being undertaken appropriately?

Î Presentation by K. Nishimura 14/16

Issues of Evaluation (4)4. Understanding by Society and Citizens(1) Is enhanced understanding of the safety of the deuterium
experiment
i
tb
being
i advanceddd appropriately
i t l tto llocall residents?
id t ?
(2) Is promotion of the deuterium experiment plan being designed inconjunction with local governments?
(3) Is the importance of fusion research and its safety being widely
disseminated in society?
yÎ Presentation by Y. Takeiri
15/16

Note from the review ofthe safetyy managementgin 2009
Referencing the “recommendation”
recommendation regarding the safety
management plan at the time of the deuterium experiment in theexternal review of the safety management undertaken in 2009, thetwo points below,
below too
too, are to be considered in this evaluation
evaluation.
1) Has the cultivation and the education training of those
responsible
ibl att theth timeti
off theth deuteriumd t iexperimentit beenbconducted appropriately?
2) Are the organization of the safety committee for radiation
safety management, the safety observation committee, theradiation managementgoffice,, and others,, and the structure at
the time of an emergency being appropriately constructed?
Î Reflect to “3
3. safety management planning”
planning
16/16

M２

1. Research Plan

２(1) Is the goal of the deuterium experiment appropriate? Further, do
the research plan and the implementation system for ensuringsafety achieve those goals?
(2) Does this plan contribute to the promotion of a comprehensive
understanding of toroidal plasma and heighten its academic meritwith regard to the realization of fusion energy?
(3) Regarding implementation of the plan, will this achieve a systemof collaborative use and collaborative research that enables
participation by a wide range of researchers?

1/47

1. Research Plan
(1) Is the goal of the deuterium experiment appropriate? Further, do
the research plan and the implementation system for ensuringsafety achieve those goals?
(2) Does this plan contribute to the promotion of a comprehensive
understanding of toroidal plasma and heighten its academic meritwith regard to the realization of fusion energy?
(3) Regarding implementation of the plan, will this achieve a systemof collaborative use and collaborative research that enables
participation by a wide range of researchers?

2/47

Objectives of the LHD deuterium experiment1.To realize high-performance plasmas by confinement
improvement and to provide a wide range of plasma
parameter space relevant to the reactor plasmas.
As a consequence, scientific research area will be expandedwith an increase in the variety of experiments.

2. To study the mass dependence (isotope effect) in theplasma confinement, leading to the establishment of amodel for the burning experiment using deuterium andtritium.
3. To demonstrate that the confinement capability ofhigh-energy ions is relevant to the burning plasmas inhelical systems.
3/47

Improvement of the plasma confinement(Isotope effect) is clearly observed in deuterium
experiments in the world-major devices.
DeviceNationImprovement
factor in
D-exp

JFT-2MJapan

1.1䡚1.4

JT-60U

Japan

1.2䡚2

Alcator C

USA

1.5

DIII-D

USA

1.4䡚2

ISX-B

USA

1.4

TFTR

USA

1.2

ASDEX

Germany

1.3䡚2

ASDEX-U

Germany

1.5

TEXTOR

Germany

1.4

JET

UK

1.2䡚1.4

FTU

Italy

1.4

Isotope effect is a major issue to be
identified for the burning plasmas.
Comparison between deuterium andhydrogen plasmas (JT-60U)

4/47

Main subjects
in the LHD deuterium experiment (1)(a) Confinement improvement and related physics
Research on the isotope effect in the plasma confinement and therelated confinement improvement in the deuterium experiments,
toward systematic understanding of the toroidal plasmas.

(b) Improvement of MHD stability and expansion ofhigh-E regime
Research on the MHD equilibrium and stability in high-E regime ofcollisionless plasmas realized by the confinement improvement
and the increase in the heating power in the deuterium experiment.

(c) Confinement of high-energy ions
Research on the confinement of high-energy ions, such as ICRF
accelerated ions and 1-MeV triton with a high-accuracy diagnosticof neutrons (utilizing T+D --> n(14MeV)+D as the secondary
reaction of D+D --> T(1.0MeV)+p ).
5/47

Main subjects
in the LHD deuterium experiment (2)(d) Optimization of divertor
Research on the particle and heat control in the peripheral plasma
region with the closed helical divertor and improvement of thesteady state plasma performance.

(e) Plasma wall interaction (isotope effects)
Research on the isotope effects in the plasma wall interaction
including the fuel recycling, to understand the behavior in theburning plasmas.

(f) Expansion of experimental approaches
Ion heating experiments by the ICRF heating schemes of Hminority/D-majority and 3He-minority/D-majority.

6/47

Expected plasma parameters andthe resulted neutron and tritium yields
䞉Heating condition 㻌 㻌 NBI 32MW (perp.: 80keV-18MW, tang.: 180keV-14MW)
㻌㻌㻌
ICH+ECH 3MW
䞉Assumed energy conf. time㻌 2 times ISS95 (Achievement: x1.6) 䞉Magnetic field 3T

Absorbed power

12
10
8

20

Centraltemperature 6⵳✚࢚ࢿࣝࢠ࣮

10

4Storedenergyᗘ2002 10160
1 2 3 4 5 619
Averageddensiy (10m-3)⥺ᖹᆒᐦᗘ
P

Neutron yield rate
(1/s)
୰ᛶᏊⓎ⏕⋡
ಶ⛊㸧

30⥲྾཰ࣃ࣮࣡

Stored energy (MJ)
Central temperature (keV)40⵳✚࢚ࢿࣝࢠ࣮ 0୰ᚰ ᗘ NH9

Total
absorbed power0:(MW)⥲྾཰ࣃ࣮࣡

Î Ti(0) = 10keV at ne = 2u1019 m-3
Wp = 3.8MJ at ne = 1u1020 m-3 Î <β> ~3%, T(0)~5keV㻌 Î nTW ~ 1.4 u1020 m-3 keV s 㻌 㻌 㻌 㻌 㻌 㻌 㻌
Î if WE~3WEISS95 , Q~0.3
㻌Total⥲୰ᛶᏊ
neutron yield⥲୰ᛶᏊࣉࣛࢬ࣐࡛ࡢ཯ᛂ
ࣉࣛࢬ࣐࡛ࡢ཯ᛂ

TCT effect isdominant

1 1016
Neutron yield bythermal plasma

0
0

1

2

3

4

5

P19
 -3
⥺ᖹᆒᐦᗘ
(10
Averageddensiym )6

Maximum neutron and tritium yields
27.7 MW㻌 㻌 Line-averaged density 2.5u1019 m-3㻌 Total abs. heating power㻌 㻌 Central temperature
9.5 keV
Plasma stored energy
1.77 MJ
16㻌 㻌 Neutron yield rate
1.91u10 /s㻌 (yield rate by thermal plasma 5.98u1014 /s)
䞉Pulse length: 3sec Î Neutron yield: 5.7u1016, Tritium yield: 1.0u108 Bq 䠄2.7u10-3Ci䠅

7/47

Annual Plan for LHD Deuterium ExperimentFirst 6 years

Second 3 years

FY

1st year

2nd – 6th year

7th – 9th year

After
10th
year

Experiments

Preliminary Exp.
(Commissioning)

Plasma Exp.
For Target
Parameters

Integrated HighPerformance Exp.

PostLHD
Project

5.55x1010 Bq (1.5 Ci)(Integrated yield)---

Maximum
Annual Yield
of Tritium
Maximum
AnnualDischarge of
Tritium
Maximum
Annual Yieldof Neutron

3.7x1010 Bq (1 Ci)(Integrated yield)

3.7x109 Bq (0.1 Ci) (Integrated yield)

2.1x1019(Integrated yield)

3.2x1019(Integrated yield)

---

---

LHD deuterium experiment will start after the supposed 3-years preparation.

Post-LHD project will be directed to researches for the basic plasma science and theplasma application as well as the reactor design, with hydrogen plasma experiments.
8/47

Device Upgrade Plan for the LHD Deuterium Experiment
Tritium Removal System

MonitorMonitorMonitorIntegrated Radiation
Monitoring System
Control
SystemUpgrade of
Diagnostics

RemoteControl
MonitorMonitorStack

ECH and ICH
UpgradeNBI UpgradeUpgrade of Vacuum
Pumping System
ᾛᾗᾓᴾ
Closed Helical
Divertor

Access Control System

Neutron Diagnostics
System9/47

NBI upgrade plan for deuterium experimentLow-energy positive-NBIs: 2 (perp. inj.) 18MW
High-energy negative-NBIs: 3 (tang. inj.) 14MW
- NBI upgrade for raising the beam energy of positive-NBIs has been completed.

Positive-NBI
80keV-9MW

BL5
BL1

Negative-NBI
180keV-(4-5)MWNegative-NBI
180keV-(4-5)MW

BL2

BL3
Positive-NBI
60keV-9MW

Negative-NBI
180keV-(4-5)MW
BL4

10/47

ECH upgrade plan for deuterium experiment
77GHz/154GHz㻌㻌 6 systems
6MW/3sec, 1MW/cw- Three 77GHz- and two 154GHz-ECH systems, each of which injects >1MW fora short pulse and >300kW for CW, have been installed. (an 84GHz- and an
82.7GHz-ECH systems will not be available in the D-experiment.)- One 154GHz-ECH system is planned to be installed after the start of thedeuterium experiment.

11/47

ICH upgrade plan for deuterium experiment
3 sets with 6 antennas 6MW/5sec, 2䡚䡚3MW/cw- Each antenna injects >1MW for pulse and >0.5MW for CW.

4.5U/L FAIT antenna- 2 straps of HAS (HAsu-Seigyo) antenna
2 straps of FAIT (Field-Aligned Impedance-Transforming) antenna
2 straps of PA (Poloidal Array) antenna- Frequency will be fixed at 38.5 MHz.
- PA antennas will be removed before the deuterium experiment.

7.5U/L PA antenna

3.5U/L HAS antenna

ICRF antennas in 2014 experiment

12/47

LHD in-vessel components- Armor was installed to protect
vessel wall from the increased
NB power.

- Baffles to form closed helicaldivertor configuration have been
installed (9 modules completed).

Cryopumps arebeing installed
under the dome.

Tiles are made of tungsten or carbon
fiber composite materials.

13/47

Upgrade plan for diagnostics (1)Extension of confinement study for high-energy particles
Neutron䞉J-ray diagnostics
Fast-neutron
scintillation detector

Neutron flux monitor
based on 235U fission chamber

High-energy particle
diagnostics
LHD plasma

Neutron activation
systemEscaping fast-ion
diagnostics

Capsulefor activation foil

Scintillatorarray

LHD plasmaCollective Thomson
scattering diagnostics

High-pure
Ge detector

High-sensitivity
CCD camera

Gyrotron

Rail & trainsystemJ-ray camera

NeutroncameraReceiverGyroradius

252Cf neutron2sourceImage fibers

14/47

Upgrade plan for diagnostics (2)Enhancement of anomalous transport studyHighHi
h precisioni itransport
diagnostics system

T
Toward deeper understanding ofdivertor physics
Microwave
reflectometry
imaging

Upgrade of divertor, edge
plasma diagnostics
Divertor plate

Multichannel
ECE imaging

Coolingpipe

LHD plasma

Dome

Fast iongauge

YAG laserr
YA
High-energy
neutral beam

Beam emission
spectroscopy(BES) imaging

Bolometer

PolychromatorP
olychromator

Edge Thomson
scattering
diagnostics

Steady state, fast data acquisition andmanagement system
9 Fast DAQ for fluctuation measurements withhigh-time and space resolutions
9 Data analysis computing cluster for real-time
analysis and monitoringHigh radiation
resistance
fast network

9 Real-time operability for steady-state plasmameasurement and control

15/47

Schedule for LHD deuterium experiment (tentative)- Concluding the Agreements for the LHD deuterium experiment withlocal government bodies on March 28, 2013.
- Deuterium experiment will start in 2016, and during the planned 9years’ experiments, 10keV of the Ti should be achieved.
Target
FY2014FY2015FY2016 – FY2024
FY2013
Deuterium Experiments (9 years) in D-Exp.
Preparation for D-exp. (3 years)㻴㻙㻱㼤㼜㻚㻌

㼁㼜㼓㼞㼍㼐㼑㻌㼒㼛㼞㻌㻴㼑㼍㼠㼕㼚㼓㻌㻿㼥㼟㼠㼑㼙㻌㻔㻺㻮㻵㻘㻌㻱㻯㻴㻘㻌㻵㻯㻾㻲㻕㻌㼁㼜㼓㼞㼍㼐㼑㻌㼒㼛㼞㻌㻰㼕㼍㼓㼚㼛㼟㼠㼕㼏㼟㻌㻿㼥㼟㼠㼑㼙㻌㻔㻺㼑㼡㼠㼞㼛㼚㻌㼐㼕㼍㼓㼚㼛㼟㼠㼕㼏㼟㻘㻌㼑㼠㼏㻚㻕㻌㻵㼚㼟㼠㼍㼘㼘㼍㼠㼕㼛㼚㻌㼛㼒㻌㻿㼍㼒㼑㼠㼥㻌㻱㼝㼡㼕㼜㼙㼑㼚㼠㼟㻌㻔㼀㼞㼕㼠㼕㼡㼙㻌㼞㼑㼙㼛㼢㼍㼘㻌㼟㼥㼟㼠㼑㼙㻘㻌㼑㼠㼏㻚㻕㻌㻾㼑㼙㼛㼐㼑㼘㼕㼚㼓㻌㼛㼒㻌㻮㼡㼕㼘㼐㼕㼚㼓㻌㼍㼚㼐㻌㻲㼍㼏㼕㼘㼕㼠㼕㼑㼟㻌

Deuterium Experiments
Preliminary Experiments for Commissioning㻸㼑㼓㼍㼘㻌㻸㼕㼏㼑㼚㼟㼑㻌

Calibration Experiments for Neutron Diagnostics

Agreements
for D-exp.㻌

㻴㻙㻱㼤㼜㻚㻌

㻯㼘㼛㼟㼑㼐㻌㻴㼑㼘㼕㼏㼍㼘㻌㻰㼕㼢㼑㼞㼠㼛㼞㻌㼣㼕㼠㼔㻌㻼㼡㼙㼜㼕㼚㼓㻌㻿㼥㼟㼠㼑㼙㻌㻺㻮㻵㻦㻌㻝㻤㻹㼃㻌㻔㻢㻜㻙㻤㻜㼗㼑㼂㻘㻌㻞㼟㼑㼏㻕㻌㻌㻌㻌㻌㻌㻌㻌㻝㻠㻹㼃㻌㻔㻝㻤㻜㼗㼑㼂㻘㻌㻞㼟㼑㼏㻕㻌㻱㻯㻴㻦㻌㻢㻹㼃㻙㻟㼟㼑㼏㻘㻌㻝㻹㼃㻙㻯㼃㻌㻌㻌㻌㻌㻌㻌㻌㻌㻔㻣㻣㻳㻴㼦㻌㻒㻌㻝㻡㻠㻳㻴㼦㻕㻌㻵㻯㻾㻲㻦㻌㻢㻹㼃㻙㻡㼟㼑㼏㻘㻌㻞㻙㻟㻹㼃㻙㻯㼃㻌㻺㼑㼡㼠㼞㼛㼚㻌㻰㼕㼍㼓㼚㼛㼟㼠㼕㼏㼟㻌㻴㼕㼓㼔㻙㻱㼚㼑㼞㼓㼥㻌㻼㼍㼞㼠㼕㼏㼘㼑㻌㻹㼑㼍㼟㼡㼞㼑㼙㼑㼚㼠㻌㻟㻙㻰㼕㼙㼑㼚㼟㼕㼛㼚㼍㼘㻌㻹㼑㼍㼟㼡㼞㼑㼙㼑㼚㼠㻌㻴㼕㼓㼔㻙㻭㼏㼏㼡㼞㼍㼏㼥㻌㻹㼑㼍㼟㼡㼞㼑㼙㼑㼚㼠㻌㻰㼕㼢㼑㼞㼠㼛㼞㻌㻰㼕㼍㼓㼚㼛㼟㼠㼕㼏㼟㻌㻿㼠㼑㼍㼐㼥㻙㻿㼠㼍㼠㼑㻌㻰㼍㼠㼍㻌㻭㼏㼝㼡㼕㼟㼕㼠㼕㼛㼚㻌㻼㼃㻵㻌㻸㼍㼎㼛㼞㼍㼠㼛㼞㼥㻌Ti = 10keV
at 2u1019 m-3㻌
Wp = 3.8MJ
at 1u1020 m-3<β> ~ 3%at T(0)~5keV㻌

nTW~1.4u1020
m-3 keV s㻌
3MW Heatingfor 1 hour㻌
16/47

Research schedule plan for deuterium experiments
Preparation
2013

First 6 years

2014

2015

2016

Agreements for D-exp

Legal license

Inspection

Device upgrades
Safety installation

Preliminary
experiments

Second 3 years

2017

2018

2019

2020

2021

2022

2023

After
2024

Post LHD

Plasma flow and stability
High fusion products
Impurity control

Isotope effectIntegrated plasma research
Establishment of academic basis

Control of edge plasma
Super-dense plasma
Internal transport barrierHigh temperatrue

Extension of high-E
Stability of high-E plasma

Extension of parameter regime
Establishment of academic basis

Long pulse discharge

High-energy ion confinement

17/47

Implementation system for LHD deuterium experiment (1)LHD Experiment Board
chaired by Executive Director

LHD Operation GroupLHD Experiment GroupLHD Device Engineering Meeting

LHD Experiment Group Meetingx Technological examination of devices

x Preparation and planning ofexperimentx Arrangement and planning of
installation

x Report of experimental results
x Discussion of researches

Division director of health andsafety promotion- Watches and supervises thesafety of experiments

x Dry-run for presentation

Radiation Control Office- Checks the radiation safety of theexperiments

LHD team

18/47

Implementation system for LHD deuterium experiment (2)- LHD experiment board is responsible
for management of the LHD
experiment.
- Experiment plans are verified andfinalized by the board including thesafety management.
- Division director of health and safety
promotion watches and supervises
the safety for experiments as a board
member.
- Head of radiation control officechecks the radiation safety in theexperiments.
- Safety regulation and roles in theemergency are confirmed at themorning meeting before theexperiment.
19/47(1) Is the goal of the deuterium experiment appropriate? Further,do the research plan and the implementation system forensuring safety achieve those goals?
1. Deuterium experiment is expected to greatly extend the LHD plasma
parameter regime to the reactor-relevant regime, which should lead to thefirm design of a helical fusion reactor by establishment of an academicbasis for toroidal plasmas.
2. Main subjects in the LHD deuterium experiment should contribute toachievement of the goal of the deuterium experiment through theconfinement improvement due to the isotope effect, extension of high-E
regime, intensive research on enhanced high-energy ions, optimization ofdivertor, and research on the isotope effects in the peripheral region andthe plasma wall interaction, as well as expansion of ICRF heating schemes.

3. Machine upgrade is planned to maximize the heating capability in the
deuterium experiments, to improve the diagnostic accuracy for precise
physics research, and to install the closed helical divertors, and theresearch schedule is also planned along the main subjects.
4. LHD experiment board should conduct the deuterium experiment toachieve the goal, through well-organized research and safety management
system.

20/47

1. Research Plan
(1) Is the goal of the deuterium experiment appropriate? Further, do
the research plan and the implementation system for ensuringsafety achieve those goals?
(2) Does this plan contribute to the promotion of a comprehensive
understanding of toroidal plasma and heighten its academic meritwith regard to the realization of fusion energy?
(3) Regarding implementation of the plan, will this achieve a systemof collaborative use and collaborative research that enables
participation by a wide range of researchers?

21/47

High-Temperature Plasmas with ITB formation
High electron temperature plasmas with Electron ITB/CERC
Æ Upgrade of ECH power and fine control of deposition
Æ Transport improvement due to the bifurcation of Er
High ion temperature plasmas with ion ITB
Æ Wall conditioning enhances the transport improvement
Æ Impurity exhaust (Impurity Hole formation)
High temperature plasmas with comparable Ti and Te
Æ Integration of ion ITB and electron ITB
Æ Control of temperature profile

22/47

High-Temperature Regime in Deuterium Exp.
Neutral beam Injectors (NBIs) will be upgraded for deuterium beam injection, which havehigher ion heating efficiency
Positive NBI (40kV, 6MW, H0) + (40kV, 6MW, H0) Î (60kV, 9MW, D0) + (80kV, 9MW, D0)
Negative NBI (180kV, 5MW, H0) x 3 Î (180kV, ~3.5MW, D0) x 3
In LHD deuterium experiment, Ti0 = 10 keV will be achieved with deuterium beam
injection and further improvement of confinement due to the isotope effectTi0 [keV]

D-H exp.
10
D-D exp.
9
Wall cond.
8
2012-20137 New perp. NBI
2011
6
2010
5
~2009

4
3

1

2
3
4 5 6 7 8
Pi/ne [x10-19 MW m3]
23/47

Extension of High Beta Regime<EE> > 5 % is required for realization of economical helical fusion
reactor and was achieved in high collisional regime, whichclarify the following characteristics of MHD equilibrium andstability:- Activities of resistive interchange modes are mitigated incollisionless regime with high magnetic Reynolds number- Plasma is well confined in stochastic region
Confinement improvement in DD
experiments expects to- access to low-collisional highbeta regime, which enable us to
studies of equilibrium, stability
and transport in new regime.
- clarify collisionality dependenceof plasma confinement in thestochastic region
24/47

Subjects of MHD Studies
MHD studies are required for maintenance of stable plasma
The studies of the following subjects
are ongoing:- Beta limits due to equilibrium andstability- Change of magnetic topology- Equilibrium, stability and transport
in stochastic region- Response of 3D field to plasma- Non-linear growth of MHD
instabilities- H mode physics and ELM control

Further understanding of MHD physics
is expected through DD experiments
25/47

High-energy ions
Neutron profile based on FIT3D code

PlasmaNeutron Flux
Monitor (NFM)

Total neutron rate

Neutron counts [a.u.]

Torus hall

R [m]Neutron Profile
Monitor(NPM)••

Neutron profile

basement•

Neutron is mainly due to fast-ion-plasma reaction.
Neutron measurement expands the fast-ion study.
• NFM reveals global confinement of fast ion.
• NPM reveals radial profile of fast ion.
Further progress of study on fast-ion confinementchanging due to magnetic field configuration or
26/47
MHD instability will be promising.

Closed Helical Divertor
Particle and impurity control by divertor pumping
Æ Suppression of plasma cooling due to gas and removal of impurityÆ Improvement of plasma performance
Reduction of heat and particle load in divertor
Æ Achievement of high-power and long-pulse plasmaÆ Divertor design of helical reactor
Open Divertor

Closed Divertor

䞉 Closed helical divertor
with baffle structure
and pumping system
㻌 →Active particle
control in high-heating
power and long-pulse
discharge
䞉 Closed divertor in
inboard side

PlasmaGas

Plasma iscooledby gas.

PlasmaGas is not
returned
to plasma.

䞉 Step-by-step
installation of closed
divertor

Pumping

27/47

Divertor Studies
Strategy of edge plasma control: combination of
Closed Helical Divertor (CHD) and Stochastization with RMP

x Particle recycling is controlled with closed helical divertor (CHD) with pumpx RMP-controlled stochastic layer is utilized for radiative cooling and impurity shieldingx RMP-controlled stochastic layer is expected to enhance the divertor detachment
x Radiative cooling in stochastic layer mitigates heat load to divertor platesx Isotope effect and neutral particle transport including He should be investigated28/47

Plasma Wall Interaction
Heat transport
ዘDistribution of the heat loading
and its global balance towards
the FFHR-d1 is estimated in the
LHD D-D plasma with longpppulse operation.

Particle transport
Heat
transport

Heat
H

D-D Materialtransport
plasmaDeposition
ErosionዘQuantitative analysis of H
isotopes on the entire wall
surface is estimated by material
probe experiment. Then, thedata is applied to estimation of
the total T inventory in the large
fusion system.

Material transport
ዘErosion and deposition profileof the plasma facing
components on entire wall
surface in LHD is evaluated bymaterial probe experiment. 29/47

ParticlePa
articlle
Particletransport

Tritium Study~ tritium mass balance and safety handling technology ~• Application of tritium as a tracer– Study of tritium behavior in the large system• Tritium mass balance in LHD– Total amount of tritium by neutron measurement= Tritium inventory in/on the first wall and the diverter tile [PWI study]+ Tritium analysis in the vacuum exhaust gas• Tritium safety handling technology– Validation of the tritium decontamination factor in the large scale tritium removal
systemStudy of tritium behavior in the large system

30/47

Heating & Steady State (Ion Cyclotron Heating)Helium will be replaced by deuterium in ICRF heating
Minority ion heating (D(H) plasma)- Applicable to a variety of plasmas if deuterium is usually used
- Optimal minority ratio may differ from tokamak devices

Second harmonic heating of deuterium- Effective with high temperature and/or high energy deuterium ions
- Simultaneous heating with minority heating in D(H) plasma
Other heating and physics
experiment- D(He3) heating- Study about high energy ion
and fusion products generated
by ICRF heating

Deuterium

Steady state experiment- Comparison with deuterium
and helium plasmas- Effect of actual fuel in steadystate discharge on engineeringand operation and so on

Hydrogen

620kW

1150kW
Ohmic

620kW

1150kW

Comparison of charge-exchange spectra in D(H) plasma
31/47
of PLT tokamak

Research on Isotope Effect• Isotope effect is a long-standing mystery• The one of missions of LHD deuterium experiment
9 key to realize confinement improvement
9 Academic base for physics towards burning plasmas
Previous experiments in tokamaks and helical systems
have indicated the importance of low-recycling for
improved confinementÆ Hypothesis:
recycling control and its impact on core confinement(through core-edge coupling)Æ Increased understandings through integrated view
Core neutral density
profile (high dynamicrange Balmar α)
Bulk ion temperaturep(
profile(bulk
CXS))
Isotope density ratio(GAM spectroscopy)

ECE sight of vi
vview

Image
ma

• Non-local
phenomenon• Multi-scale
turbulence

Recycling
control• Impacts of ion mass on poloidal flow Æ Mp
• Residual zonal flow level : D >H

32/47

Isotope Effect from the viewpoint of impurity
Isotope effect should be also considered from impurity• JET: ITER like wall experiment (Maddison NF2014)• JT-60U Zeff is larger in D compared to H (T.Nakano)• Impacts of wall material on H mode (Itoh, Itoh, PPCF1995) and so on

Impact of impurity on ion heat confinement in LHD (Osakabe, PPCF2014)• 4 different-size C pellets into in high-Ti plasmas• Indicating the existence of threshold of C density for ion heat confinement
improvementÆ Isotope effect will be considered also from the viewpoint of impurity
33/47(2) Does this plan contribute to the promotion of acomprehensive understanding of toroidal plasma andheighten its academic merit with regard to the realization offusion energy?
1. NBI upgrade for the deuterium beam injection effectively enhances the ion heating
power, and should raise the ion temperature to Ti0 = 10 keV with confinement
improvement due to the isotope effect.
2. Confinement improvement in the deuterium experiments should extend high-E regime
to low-collisional regime extrapolated to a reactor plasma, and clarify collisionality
dependence of confinement in the stochastic region.

3. Precise measurement of neutrons should clarify the fast ion confinement and reveal
the fast-ion induced MHD instability foreseen in a reactor plasma.
4. Particle control with closed helical divertor and control of stochastic region with RMP
should lead to diverter optimization for a reactor.

5. Deuterium experiments greatly expand the PWI study with regard to the heattransport, the particle transport, and the material transport, contributing to the reactor
design.
6. Deuterium experiments expand the heating scenario with ICH, leading to highperformance of long-pulse discharges, which extend the reactor relevant PWI study.
7. Research on the isotope effect contributes to establishment of academic basis forcomprehensive understanding of toroidal plasmas.

34/47

1. Research Plan
(1) Is the goal of the deuterium experiment appropriate? Further, do
the research plan and the implementation system for ensuringsafety achieve those goals?
(2) Does this plan contribute to the promotion of a comprehensive
understanding of toroidal plasma and heighten its academic meritwith regard to the realization of fusion energy?
(3) Regarding implementation of the plan, will this achieve a systemof collaborative use and collaborative research that enables
participation by a wide range of researchers?

35/47

Research plan has been discussed by a wide rangeof researchers through collaboration.

- Research plan for the LHD deuterium experiment has been discussed
and proposed in workshops organized in frameworks of the NIFS
collaboration system. Eight workshops have been held, and various kindsof subjects have been discussed, such as device development, divertor
study, PWI study, isotope effect, fast ion confinement, tritium study, andenvironmental radiation.
- Also, in academic meetings of the fusion community, such as meetings
held by the Fusion Network and symposiums held in annual conferenceof The Japan Society of Plasma Science and Nuclear Fusion Research,
the research plan related with the deuterium experiment has been
proposed and discussed by a wide range of researchers.
- Through these discussions among the fusion community, the researchplan for the LHD deuterium experiment has been established.

36/47

Workshops with collaborators toward
deuterium experiment from 2010 to 2014
- Eight workshops have been held at NIFS to discuss on the
deuterium experiment plan and the tritium safety.

37/47

Symposiums on deuterium experiment planin academic meetings- Deuterium experiment plan has been discussed with collaborators in
symposiums of academic meetings.
- It has been also discussed in a question and answer time of plenary talk andinvited talk.

38/47

All Japan fusion neutron diagnostics development teamhas been organized toward the LHD deuterium project.
Nagoya Univ./Dr. H. Tomita, Prof.T. Iguchi• Neutron spectrometerte• Nuclear
clear emulsionemu

Nagoya Univ./Prof. A. Uritani‫؞‬NFM designn- MCNP modelingeling

Hokkaido Univ./
Dr. J.H. Kaneko• Triton burnup/NPA- CVD diamond
Kinki University/
Dr. H. Yamanishima• Reactor UTR-KINK
KII
UTR-KINKI
Kyoto University/y//Prof. T. Misawa• Reactor KUCA

FNS collaboration
EA/
T. Nishitani,
ITER JAEA/Drs.
MFC K. Ochiai, M. Ishikawa, andK. Shinohara
M. Isobe, K. Ogawa• FNS
Neutron camera on JT-60U• Neutron• ITER
Micro FC
IT
T
TER

NIFS

JT-60U collaboration
Kyoto U
Univ.//
Dr. S. Murakami‫؞‬Fast-ion modelingd‫؞‬Prediction of fusion output

Fission reactor collaboration

National
N
Institute of Technol.,Toyama College/gProf. E. Takadad• Neutron camera detector

NIFS-Univ. collaboration

JAEA collaboration
39/47

Collaboration with Nagoya University~ Joint work for neutron flux monitor development ~Test operation of wide dynamic
range DSP unit prototype at KUCA

Neutron transport study by MCNPThe LHD is fairly complicated.
→ A program generating an input file of 3D
machine geometry for MCNP has been developed.

KUCA is flexible in changing
thermal neutron flux

FC for NIFS
Thermal neutron flux
up to 107 nv in the reactor core
An example of test
operation at KUCA

KUCA UIC output

NIFS 235FC output

A satisfactory prospect
was obtained toward
manufacture of NFMDSP unit for LHD

Time (s)N. Nishio et al., Rev. Sci. Instrum. 81(2010) 10D306.

40/47

Research on environmental tritium
Collaborations with Kyushu Univ., Kumamoto Univ., JAEA, etc• Tritium behavior in ground water at the NIFS site
– To understand the background tritium level at the NIFS site and the tritium
behavior released from the facility to the environment, two component
separation analysis was carried out.
– The tritium concentrations in rain was 0.09-0.78 Bq/L, and the tritium
concentrations of stream water and ground water were almost constant,
0.34 Bq/L and 0.25 Bq/L, respectively.
– The two component separation analysis gave good agreement between
isotopic ratio and conductivity.

Sampling locations at NIFS toki site (R-10, R-15: stream
water, G-B, G-F, G-G, and G-J: groundwater, Rain: rainwater)

Two component separation of flow rate using G18O,
conductivity and tritium concentration at the rain
event. The black bar represents the ground watercomponent and the slash bar is the rain component.

41/47

S. Sugihara, et al., Fusion Science and Technology 60 (2011) 1300-1303

Research on polymer membrane
Collaboration with Nagoya Univ.

• Simulation model of hollow fiber polymer membrane– A simulation model was developed for transient response of a hollow
fiber membrane for the tritium removal system.
– The mass transfer processes such as sorption and desorption, diffusivetransfer of gases are treated in the model.
– This model represents well not only separation factors and recovery ratioat the steady state but also responses to the multi-step wise change inthe sweep gas rate.

Water vapor separation model with the hollow fiber membrane
module.
T. Sugiyama, et al., Fusion Engineering and Design 86 (2011) 2743–2746

Transient response to the multi step-wisedecrease in the reflux flow rate

42/47

Desorption of deuterium from after exposed W+
Cu irradiation+ LHD-H plasma exposure
LHD-H plasma exposure
Cu+ irradiation

3.0

ዘPost D+ ion irradiation was
carried out to the various kindsof W samples.
ዘTrapping sites are changed oneach desorption stage
1.2

Desorption rate / 1017 D2 m-2 s-1

Desorption rate / 1018 D2 m-2 s-1

Shizuoka Univ.

Pure W

Stage C 1.0
Stage A
2.0

0.8

Stage B

0.6

¾ Dislocations㻿㼠㼍㼓㼑㻌㻮㻌
¾ W-O¾ Point defects by irradiation

0.4

1.0

0.2
0.0

㻿㼠㼍㼓㼑㻌㻭㻌

400

600

800

1000

0.0

1200

㻿㼠㼍㼓㼑㻌㻯㻌
¾ Void¾ Carbon deposition layer

Tempareture / K

TDS spectrum of D from various kind of the W samples

43/47

Characterization of surface morphologies of first wall
Kyushu Univ.
ዘCharacterization of the surface morphologies were clarified by
microstructural observation.
ዘFormation of the microscopic defects such as dislocation loops and helium
bubbles were formed on the subsurface region. Impurity deposition was
also observed on the top surface.
ዘThese surface morphologies can act as the strong trapping site of thehydrogen isotopes.
Cross-sectional TEM images of stainless first wall sample
after exposed to single LHD campaign
Top surface Dark Field Image

㻝㻜

㻌

㻞㻜

㻰㼑㼜㼠㼔㻌㻔㼚㼙㻕

Bright Field Image

Depth profile of He
calculated by TRIM
㻜code㻌㻝㼗㼑㼂㻙㻴㼑
㻌㻞㼗㼑㼂㻙㻴㼑
㻌㻟㼗㼑㼂㻙㻴㼑

㻟㻜

㻠㻜

20 nm

㻜

㻝㻜

㻞㻜

㻟㻜

㻠㻜

㻵㼛㼚㼟㻌㻔㼍㼞㼎㻚㻕

㻡㻜

㻢㻜

㻣㻜

㻡㻜
㻤㻜

44/47

LHD deuterium experiment project promotes research
activities in universities through the collaboration.
- Number of NIFS collaboration related with the deuterium experiment iscounted to around 40 every year.

45/47

Statistics of published papers- Through the NIFS collaboration, number of papers have been
published related with the deuterium experiment project.

46/47

(3) Regarding implementation of the plan, will this achieve asystem of collaborative use and collaborative research thatenables participation by a wide range of researchers?
1. Research plan for the LHD deuterium experiment has been discussed andproposed by a wide range of researchers through the collaboration.
2. Toward the LHD deuterium experiment, all Japan fusion neutron diagnostics
development team has been organized based on collaborative research.
3. Tritium-related studies important for the deuterium experiment, such as
research on the environmental tritium and technology development for thetritium removal system, have been conducted in collaborative researcheswith universities.
4. PWI studies, such as the retention properties of hydrogen isotopes and thecharacterization of surface morphologies of the first wall, have been
accelerated toward the LHD deuterium experiment, leading toestablishment of a wide range of collaboration network.
5. Selected subjects related with the deuterium experiments are counted toaround 40 every year in the NIFS collaboration system, and 47 papers havebeen published.
47/47

M２

2. Deuterium Experiment
Preparationp
Systemy(1) Moving toward the initiation of deuterium experiments in Heisei
28 [2016], is the preparation of equipment and facilities being
planned appropriately?
(2) Is the preparation system for the initiation of deuterium
experiments appropriate? Is preparation of the facilities, including
safety equipment, and machinery being advanced appropriately?

1/24

2. Deuterium Experiment
Preparationp
Systemy(1) Moving toward the initiation of deuterium experiments in Heisei
28 [2016], is the preparation of equipment and facilities being
planned appropriately?
(2) Is the preparation system for the initiation of deuterium
experiments appropriate? Is preparation of the facilities, including
safety equipment, and machinery being advanced appropriately?

2/24

３

Device Upgrade Plan for the LHD Deuterium Experiment
Tritium Removal System

Monitor

M it
MonitorIntegrated Radiation
Monitoring System
Control
SystemMonitorUpgrade of
Diagnosticsg

RemoteControl

ECH and ICH
UpgradeMonitorMonitorStack

NBI UpgradeUpgrade of Vacuum
Pumping System
ᾛᾗᾓClosed Helical
Divertor

Neutron Diagnostics
SystemAccess Control System

3/24

Preparation plan of equipment and facilities forsafetyy for the start of deuterium experimentp
H25(2013)

H26(2014)

H27(2015)

H28(2016)

Radiation Controlled Area

LHD
Experiments

H-exp

H-exp
䠄H-exp䠅 Start of D
D-exp
exp

SafetyM
Managementt
System䠄LHD Application䠅

䠄Approval䠅

Neutron and RI radiation monitoring systems
Integrated radiation monitoring system
Access control systemyTritium removal system(Test)

Filling wall holes, Remote control
Neutron shielding of devices
Remodeling of building and facilitiesy Experim
mentsPreliminary

Equipment for
Building andFacilities

䠄Check䠅pment in H-exp.
H
Test of Equip
situ Calibbration of NFM
In-s

Installation of
SafetyEquipment

Conclusion of Agree
ement

Legal
Licenses䠄Inspection䠅

Legal regulation, Manuals, Training

4/24

Preparation schedule of machine upgrade
for the start of deuterium experimentp

LHD Experiments

UpgradeU
d fforHeating System

Conclusion of AgreemenCnt

Installation of
Closed Divertor

Upgrade for
Diagnostics System

H25(2013)

H26(2014)

H-exp

H-exp

H27
(2015)

H28(2016)

䠄H-exp䠅 D-exp(Upgrade)

Installation (Step by Step)

NBI䠄BL4䠅 Upgrade

NBI system modification andadjustment
djforf D-injection
Di j iECH Gyrotron 䠄154GHz䠅

ECH Gyrotron 䠄154GHz䠅

ICH Antenna

ICH Antenna
A t&O
Oscillator
ill t

Neutron diagnostics, High precision & 3D diagnostics
Neutron shielding, Remote control,
C tCategorizing
i idiagnostics
diti forf necessityit(Removal of unnecessary devices)

5/24

Upgrade of NBI for deuterium experiments
Positive-NBI
H:40-50keV/6MW
э D:80keV/9MW

Negative-NBI
180keV/5MW

Negative-NBI
180keV/4.5MW

Negative-NBIg180keV/4.5MW

Positive-NBI
40keV-6MW
э D:60keV/9MW

Neutron Diagnostics
Fusion reaction producing neutrons in deuterium plasmas :d + d ĺ n (2.5 MeV) + 3He (0.82 MeV)ĺ p (3.0(MeV)) + t ((1.0 MeV))
Secondary reaction : d + t ĺ n (14 MeV) + D (3.5 MeV)
DD neutron rate expected in LHD is >1016n/s,
comparable to JT
JT-60U,
60U TFTR,
TFTR and JET.
JET

235U fission chamber satisfies

1. Wide dynamic range-> Pulse counting mode
+ Campbelling mode
2. Fast time response (~1 ms)
3. Good n-J discrimination capability
4. Long-termLong term high reliability

Role of neutron diagnostics
1 M
1.
Measurementt off ffusioni
output,t twhich estimates amount of tritium
2. Study on beam-ion behavior• Global confinement property andslowing down of beam ions
• Radial profile of beam ions
ĺBeam
B
d
depositioniiĺEffect of Alfvénic modes on radialtransport of beam ions
3. Confinement study of MeV tritons
isotropic in velocity space

7/24

Tritium Removal System
Two types of tritium recovery system are installed.
- Molecular sieve type for exhausted gas in the vacuum pumping- Polyimide membrane type for purged gas in the maintenanceStack
Recover Absorber

Exhausted Gas
i vacuum pumping
in
i

C d
Condense

HeaterNit
NitrogenAbsorber

Purged Gas
in maintenance

Catalyst(Pt or Pd)

Absorber

Catalyst(Pt or Pd)

Membrane
Separator((PolyimidyTube))

Hydrogen Gas
ĺ Water (HTO)

Absorb and Recover
Water (HTO)

Recovering Rate: >95 %

Air

8/24

(1) Moving toward the initiation of deuterium experiments in
Heisei 28 [2016], is the preparation of equipment and facilities
being planned appropriately?
?
1 Aft
1.
After theth conclusionl i off theth Agreement
A
t for
f the
th LHD deuteriumd t iexperimentit withith
local government bodies on March 28, 2013, the preparation schedule for themachine upgrade, the installation of safety equipment, and the equipment forbuilding and facilities was defined, including the establishment of safety
management system, toward the start of the deuterium experiment in 2016.
2. NBI systems has been upgraded for the deuterium beam injection with a highpriority to enhance the ion heating power in the deuterium experimentexperiment.
3. Neutron flux monitor system development has firstly been started as the mostimportant diagnostics for the deuterium experiment, and as a primary safety
equipment the tritium removal system has been designed and constructedequipment,
constructed.
4. Neutron shielding is designed for individual devices, and devices are listed, whichshould be removed due to weakness against neutrons and less necessity.
5. Building and facilities have been remodeled for the radiation controlled area.
6. Legal license procedure and preparation of various kinds of operation and safety
manuals are scheduled.
scheduled
9/24

2. Deuterium Experiment
Preparationp
Systemy(1) Moving toward the initiation of deuterium experiments in Heisei
28 [2016], is the preparation of equipment and facilities being
planned appropriately?
(2) Is the preparation system for the initiation of deuterium
experiments appropriate? Is preparation of the facilities, including
safety equipment, and machinery being advanced appropriately?

10/24

Preparation system for the
initiation of the LHD
deuterium experiment- Division for deuterium experiments
management is responsible for the
preparation for the LHD deuterium
experiment.
- D-exp management division mainly
consists of division directors of NIFS
including the safety-related divisions,which enables fast decision and topdown implementation.
- Under the D-exp managementgdivision, LHD upgrade team carries
out the design and construction for
individual items including the safety
management, according to theplanned preparation schedule for the
initiation of the deuterium experiment.
Preparation items executedby LHD upgrade team

11/24

Preparation items and schedule for the
initiation of the LHD deuterium experimentp
Conducted by LHD upgrade teamyTritium removal system

H25(2013)

H26(2014)

H27(2015)

H28(2016)

Neutron diagnostic system
Integrated radiation monitoring system
He gas tank
Filling holes
Neutron shielding & Remote control
G puffingGas
ffi
systemt
Vacuum pumping & Gas exhaust system
Cooling water system
D i modification
Devicedifi tiagainsti t radiation
di ti
Device removal
Plasma monitoring camera system
Access control room
Water-proof coating
Air circulating system
Electric facilities
Coating and painting
Reinforcement against earthquake

12/24

Strategy to select removed and/or reformed devices
which are weak against radiation
Step 1: Check list submission for existing devices in the LHD torus hall andbasement- Status
St t off existingi ti devices
d i
and
d th
their
i robustnessb tagainsti t radiationdi ti werechecked.
- Diagnostics and/or control systems which are obviously weak against
radiation were picked up
up, and were decided to be removed
removed.
- Done in October, 2013.
Step 2: Manual preparation for operation and radiation safety- Manuals for operation and radiation safety were prepared for each device
and maintenance work.
prepared.
- Device has to be removed if manual is not prepared- Done in May, 2014.
p 3: Implementationpplanpsubmission
Step- Suitability and feasibility of the plan were checked.
- Done in June, 2014.

All devices are now being classified into three groups according to
the implementation plan, for the judgement of removal or reformation.

13/24

Removal of devices that are weak against radiationis ongoing
List of devices that were and will be removed
An example :according to stages classified based on the check list X-ray PHA based on Si detector

Before

After
14/24

Reduce the neutron/gamma-ray streaming䞉 Effective dose outside the controlled area < 1.3mSv/3weeks
per yyear. -> effective dose < 0.6ȝSv/shotȝ䞉 We will have ~2,100 shots p
䞉 Some holes made for diagnostic/controlling at the basement levelshould be filled to satisfy the effective-dose limit.
䞉 Now,Nfilli
filling hholes
l att ththe northernthside
id was completed.
l t d
䞉 This work will be finished before the start of the deuterium experiment.
Example of shielding

Effective dose at the basement levelby calculation (after shielding)Effective dose (ȝSv/shot)䞉Northern side :0.13
䞉Eastern side :0.29
䞉Southern side :0.16
䞉Western side :
0.06
15/24

Filling holes of northern wall in basement
Filling holes of the floor between the heating equipment
room and the trench with polyethylene beads

N

Trench forheatingequipment
2m-thick wall
Basement

Filling holes of the wall between the basement andthe trench with polyethylene plates and beads

16/24

Removed/reformed devices which are
weak against radiation
䞉 Last year, all systems equipped with LHD were classified into threegroups based on the check list: “remove”,
remove , “reform”,
reform , and “satisfy”.
satisfy .
䞉 Devices classified into “remove” are now antecedently removed.
䞉 Implementation planning sheet is submitted and defined this year.
䞉 Removing/reforming devices will be done according to the planningsheet.
PHA diagnostics

After removing PHA diagnostics

17/24

Exhaust gas processing system~ Tritium removal systems ~• Exhaust gas processing system– Two types of tritium removal system• Molecular Sieves [MS] type and Permeable Membrane [PM] type

• Schedule of construction and commissioning– Completion:
Completion PFD
PFD, P&ID
P&ID, design of components and lalayouto t– Next step: Control system design, construction and commissioning
2014
4

5

6

7

8

2015
9

10

11

12

1

2

3

4

5

6

7

2016
8

9

10

11

12

1

2

3

PFD
P&ID
Drawing
S t
Systemddesigni
Construction
Commissioning
Operation

18/24

Absolute calibration of neutron flux monitor
using 252Cf neutron source
Train system
LHD Vacuum vessel

Track

Neutron Flux
MonitorPower lines

Pumping system

Power supply& controller• To measure the total number of neutron,
th neutronthet
fl monitor
flux
it systemtneedsdto be absolutely calibrated.
• Calibration will be carried out along the
guide
id lineli ddecidedid d iin th
the WS on th
theneutron calibration*.
• To avoid rescue circumstance of thesource, the train and track systemshould be reliable.
• We have developed a train that can run
continuously at least for three days.
• Test installation of the track inside thevacuum vessel has already been
performed twice to measure the timenecessary to install, and to find points at
issue for the installation.
*J.D. Strachan et al., Rev. Sci. Instrum. 61 (1990) 3501.

19/24

Refurbishment of LHD Building
Maintenance room

Air conditioning machine room
Exhaust treatment room

Main hall (1F)
Access control room
Material research lab.
1st Floor

1st Floor of basement
Controlled area is enclosed by red lines.
<Major items of refurbishments>

Storeroom
Main hall(B2F)

2nd Floor of basement(1) Preparation of rooms in LHD building,such as access control room,, material
research labs., and maintenance room.
(2) Maintenance of air conditioning machine(3) Installation of an emergency power
generator of 100 kW providing for 10
days
20/24

Air Balance of LHD BuildingH

74,300 m3/h

C

ACu-7

12,550
m3/h

500

0
500

H C
C C

ACu-6

Main hall (1F)

CAV-8

LHD

0

500
0

8,200 Exhaust treatment
room (B1F)
TR

Green house

300

Maintenance room

1,500
300
Tritium Removal
equipment
CAV: Constant Air
Volume
VAV: Variable Air
Volume
FD: Fire Damper
SFD: Smoke and Fire
Damper

FD
CAV-3

VAV

Stack

74,800Main hall (B2F)

TR:

400
SFD 300

550
400
FD

100

FD

CAV-1

Monitoring room
Water cooling room (1)CAV-7

Water cooling room (2)Device maintenance room
Storeroom for sources

SFD

Storeroom (1)Storeroom (2)FDPumping room

21/24

Application Procedure for the Licenses
Apparatusetc.

Act

Definition

Fission Chamber(U-235)

Act on the Regulation of
Nuclear Source Material,
Nuclear Fuel Material andReactors(The Reactor Regulation Act)

Nuclear Fuel Material(enriched Uranium)

Cf-252 sealed source Act on Concerning Prevention(800MBq)
from Radiation Hazards due toRadioisotopes,
ad o sotopes, etc.
etc
(Radiation Hazard Prevention
Act)

Radio-isotope(sealed source)

LHD

Given above

Radiation Generatingg
Device(Plasma Generator)

Material for the firstwall and the plasma
irradiation

Given above

Radio-isotope(unsealed source)

Some licenses have to be obtained before starting the LHD deuterium experiment.
22/24

Schedule for obtaining the Licenses
FY

2014

2013

2012

2015

2016

Experiment
A
Agreementt fforenvironmental safety(Mar.)

It
Item

(1) Fission Chamber

Application

Set the controlarea(Dec.)

Approval
Order

DeliverySet in the LHD hallCalibration(2) Cf-252

Application

Approval
DeliveryOrder(3) LHD & unsealed
radioactive materials

Hearing

Application
Approval

Facilitiesiinspectionti&First Plasma

H iHearing(4) Accounting Provision

Application
Approval(5) Change of the
Ministerial OrdinanceNotification

LHD deuterium experiment will start after the facilities inspection preparation.

23/24(2) Is the preparation system for the initiation of deuterium
experiments appropriate? Is preparation of the facilities,
including safety equipment, and machinery being advanced
appropriately?
1 Division for deuterium experiments management was established1.
established, which is responsible for the
preparation for the initiation of deuterium experiments, and conducts and accelerates the
preparation of the facilities and the establishment of the safety management.
2. LHD upgrade team for the deuterium experiment has carried out the design and constructionof the safety equipment and the device upgrade required for the deuterium experiments.
3. Along the planned schedule, the device upgrade and the preparation of the safety equipment
including the establishment of the safety management have progressed under the organizedpreparation system.
4. Filling holes of walls for reduction of the neutron streaming has been completed to 80%.
Devices which are weak against the radiation are classified for the judgement of removing/reforming
f
i b
based
d on ththe submitted
b itt d iimplementationlt ti plan,
l
and
d th
the removall hhas partly
tl started.
t t d
5. Tritium removal systems and the neutron diagnostic system as the safety equipment are now
under construction, and the preparation for the absolute calibration of neutron flux monitor has
successfully progressed
progressed.
6. Refurbishment of the LHD building for setting the radiation controlled area has been
completed, and the related facilities, such as the exhausted water and the air conditioning
system,y
are under construction.
7. Procedure for the legal licenses proceeds without any problem, and the required licenses
should be obtained before the start of LHD deuterium experiments.

24/24

M２

[3]Safetymanagementplanning
Points of Evaluation 3.
(3Ͳ1)Isthefundamentalconceptregardingsafetymanagementappropriateatthetimeof
p g
g
y
g
pp p
theformulationofthedeuteriumexperimentexecutionplanasalsobasedupontheopinionsoflocalresidents?
㔜Ỉ⣲ᐇ㦂䛾┠ⓗ䛿㐺ษ䛛䚸䜎䛯䛭䛾┠ⓗ䜢㐩ᡂ䛩䜛◊✲ィ⏬ཬ䜃Ᏻ඲䜢☜ಖ䛩䜛ᐇ᪋యไ䛸䛺䛳䛶䛔䜛䛛䚹(3Ͳ2)Aresafetymanagementequipment,facilities,andexperimentequipmentbeingplannedappropriatelyforthesafeaccomplishmentofthedeuteriumexperimentand
tosupportmanagement?
Ᏻ඲⟶⌮ᶵჾ䞉タഛ䚸ᐇ㦂ᶵჾ➼䛿㔜Ỉ⣲ᐇ㦂䜢Ᏻ඲䛻㐙⾜䛧䚸⥔ᣢ⟶⌮䛩䜛䛯䜑䛻㐺ษ䛻ィ⏬䛥䜜䛶䛔䜛䛛䚹(3Ͳ3)Inordertosafelyaccomplishthedeuteriumexperiment,arevarioustypesof
g
g
pp p
y
regulationsbeingformulatedappropriately?
㔜Ỉ⣲ᐇ㦂䜢Ᏻ඲䛻㐙⾜䛩䜛䛯䜑䛻䚸つ๎㢮䛿㐺ษ䛻⟇ᐃ䛥䜜䛶䛔䜛䛛䚹(3Ͳ4)Aretheoperationmanual,theradiationmanagementmanual,andtheemergency
manual being formulated appropriately?
manualbeingformulatedappropriately?
㐠㌿䝬䝙䝳䜰䝹䚸ᨺᑕ⥺⟶⌮䝬䝙䝳䜰䝹䚸⥭ᛴ᫬䝬䝙䝳䜰䝹➼䛿㐺ษ䛻⟇ᐃ䛥䜜䛶䛔䜛䛛䚹(3Ͳ5)Aretheorganizationandthesystemforsafetymanagementwhenthedeuterium
experiments are being conducted being constructed appropriately?
experimentsarebeingconductedbeingconstructedappropriately?
㔜Ỉ⣲ᐇ㦂䜢ᐇ᪋䛩䜛㝿䛾Ᏻ඲⟶⌮䛾䛯䜑䛾⤌⧊䚸యไ➼䜢㐺ษ䛻ᵓ⠏䛧䛶䛔䜛䛛䚹(3Ͳ6)Areeducationandtrainingforthesafeexecutionofthedeuteriumexperiments,and
nurturing for those responsible for safety management being undertaken
nurturingforthoseresponsibleforsafetymanagementbeingundertaken
appropriately?
㔜Ỉ⣲ᐇ㦂䛾Ᏻ඲䛺㐙⾜䛻ྥ䛡䛯ᩍ⫱䞉カ⦎ཬ䜃Ᏻ඲⟶⌮㈐௵⪅䛾㣴ᡂ䛿㐺ษ䛻ィ⏬䛥䜜 䛶䛔䜛䛛䚹

1/91(3Ͳ1)IsthefundamentalconceptregardingsafetymanagementappropriateatthetimePoints of Evaluation 3.
oftheformulationofthedeuteriumexperimentexecutionplanasalsobaseduponthe opinions of local residents?
theopinionsoflocalresidents?
㔜Ỉ⣲ᐇ㦂䛾┠ⓗ䛿㐺ษ䛛䚸䜎䛯䛭䛾┠ⓗ䜢㐩ᡂ䛩䜛◊✲ィ⏬ཬ䜃Ᏻ඲䜢☜ಖ䛩䜛ᐇ᪋యไ䛸䛺䛳䛶䛔䜛䛛䚹(3Ͳ2)Aresafetymanagementequipment,facilities,andexperimentequipmentbeingplanned appropriately for the safe accomplishment of the deuterium experiment andplannedappropriatelyforthesafeaccomplishmentofthedeuteriumexperimentand
tosupportmanagement?
Ᏻ඲⟶⌮ᶵჾ䞉タഛ䚸ᐇ㦂ᶵჾ➼䛿㔜Ỉ⣲ᐇ㦂䜢Ᏻ඲䛻㐙⾜䛧䚸⥔ᣢ⟶⌮䛩䜛䛯䜑䛻㐺ษ䛻ィ⏬䛥䜜䛶䛔䜛䛛䚹(3Ͳ3)Inordertosafelyaccomplishthedeuteriumexperiment,arevarioustypesof
(3
3) I
d t
f l
li h th d t i
i
t
i
t
f
regulationsbeingformulatedappropriately?
㔜Ỉ⣲ᐇ㦂䜢Ᏻ඲䛻㐙⾜䛩䜛䛯䜑䛻䚸つ๎㢮䛿㐺ษ䛻⟇ᐃ䛥䜜䛶䛔䜛䛛䚹((3Ͳ4)Aretheoperationmanual,theradiationmanagementmanual,andtheemergency
)
h
i
l h
di i
l d h
manualbeingformulatedappropriately?
㐠㌿䝬䝙䝳䜰䝹䚸ᨺᑕ⥺⟶⌮䝬䝙䝳䜰䝹䚸⥭ᛴ᫬䝬䝙䝳䜰䝹➼䛿㐺ษ䛻⟇ᐃ䛥䜜䛶䛔䜛䛛䚹(3Ͳ5)Aretheorganizationandthesystemforsafetymanagementwhenthedeuterium
experimentsarebeingconductedbeingconstructedappropriately?
㔜Ỉ⣲ᐇ㦂䜢ᐇ᪋䛩䜛㝿䛾Ᏻ඲⟶⌮䛾䛯䜑䛾⤌⧊䚸యไ➼䜢㐺ษ䛻ᵓ⠏䛧䛶䛔䜛䛛䚹(3Ͳ6)Areeducationandtrainingforthesafeexecutionofthedeuteriumexperiments,and
nurturingforthoseresponsibleforsafetymanagementbeingundertaken
appropriately?
㔜Ỉ⣲ᐇ㦂䛾Ᏻ඲䛺㐙⾜䛻ྥ䛡䛯ᩍ⫱䞉カ⦎ཬ䜃Ᏻ඲⟶⌮㈐௵⪅䛾㣴ᡂ䛿㐺ษ䛻ィ⏬䛥䜜 䛶䛔䜛䛛䚹

2/91

４

Fundamental Concept for Safety management
Deuterium
Experiment

LHD
PlasmaGeneratingg
DeviceNeutronNt
Tritium
Radio-active Materials

Regulation for Safety Management
䚽Act Concerning Prevention from Radiation Hazards due top , etc. ((Legalg Level))radioisotopes,
䚽Final report of the Deuterium Experiment Security Evaluation
Committee (NIFS management Level)
䚽Arbitration proposal by the Environmental Dispute Coordination
Commission(in deference)
3/91

Basic Concept
䚽Minimize quantity of occurring tritium.
э Examination of the experiment parameter
䚽Limit the quantity of tritium remaining in a VV which does notexceed a management level, even if a gross quantity is released.
pplanpэ Examination of the experiment䚽Keep the management level of the radiological generations whichhave a possibility to give influence on the environment.
э PreparationPti off exhaust,
ht drainage,d iththe ventilation
til ti equipmentit䚽Pay attention severely about a leak of the tritium component water.
э Preparation of a safekeeping method
method, safekeeping facilities

theSafetyManagementPlanEvaluationCommittee
Management of low level radiation
э Develop and establish the measurement technique andis useful for the Fusion Reactor in Future

4/91

(3Ͳ1)Isthefundamentalconceptregardingsafetymanagement
appropriateatthetimeoftheformulationofthedeuterium
experimentexecutionplanasalsobasedupontheopinionsof
i
t
ti
l
l b d
th
i i
f
localresidents?
Thebasicconceptforthesafetymanagement,suchastheNIFSmanagementlevelbeen
setsevererthanlawsandordinances,isconsideredtobeexcessiveasthestandardfor
generalfacilitytreatingwithradiation.However,thiswasbasedonanArbitration
proposalbytheEnvironmentalDisputeCoordinationCommissionandonalocalopinion.
lb h E il Di
C di i Ci i
dl l i i
Furthermore,fromtheSafetyManagementPlanEvaluationCommittee,“TheNIFS
managementvalueissufficientlylowcomparewiththatoflawsandordinances,but
research of a such small amount radiation promotes the development of its measurement
researchofasuchsmallamountradiationpromotesthedevelopmentofitsmeasurement
equipmentandaresearchtoestablishitsmeasurementtechnique.”isevaluatedtobe
appropriate.

5/91(3Ͳ1)Isthefundamentalconceptregardingsafetymanagementappropriateatthetimeof
Points of Evaluation 3.
theformulationofthedeuteriumexperimentexecutionplanasalsobasedupontheopinions of local residents?
opinionsoflocalresidents?
㔜Ỉ⣲ᐇ㦂䛾┠ⓗ䛿㐺ษ䛛䚸䜎䛯䛭䛾┠ⓗ䜢㐩ᡂ䛩䜛◊✲ィ⏬ཬ䜃Ᏻ඲䜢☜ಖ䛩䜛ᐇ᪋యไ䛸䛺䛳䛶䛔䜛䛛䚹(3Ͳ2)Aresafetymanagementequipment,facilities,andexperimentequipmentbeingplanned appropriately for the safe accomplishment of the deuterium experimentplannedappropriatelyforthesafeaccomplishmentofthedeuteriumexperiment
andtosupportmanagement?
Ᏻ඲⟶⌮ᶵჾ䞉タഛ䚸ᐇ㦂ᶵჾ➼䛿㔜Ỉ⣲ᐇ㦂䜢Ᏻ඲䛻㐙⾜䛧䚸⥔ᣢ⟶⌮䛩䜛䛯䜑䛻㐺ษ䛻ィ⏬䛥䜜䛶䛔䜛䛛䚹(3Ͳ3)Inordertosafelyaccomplishthedeuteriumexperiment,arevarioustypesof
(3
3) I
d t
f l
li h th d t i
i
t
i
t
f
regulationsbeingformulatedappropriately?
㔜Ỉ⣲ᐇ㦂䜢Ᏻ඲䛻㐙⾜䛩䜛䛯䜑䛻䚸つ๎㢮䛿㐺ษ䛻⟇ᐃ䛥䜜䛶䛔䜛䛛䚹((3Ͳ4)Aretheoperationmanual,theradiationmanagementmanual,andtheemergency
)
h
i
l h
di i
l d h
manualbeingformulatedappropriately?
㐠㌿䝬䝙䝳䜰䝹䚸ᨺᑕ⥺⟶⌮䝬䝙䝳䜰䝹䚸⥭ᛴ᫬䝬䝙䝳䜰䝹➼䛿㐺ษ䛻⟇ᐃ䛥䜜䛶䛔䜛䛛䚹(3Ͳ5)Aretheorganizationandthesystemforsafetymanagementwhenthedeuterium
experimentsarebeingconductedbeingconstructedappropriately?
㔜Ỉ⣲ᐇ㦂䜢ᐇ᪋䛩䜛㝿䛾Ᏻ඲⟶⌮䛾䛯䜑䛾⤌⧊䚸యไ➼䜢㐺ษ䛻ᵓ⠏䛧䛶䛔䜛䛛䚹(3Ͳ6)Areeducationandtrainingforthesafeexecutionofthedeuteriumexperiments,and
nurturingforthoseresponsibleforsafetymanagementbeingundertaken
appropriately?
㔜Ỉ⣲ᐇ㦂䛾Ᏻ඲䛺㐙⾜䛻ྥ䛡䛯ᩍ⫱䞉カ⦎ཬ䜃Ᏻ඲⟶⌮㈐௵⪅䛾㣴ᡂ䛿㐺ษ䛻ィ⏬䛥䜜 䛶䛔䜛䛛䚹

6/91

(3Ͳ1)IsthefundamentalconceptregardingsafetymanagementappropriateatthetimePoints of Evaluation 3.
oftheformulationofthedeuteriumexperimentexecutionplanasalsobaseduponthe opinions of local residents?
theopinionsoflocalresidents?
㔜Ỉ⣲ᐇ㦂䛾┠ⓗ䛿㐺ษ䛛䚸䜎䛯䛭䛾┠ⓗ䜢㐩ᡂ䛩䜛◊✲ィ⏬ཬ䜃Ᏻ඲䜢☜ಖ䛩䜛ᐇ᪋యไ䛸䛺䛳䛶䛔䜛䛛䚹(3Ͳ2)Aresafetymanagementequipment,facilities,andexperimentequipmentbeingplanned appropriately for the safe accomplishment of the deuterium experimentplannedappropriatelyforthesafeaccomplishmentofthedeuteriumexperiment
andtosupportmanagement?
Ᏻ඲⟶⌮ᶵჾ䞉タഛ䚸ᐇ㦂ᶵჾ➼䛿㔜Ỉ⣲ᐇ㦂䜢Ᏻ඲䛻㐙⾜䛧䚸⥔ᣢ⟶⌮䛩䜛䛯䜑䛻㐺ษ䛻ィ⏬䛥䜜䛶䛔䜛䛛䚹(3Ͳ3)Inordertosafelyaccomplishthedeuteriumexperiment,arevarioustypesof
(3
3) I
d t
f l
li h th d t i
i
t
i
t
f
regulationsbeingformulatedappropriately?
㔜Ỉ⣲ᐇ㦂䜢Ᏻ඲䛻㐙⾜䛩䜛䛯䜑䛻䚸つ๎㢮䛿㐺ษ䛻⟇ᐃ䛥䜜䛶䛔䜛䛛䚹((3Ͳ4)Aretheoperationmanual,theradiationmanagementmanual,andtheemergency
)
h
i
l h
di i
l d h
manualbeingformulatedappropriately?
㐠㌿䝬䝙䝳䜰䝹䚸ᨺᑕ⥺⟶⌮䝬䝙䝳䜰䝹䚸⥭ᛴ᫬䝬䝙䝳䜰䝹➼䛿㐺ษ䛻⟇ᐃ䛥䜜䛶䛔䜛䛛䚹(3Ͳ5)Aretheorganizationandthesystemforsafetymanagementwhenthedeuterium
experimentsarebeingconductedbeingconstructedappropriately?
㔜Ỉ⣲ᐇ㦂䜢ᐇ᪋䛩䜛㝿䛾Ᏻ඲⟶⌮䛾䛯䜑䛾⤌⧊䚸యไ➼䜢㐺ษ䛻ᵓ⠏䛧䛶䛔䜛䛛䚹(3Ͳ6)Areeducationandtrainingforthesafeexecutionofthedeuteriumexperiments,and
nurturingforthoseresponsibleforsafetymanagementbeingundertaken
appropriately?
㔜Ỉ⣲ᐇ㦂䛾Ᏻ඲䛺㐙⾜䛻ྥ䛡䛯ᩍ⫱䞉カ⦎ཬ䜃Ᏻ඲⟶⌮㈐௵⪅䛾㣴ᡂ䛿㐺ษ䛻ィ⏬䛥䜜䛶䛔䜛䛛䚹

7/91

Neutron and tritium measure and control
50%

T+p

50%

3He + nD+D

NumberofTritium=NumberofNeutronbf

To manage these safely, it is necessary to grasp quantity of theneutron production precisely

The fission chamber detectors are used to grasp
quantity of neutron precisely.
(See 㼲2.3.3.1䠅
1. N, J-ray protection
2. Provision for tritium (One of the most important issue)
3. Management of Exhaust, drain water, RI and RA-waste
RA waste
4. Radiation Controlled Area & Security
5. Integrated Radiation Monitoring System

8/91

1. Neutron and Ȗ-ray Protection
Reduction of radio-activation by neutron••

one of the importantsafety issue

Concrete under the LHD
machine will be strongly radioactivated.
To reduce the radio-activation of
concrete, we have a plan tocover the concrete with 5 cm
thick borated polyethylene (PE).
This year
year, covering
concrete on one-torus
section with PE was done.

•

We will finish covering concreteat the other torus sections
b f
beforestarting
t ti deuteriumd t iexperiment.

Covering concrete on onet
torus
sectionti
byb Polyethylene
P l th lblocks
9/91

2. Provision for tritium- Exhaust gas processing system -• Specificationsoftritiumremovalsystems

Environmental monitoring– Typeoftritiumremovalsystem:
• Oxidationcatalyst+absorbent[MStype]• Oxidationcatalyst+polymermembrane[PMtype]– Maximumflowrate:
• MStype:20Nm3/h• PMtype:300Nm3/h

– Detritiationfactor[DF][ ] :>20
Detritiation factor > 20
Tritium removal systems
MS type
PM type
Large Helical Device(LHD)
Maximum tritium p
production:
55.5 GBq/y

Stack

Tritium active
samplerl
Dilution by room air((24610 m3/h))

Tritium removal system
Oxidation catalyst Ļ Recovery of HTO
Chemical form of tritium
HTO

Collection anddelivery to JRIA
10/91

- MS type tritium removal system 䖃

Environmental
monitoring

Features of system– Catalysts: Pt-Al2O3 for hydrogen,
Pd Al2O3 for
Pd-Al
f hydrocarbons
h db3– Low throughput [< 20 m /h]– High tritium concentration– Operation: period of plasma exp.

RegenerationgsystemyCold trap

Addition of
air or oxygen

Oxidation
reactor(Pt /Pd)

NBI, Pellet
injection,
Plasma diagnostics
system, etc

Tritiated hydrogen andhydrocarbons
ĻCConversion
to tritiatedwater vapor [HTO]Heater

N2 gasStack

Absorbent(Zeolite)
Absorbent(Zeolite)
Dilution by air

RecoveryRof HTO

Tritium decontamination factor: > 20
(Tritium recovery rate : > 95 %)11/91- PM type tritium removal system Environmental
monitoringz Features of systemz Catalyst: Pt-Al2O3 for HT

z Application of polymer membrane => Merits of membrane:• No regeneration systemz High throughput [< 300 m3/h]
z Low tritium concentrationz Operation: period of maintenanceRoom air(300 Nm3/h)

Oxidation
reactor(Pt)
Tritiated hydrogen [HT]ĻConversion to tritiatedwater vapor [HTO]• High throughput• Continuous operation• Compact system• Control of performance• Ease maintenanceStackmembrane(polyimide)
Dilution by air
Recoveryof HTO

Maintenance invacuum vessel
Tritium decontamination factor: > 20
(Tritium recovery rate : > 95 %)12/91

3. Management of Exhaust, drain water, RI and RA-waste 1[Exhaust and Ventilation]
䚽 Since Ar in air is activated during Deuterium Experiment, we have tominimize the ventilation of the main experiment hall keeping negative
pressure.
pressure䚽 To keep the concentration of Ar-41 below the limit in law, we vent air
with 500Nm3/h.
/h䚽 A ventilation systems of ACU-6 and ACU-14 have ability to keep thepressure ini th
the maini hhallll andd th
the maintenancei tworkroomknegative.
ti䚽 Radio-active dusts are removed by the pre-filter and hepa-filter before
exhausting.

13/91- Air ventilation system of the LHD building Environmental
monitoring

LHD hall
500Nm3/h
Basement

500Nm3/h
Filters

Fresh
Air
500Nm3/h

Stack
14/91

3. Management of Exhaust, drain water, RI and RA-waste 2[Drain water and Recovered water]䚽 All ddrainageith t occurred
that
d in
i Controlled
C t ll d A
Area exceptt theth recoveredd watert
is kept in a retention tank temporarily and discharged after confirmation
the radio-activity concentration below NIFS management level (tritium :0.6 Bq/cm3). (Legal level : 60 Bq/cm3)
3) is treated䚽 Drainage
g that exceeds NIFS managementglevel ((0.6 Bq/cmq
as same as recovered water described below.

䚽 Recovered water
water, which produces by the tritium removal system andcontains the triated water (HTO), is contained in an exclusive
safekeeping container and asks Japan Radio-Isotope Association (JRIA)
for taking care of
of.

15/91

- Drainage Facility-

16/91

- Storage of Recovered Water Waterproof
g section
storage5,6RXUFH
6WRUDJH$UHD'LVSRVDOE\6WRUDJH)DFLOLW\

Plasticbag
MetalContainer((50L))
PlasticContainer(25L)

Lentby
Lent
by
JRIA

17/91

3. Management of Exhaust, drain water, RI and RA-waste 3[Radio-Active Waste]
Radio-Active wastes are classified into 8 categories as follows and put inthe metal-container(50L) of the JRIA designation. These are kept at one
time in a Disposal –by-Storage Facility and are asked JRIA for processing.
processing1) combustibles (type1)
2) incombustibles
3) incompressible incombustibles4) combustibles
combustibles* (type2)5) filters6) IonIon-exchange
exchange resin (consultation required)7) inorganic substances
8) organic substances
18/91

1) combustibles (type1)
䞉 flammable waste such as work gloves, the mask, a paper towel,
cloth Wes, etc.
2) incombustibles
䞉 a glass vial, glassware vinyl chloride, silicon, china, aluminum foil,
Teflon fit, etc.
3) incompressiblei
ibl incombustibles
ib tibl䞉 the soil, a steel frame, a pipe, a concrete piece, a casting, etc.
4) combustibles* (type2)
䞉 plastic, a poly-vial, a poly-seat, rubber gloves, Styrofoam, etc.
5) filterp
to arrange
g to exhaust facilities
䞉 Pre-filter, hepa-filter6) ion-exchange resin (consultation required)䞉 Ion-exchange resin such as primary cooling facilities
7) inorganic substances䞉 Be in 25L of poly-container, and it is held by 50L of metal-container
8) organic substances䞉 With liquid scintillation waste fluid
fluid, etc.
etc
Be in 25L of poly-container, and it is held by 50L of metal-container
19/91[Radioisotope](1) The radioisotope which is used as a radiation detector and for thecalibration
Enriched U
U-235
235 (fission chamber) 䠖 Neutron measurement
Cf-252 䠖 Source for calibration of the neutron measurement(2) The materials which are activated by a neutron or absorb Radioisotope
SUS sample, carbon sample, silicon sample : used for PWI studies
䚽 Main radionuclide
Graphite : T
T, C
C-14,
14 Be-7
Be 7
SUS316 䠖 T, C-14, Cr-51, Mn-53, Mn-54, Fe-55, Fe-59, Co-56,
Co-57, Co-58, Co-60, Ni-59, Ni-63, Zr-95, Nb-95m,
Nb-94 Nb-95,
Nb-94,
Nb-95 Nb-93m
Nb-93m, Mo-93
Mo-93, Tc-99

These materials are controlled in the Storage Facility.
20/91

4. Controlled Area & Security- Controlled Area 1st floor

1st basement

2nd floor

2nd basement

Controlled Area in the LHD Building for the Deuterium Experiments 21/91

Access Control- Gates and Security Code (SQRC) Access Gates and SQRC (Security QR Code)for authentication
SQRC seal are affixedon personal dosimeters.
Then, no one can enter
the controlled area
without personal
dosimeter.
Access gates
SQRC reader

Personal dosimeterwith SQRC

Access control room and rocker room

22/91

- Exit Flow and Contamination Test Apparatus Contamination monitor
From
LHD hallAccess gatesfor LHD hall
Access gatessurvey meter
hand-foot-clothing monitors 㽢3

Access Control room

From basement

Contamination
inspection room

LHD deuterium experiment will start after the supposed 3-years preparation.
3H/14C survey meter
Expiration
inspection device
23/91

5. Integrated Radiation Monitoring Systemexhaustht gas monitor
itgas and dust monitor
ITVdrainage monitor

exhaust gas
processing system
Monitors in thevacuum vesselContamination monitor
Accessccess gatesunification
environmentaleo e tamonitors䐟interlock䐠integrated radiation
monitoring system

LHD centralt l control
t lControl room䐡 Enhancement of monitoring system of LHD building

24/91

Example of Monitoring Displays
DRAINAGE CONTROL SYSTEMSTACK and LHD HALL GASMONITORRMSAFE (SITE BOUNDARY)RMSAFE(LHD HALL)

25/91

Measuring Instruments (1)Measuring equipment
䞉 prepared and started operations to get BG data

Stack gas monitors

Drainage tanks

3H sampler for stack gas

Drainage monitor

Low background Liquid
scintillation counters(LSC-LB7)

Ultra Low Level Liquid
Scintillation Spectrometer(1220 QUANTULUS)

Auto Well Gamma System(AccuFLEX 7000) 26/91

Measuring Instruments (2)Air monitors for the LHD hall
Monitoring post of RMSAFE

Survey meters

hand-foot-clothing monitors

27/91

RenovatedLHDBuildingtoapplyDͲexperiments
1F

Exhaust Gas
Processing
SystemB2F

Access Control
Area

RI Analysis
Area

RI storage
Area

B1F

28/91

Environmental Radiation Monitoring

Dose rate [mGy/yyear]

1.5
1
2
3
BG

1

0.5

0
04/4

05/4

06/4

07/4

08/4

09/4

10/4

11/4

12/4

13/4

14/4

11/4

12/4

13/4

14/4

Year / Month

Dose rate [mGy/year]

1.5
4
5
6
7
8
BG

1

0.5

0
04/4

05/4

06/4

07/4

08/4

09/4

10/4

Year / Month

Cumulative dose were monitored by glass dosimeter installed in the site(1) andd siteit bboundaryd(2-8).
(2 8)
Data shows the flat background dose.

29/91

Environmental Radiation Monitoring- Background of Radioactivity -Environmental
backgroundoff radioactivity
di
ti it

It is need to estimate theinfluence of the deuterium
experimentsitFollowing environmental background is being measured.
measured䚽 Radioactivity in the Stack Gas
䚽 Atmospheric tritium
Three chemical type of tritium was measured separately
water vapor (HTO), molecular hydrogen (HT) and hydrocarbons (CH3T)
䚽 Tritium in the river water (HTO)
Recent date is under 0.5 Bq/L.
䚽 Tritium in plant samples (FWT and OBT)
Pine needles at NIFS and Shiomi-park
䚽 Environmental radionuclides
rain, atmospheric dust, atmospheric deposition and surface soil
30/91

- Examples of Background of Radioactivity Data

7ULWLLXPFRQFHQWUD
DWLRQ
%T/

Tritium concentration in
the river water








                        '$7(

FWT: Free Water Tritium
OBT: Organically Bound Tritium

1.5
NIFS-FWT-1

Concentra
ation (Bq L )Tritium concentration in
the plant

NIFS-OBT
Shiomi-FWT

1.0

Shiomi-OBT

0.5

0.0
1996

2001

2006
Fiscal year

2011

31/91

Background of Radioactivity- Radioactivity in the Stack Gas Radioactivity in the stack gas is measured as background data in order toestimate the influence of the deuterium experiments
experiments.
32/91

1EͲ03

Radioactiveconcentrationinthestackgas:2012.6䡚2014.9
NIFS management level2㽢10Ͳ4Bq/cm3(Three month average)

1EͲ04
1EͲ05
1E
05
1EͲ06
1EͲ07
1EͲ08
1EͲ09
1EͲ10
4/1/2012

9/30/2012
4/1/2013
NIFS◊✲ᡤ⟶⌮್
managementlevel

9/30/2013
HTO
HT

4/1/2014
CH3T

9/30/2014
Total
ྜィ

32/91

- Tritium monitoring in the atmosphere 50
HTO

Absolute humidity

20

40

15

30

10

20

5

10

0
0
2004/1 2005/1 2006/1 2007/1 2008/1 2009/1 2010/1 2011/1 2012/1 2013/1
Y /Year/monthth3

Tritiumm concentration [[mBq/m ]

15
HT
CH3T

10

Absolute humidity [g
g/m3]

(b)

3

Tritium concentration [mmBq/m ]

25

9 Atmospheric tritium
concentrations of three chemical
forms such as HTO, HT and
CH3T had been measured since
2004.
9 Tritium concentrations of HTO,
HT and CH3T were distributed
aroundd 2-23
2 23 mBq/m
B / 3,
3
5-11 mBq/m and 0.5-3 mBq/m3.
9 The HTO concentration depends
on humidity in air
air.
9 Recent decreasing rate of HTconcentration to half wasestimated 19.4 years.

50
2004/1 2005/1 2006/1 2007/1 2008/1 2009/1 2010/1 2011/1 2012/1 2013/1
Year/monthAtmospheric tritium was separately collected as water vapor (HTO), molecular hydrogen(HT) and hydrocarbons (CH3T) by using this sampling system.
33/91- Tritium monitoring in the river water -7ULWLXPPFRQFHQQWUDWLRQ
%T/










                        '$7(

TritiumT
iticoncentrationt ti isi graduallyd ll decreasingdi year byb year.
Recent date is under 0.5 Bq/L.
This result is similar to background tritium concentration in Japan.

34/91

- Tritium monitoring in plant samples -

1.5
-1

Co
oncentrration (BBq L )

NIFS-FWT
NIFS-OBT
Shiomi-FWT

10
1.0

Shiomi-OBT

0.5
FWT: Free Water Tritium
OBT: Organically Bound Tritium

0.0
1996

2001

2006
Fiscal year

2011

We monitoredWitd tritium
t iti
concentrationt ti ini pinei needle
dl samples.
lShiomi park is located about 5km south of NIFS.
35/91
FWT and OBT concentrations are gradually decreasing, and recent data is background level.

- Environmental monitoring of radionuclides Rain sampler

Air sampler

Atmospheric deposition
sampler

Surface soil sampling

Passive type sampler(atmospheric water vapor)

In order to understand the background level of radionuclides, westated the rain, atmospheric dust, atmospheric deposition andsurface soil collection.
We also started the passive type sampling of HTO in atmosphericwater vapor.
vapor A passive type sampler which does not require any
power supply is more effective for the study on atmospheric HTO
behavior around the LHD.

36/91

(3Ͳ2)Aresafetymanagementequipment,facilities,and
experimentequipmentbeingplannedappropriatelyforthesafe
accomplishmentofthedeuteriumexperimentandtosupport
li ht f th d t iit dttmanagement?
Inthedeuteriumexperiment,aneutronandtritiumareproduced,andthisneutron
activatesthesurroundingmaterials.ActivatedmaterialsradiatethesecondaryGammaͲray.Tomanagethesesafely,itisnecessarytograspquantityoftheneutronproduction
precisely.Tomeasurethequantityofneutronprecisely,thefissionchamberdetectorsare
i l T
h
i
f
i l h fi ih b dused.Toensurethismeasurement,thecalibrationusing252ͲCfwillbecarriedoutinLHD.
ThedeuteriumexperimentislimitedbythequantityoftheneutronproductionandtheThe
deuterium experiment is limited by the quantity of the neutron production and theexperimentisplanednottoexceedthemaximumneutronbudget.
ProtectionagainsttheneutronandgammaͲrayaredesignedusingtheDORTͲcodeand
Protection
against the neutron and gamma ray are designed using the DORT code and
FISPACTͲcode.Inthiscalculation,someshieldingmaterialsandsomethroughholesare
takingaccount.ToreducetheradioͲactivationbytheneutron,someholesareburiedby
the polyethylene and floor concrete under the LHD machine will be covered with thethepolyethyleneandfloorconcreteundertheLHDmachinewillbecoveredwiththe
BoratedPolyethylenebrocks.

37/91(3Ͳ2)Aresafetymanagementequipment,facilities,and
experimentequipmentbeingplannedappropriatelyforthesafe
accomplishmentofthedeuteriumexperimentandtosupport
li ht f th d t iit dttmanagement?
Tominimizetheinfluenceoftheradiationandtritiumtotheenvironment,NIFS
managementlevels,whicharelowerthanthelevelsinlaw,areset.Exhaust,ventilation,
drainare andtheirmonitoringsystemareequippedtokeeptheNIFSmanagementlevel.
Th
Theradiationmonitoringsystemisalsoequipped.
di i
i i
i l
i
d
RadioͲActivewastesareclassifiedinto8categoriesandputinthecontaineroftheJRIA
designation.ThesearekeptatonetimeinaDisposal–byͲStorageFacilityandareasked
designation
These are kept at one time in a Disposal by Storage Facility and are asked
JRIAforprocessing.
Toreducethetritiumintheexhaust,2typeoftritiumremovalsystemsaredesignedandTo
reduce the tritium in the exhaust 2 type of tritium removal systems are designed andequippedastheexhaustgasprocessingsystem.Tritiumconcentrationiscontrol1/25
lowerthanthatinlaw.Recoveredwaterfromthetritiumremovalsystemsiscontained
trebly in the JRIA container and is kept in the waterproof storage section Some tritium
treblyintheJRIAcontainerandiskeptinthewaterproofstoragesection.Sometritium
monitorsaresettogetthebackgrounddata.

38/91

(3Ͳ2)Aresafetymanagementequipment,facilities,and
experimentequipmentbeingplannedappropriatelyforthesafe
accomplishmentofthedeuteriumexperimentandtosupport
li ht f th d t iit dttmanagement?
WorkingproceduresforinͲvesselworkandportworkareestablishedtopreventthe
tritiumexposure.Furthermore,tritiumsafelyhandlingcourseisheldfortritiumhandling
training.
ControlareaissetintheLHDbuilding.Toreduceunguardedexpansionoftheradiation
contamination,entranceofthisareaisonlyone.Rockerroom,contaminationinspection
room decontamination room etc are set taking account the flow line Key of each room
room,decontaminationroom,etc.aresettakingaccounttheflowline.Keyofeachroom
iselectriclockandcontrolledattheaccesscontrolroom.
RadiationrelatedequipmentisconnectedtotheIntegratedRadiationMonitoringSystem
Radiation
related equipment is connected to the Integrated Radiation Monitoring Systemandbemonitoredtheirconditionsonthissystem.SomedateisconnectedtotheLHD
interlocksystem.

39/91(3Ͳ1)IsthefundamentalconceptregardingsafetymanagementappropriateatthetimePoints of Evaluation 3.
oftheformulationofthedeuteriumexperimentexecutionplanasalsobaseduponthe opinions of local residents?
theopinionsoflocalresidents?
㔜Ỉ⣲ᐇ㦂䛾┠ⓗ䛿㐺ษ䛛䚸䜎䛯䛭䛾┠ⓗ䜢㐩ᡂ䛩䜛◊✲ィ⏬ཬ䜃Ᏻ඲䜢☜ಖ䛩䜛ᐇ᪋యไ䛸䛺䛳䛶䛔䜛䛛䚹(3Ͳ2)Aresafetymanagementequipment,facilities,andexperimentequipmentbeingplanned appropriately for the safe accomplishment of the deuterium experimentplannedappropriatelyforthesafeaccomplishmentofthedeuteriumexperiment
andtosupportmanagement?
Ᏻ඲⟶⌮ᶵჾ䞉タഛ䚸ᐇ㦂ᶵჾ➼䛿㔜Ỉ⣲ᐇ㦂䜢Ᏻ඲䛻㐙⾜䛧䚸⥔ᣢ⟶⌮䛩䜛䛯䜑䛻㐺ษ䛻ィ⏬䛥䜜䛶䛔䜛䛛䚹(3Ͳ3)Inordertosafelyaccomplishthedeuteriumexperiment,arevarioustypesof
(3
3) I
d t
f l
li h th d t i
i
t
i
t
f
regulationsbeingformulatedappropriately?
㔜Ỉ⣲ᐇ㦂䜢Ᏻ඲䛻㐙⾜䛩䜛䛯䜑䛻䚸つ๎㢮䛿㐺ษ䛻⟇ᐃ䛥䜜䛶䛔䜛䛛䚹((3Ͳ4)Aretheoperationmanual,theradiationmanagementmanual,andtheemergency
)
h
i
l h
di i
l d h
manualbeingformulatedappropriately?
㐠㌿䝬䝙䝳䜰䝹䚸ᨺᑕ⥺⟶⌮䝬䝙䝳䜰䝹䚸⥭ᛴ᫬䝬䝙䝳䜰䝹➼䛿㐺ษ䛻⟇ᐃ䛥䜜䛶䛔䜛䛛䚹(3Ͳ5)Aretheorganizationandthesystemforsafetymanagementwhenthedeuterium
experimentsarebeingconductedbeingconstructedappropriately?
㔜Ỉ⣲ᐇ㦂䜢ᐇ᪋䛩䜛㝿䛾Ᏻ඲⟶⌮䛾䛯䜑䛾⤌⧊䚸యไ➼䜢㐺ษ䛻ᵓ⠏䛧䛶䛔䜛䛛䚹(3Ͳ6)Areeducationandtrainingforthesafeexecutionofthedeuteriumexperiments,and
nurturingforthoseresponsibleforsafetymanagementbeingundertaken
appropriately?
㔜Ỉ⣲ᐇ㦂䛾Ᏻ඲䛺㐙⾜䛻ྥ䛡䛯ᩍ⫱䞉カ⦎ཬ䜃Ᏻ඲⟶⌮㈐௵⪅䛾㣴ᡂ䛿㐺ษ䛻ィ⏬䛥䜜䛶䛔䜛䛛䚹

40/91

Present NIFS Regulations for Experiment
Followings are present NIFS regulations for LHD experimentͤ [NIFS Regulation of Prevention of Radiation Hazards ] is revising to fit theDeuterium Experiment now
NIFS Safety and Health Regulation
᰾⼥ྜ⛉Ꮫ◊✲ᡤᏳ඲⾨⏕⟶⌮つ๎

NIFS Regulation of Prevention of Radiation Hazards (revising for D-experiment)᰾⼥ྜ⛉Ꮫ◊✲ᡤᨺᑕ⥺㞀ᐖண㜵つ⛬䠄᱌䠅NIFS Detailed Regulation of the Vacuum Maintenance on LHD
᰾⼥ྜ⛉Ꮫ◊✲ᡤ኱ᆺ䝦䝸䜹䝹⿦⨨┿✵⥔ᣢ⟶⌮⣽๎

NIFS Detailed Regulation of the Heavy Ion Beam Probe᰾⼥ྜ⛉Ꮫ◊✲ᡤ㔜䜲䜸䞁䝡䞊䝮䝥䝻䞊䝤⿦⨨䛾⥔ᣢ⟶⌮⣽๎

NIFS Detailed Regulation of Experimental Devices᰾⼥ྜ⛉Ꮫ◊✲ᡤ䛻䛚䛡䜛ᐇ㦂⿦⨨➼䛾⥔ᣢ⟶⌮⣽๎

NIFS Detailed Regulation of the X-rays Device᰾⼥ྜ⛉Ꮫ◊✲ᡤ䛻䛚䛡䜛䜶䝑䜽䝇⥺⿦⨨䛾⥔ᣢ⟶⌮⣽๎

NIFS Detailed Handling Regulation of very small amount Sealed Radioisotope
᰾⼥ྜ⛉Ꮫ◊✲ᡤᚤ㔞ᐦᑒᨺᑕᛶྠ఩ඖ⣲➼ྲྀᢅ⣽๎

NIFS Detailed Regulation of the Ion Beam Analyzer᰾⼥ྜ⛉Ꮫ◊✲ᡤ䜲䜸䞁䝡䞊䝮ゎᯒ⿦⨨䛾⥔ᣢ⟶⌮⣽๎

41/91- General Hierarchy of Law related to Radiation Act(Legislature)

Cabinet Order(Cabinet)

Ordinance(Ministries & Agencies)

Notice(Ministries & Agencies)

Notice for the Radiation
Hazard Prevention Act

Atomic Energy
Basic Act

Cabinet Order for Enforcementof Atomic Energy Basic Act

Radiation Hazard
Prevention Act

Cabinet Order for Enforcementof the Radiation Hazard
Prevention Act

Ministerial Ordnance for
Enforcement of the Radiation
Hazard Prevention Act

Th Reactor
TheRt
Regulation Act

Cabinet Order for Enforcementof the Reactor Regulation Act

Mi i
Ministerial
i l OrdnanceOdforf
Enforcement of the Reactor
Regulation Act

Act for TechnicalStandard on Prevention
off Radiation
R di ti Hazards
Hd
Act for Establishment of
the Nuclear Regulation
Authority

Regulations on Labor
Standards for Minors

Labor Standards Law
Ordinance for Enforcementof the Labor Standards Law

Industrial Safety
and Health Law

Cabinet Order for
Enforcement of the Industrial
Safety and Health Law

Working Environment
Measurement Law

Cabinet Order for
Enforcement of the Industrial
Safety and Health Law

Civil Protection Law

Cabinet Order for Enforcementof the Civil Protection Law

Ordinance on Industrial
S f t and
Safetyd Health
H lth
Ionizing Radiation OrdinanceNotice for the Ionizing
Radiation OrdinanceOrdinance for Enforcement
off IIndustrial
d t i l Safety
S f t andd
Health Law

Working
g Environment
Measurement Standards

42/91

- Rules for Deuterium Experiment Act

Ordinance

NIFS
Regulation

NIFS Internal
Rules

Manual etc.

43/91

We establish internal rules and manuals before starting Deuterium experiment.

- Examples of NIFS Regulation –NIFS Regulation of Prevention of Radiation Hazards

44/91

- Examples of NIFS Regulation –NIFS Detailed Regulation of Experimental Devices

45/91- Examples of NIFS Regulation –NIFS Detailed Handling Regulation of very small amount Sealed Radioisotope

46/91

- Procedure for in-Vessel Work –* Prevent the tritium exposure
One should pass through anterior chamber to enter LHD vacuum vessel
One should- wear protective
t ti clothingl thi dependingddi on workklevel
- check radiation level, oxygen concentration
before entering vacuum vessel
2nd floor 1st floor
indicator

Anterior chamber has- isolated
i l t d airi conditioning
diti i systemt- 2 level control areas divided
by barriers- survey system for fist check
2nd barrier

to VV

tool

shoes
trash

trash
shoes
for VVphone

mask shelfdownstairs

to torus
hall

shoes

desk

protective
clothing

shelf

upstairs

helmet
socks

glove

shoes
1st
barrieranterior chamber

47/91- Procedure for port Work (Vacuum related) –* To prevent the tritium exposure-

One should minimize tritium leak to LHD hall
Staffs who completed the training of tritium handling in Toyama Univ.
can conduct
d t portt work.
k㻳㼍㼠㼑㻌㼂㼍㼘㼢㼑㻺㼛㻵㼚㼟㼠㼍㼘㼘㻌㼀㼑㼙㼜㼛㼞㼍㼘㻌㼃㼛㼞㼗㼞㼛㼛㼙

㼅㼑㼟㼀㼞㼕㼠㼕㼡㼙㻌㻹㼑㼍㼟㼡㼞㼑㼙㼑㼚㼠㻾㼑㼟㼕㼐㼡㼍㼘㻌㼀㼞㼕㼠㼕㼡㼙

㻺㼛㻰㼑㼏㼛㼚㼠㼍㼙㼕㼚㼍㼠㼕㼛㼚

㼅㼑㼟

㼅㼑㼟

with gate valve- Measure residual tritium usingga
tritium monitor- After confirming non-existence ofresidual tritium, port work is
conducted with a proper curing- If residual tritium cannot be
decontaminated, port work is stopped

㻯㼛㼙㼜㼘㼑㼠㼕㼛㼚㻺㼛㻼㼛㼞㼠㻌㼃㼛㼞㼗㻌㼍㼒㼠㼑㼞㻌㻯㼡㼞㼕㼚㼓- LHD vacuum vessel is kept in agppressure during
gp
port work
negative㻿㼠㼛㼜㻌㻼㼛㼞㼠㻌㼃㼛㼞㼗

w/o gate valve- Port work is conducted in a temporal
workk room with
ith a ventilation
til tiequipment
48/91

- NIFS management level 1 –䚽 Controlled Area (Working area)
1 mSv/week(100 mSv/5years)
2
40 B
Bq/cm
/
䚽 Boundary of Controlled Area
1.3 mSv/3month
4 Bq/cm2
䚽 Site Boundary
50 ȝSv/year䚽 Tritium production
37 GBq /year (former 6 years)
55 5 GBq/year (later 3 years)
55.5
䚽 Maximum Tritium release into environment
3 7 GBq/year
3.7
GB /
49/91

- NIFS management level 2 –䚽 Tritium Concentration in Working Environment (Law)

Isotope

Chemicalform

LimitinWorkingenvironment
(Bq/cm3)

3

H

Gaseoustritium

1㽢104

3

H

triatedwaterorvapor

8㽢10Ͳ1

Types of Radioisotopes
TypesofRadioisotopes

䚽 Tritium Concentration in Exhaust ((NIFS managementglevel))

Isotope

Chemicalformf

LimitinAiror
Exhaust( / 3)(Bq/cm3

Gaseoustritium

7㽢101

3

triated water or vapor
triatedwaterorvapor

TypesofRadioisotopes

H
H

LimitinDrainareor
Wastewater( / 3)(Bq/cm2㽢10Ͳ46㽢10Ͳ1

䠄5㽢10Ͳ3䠅䠄6㽢101䠅

( ) : Concentration Limit in Law
50/91

- Radiation Monitoring Equipment -51/91- Communication to the local government NIFS must report the emergency occurrence to the fire department, thepolice station and the hometown local government (Toki, Tajimi, Mizunami
cities and Gifu Prefecture)
Prefecture).
Following items are considered and discussed with the local governments.
䕿 Communication means䞉 satellite phone (facsimile), electric generator, bicycle, etc.
䕿 Working time of the communication system䞉 24 hours
䕿 Matters needingg reportsp䕿 the Important matter which should be reported without delay䕿 the Matter which should be reported in advance or without delay䕿 Report of the disaster occurrence which scale is less than that offormer matter
52/91

- Communication to the local government 1 [Communication Means]䕿 NIFS maintains satellite phones (facsimiles) which possessed
battery.
In addition, these are connected to the non-common use generation
facilities which is available for 7 days
days.
䕿 When a satellite phone (facsimile) is cut off, NIFS dispatches personin Toki city hall, Tajimi city hall, Mizunami city hall and the Tounou
Promotion Bureau
Bureau.
[the Communication System]
Because the monitoring system is operating all day, some person work
as a responsible person by turns.
A responsible person communicates to the local government and to theother staff.

53/91- Communication to the local government 2 [Matter Needing Reports]
䕿 When the accidents such as fires
䕿 When the recovered water containing tritium more than the limits oflaws and ordinances leaked out in the facility by accidents䕿 When the annual dose of radioactivity at the site boundary exceed
the limit in law
䕿 When tritium or Argon-41 more than the limits of law and ordinances
was exhausted
䕿 When the recovered water more than the limits in laws andordinances was drained away
䕿 The earthquakeqthat occurs after caution declaration based on a law,,and earthquakes which level exceeds five minus䕿 When the situation that might have an influence on the neighboring
environment by the disasters and stopped deuterium experiment

54/91

- Communication to the local government 3 [the Important matter which should be reported without delay]䕿 Quantity of annual production of a neutron and tritium exceeds the
NIFS management level䕿 When the keeping recovered water leaked out in an facility by
accidents
䕿 The annual dose of radioactivity of the site border is time beyond the
NIFS management level䕿 When tritium or Argon-41 more than the NIFS management level was
exhausted䕿 When the recovered water more than research institute managementylevel was drained away
䕿 When a deuterium experiment is stopped by the disasters such as
earthquakes, and repair of the major equipment became thenecessary for the experiment reopening

55/91- Communication to the local government 4 [the Matter which should be reported in advance or without delay]pin each fiscal yyear and end
䕿 The start time of the deuterium experiment
time (notify the assembly)䕿 When there are the maintenance plan of the research facility, a researchplan and research contents and these changes (prior communication)
䕿 Results of research (regularly)䕿 A certain matter of the publication duty
䕿 After the deuterium experiment of each fiscal year
year, annual production
quantity of a neutron and tritium, annual exhausted quantity of tritium toenvironment, the annual cumulative dose at the site boundary

56/91

- Communication to the local government 5 [Report of the disaster occurrence which scale is less than that of former
matter]NIFS reports the following cases to the local governments
governments.
䕿 When the Meteorological Agency announces that there was rolling
more than seismic intensity 4 caused by the earthquake in Toki-city,
Tajimi-city and Mizunami-city䕿 When, by a typhoon and/or a seasonal rain front, the disasters suchas a landslide and the large-scale fallen tree may occur
In addition,䕿 Publication to the homepagep g
NIFS uploads on the homepage.
䕿 Reporting means, reporting time zone
It is decided after local discussion with local government
government,.

57/91(3Ͳ3)Inordertosafelyaccomplishthedeuteriumexperiment,arevarious
typesofregulationsbeingformulatedappropriately?
Onstartingthedeuteriumexperiment,NISFispushingforwardthechangeoftheruleand
theestablishmentaccordingtotheIndustrialSafetyandHealthLaw,theAtomicEnergy
BasicActandtheCivilProtectionLawinadditiontothepresentsafetyregulations.
"NIFSRegulationofPreventionofRadiationHazards"wassubmittedtotheSupervisory
Authorityasaregulationrelatingtotheradiationgeneratorduetotheincorporationof2004.SincetheRIforthecalibrationandtheradioactivematerialsforPWIresearchisusedinthedeuteriumexperiment,thisregulationisrevised.
ThiThisregulationisinthetoppriority,andthevariousmanualsaremaintainedtopush
l ti i i th t
i it
d th
i
l
i t i dthforwardthedeuteriumexperimentwhilecheckingtheconsistencywiththisregulation.
Fortheworkswhichhaveapossibilitytocontactwithtritium,suchasinͲvesselworkingFor
the works which have a possibility to contact with tritium such as in vessel working
andportworking,workproceduresareprovidedtokeepasafetywork.FortheinͲvessel
work,theanteriorchamberisprovidedasanentranceofthevacuumvesselandprevents
spread of tritium contamination to the outside
spreadoftritiumcontaminationtotheoutside.

58/91

(3Ͳ3)Inordertosafelyaccomplishthedeuteriumexperiment,arevarious
typesofregulationsbeingformulatedappropriately?
TheNIFSmanagementlevelsforthedoseatthesiteboundaryandthetritium
concentrationfortheexhaustandthedrainagearesettocontrolthesafetybyNIFS.In
addition,themanagementvaluesoftheneutronandtritiumproductionandoftheenvironmentaldoseareset,andtheirmeasuringmethodsandpositiontoensurethesevaluesareset.Measurementofthebackgroundlevelbeforethedeuteriumexperimentis
startedaboutthepossiblemeasuringequipment.
Intheeventofanemergency,communicationmeans,suchasasatellitephone,tothel llocalgovernmentsaresecured,andthereportingmattersandtheannouncementoftheirt
d d thtitt
d tht f th idataareestablished.

59/91(3Ͳ1)IsthefundamentalconceptregardingsafetymanagementappropriateatthetimePoints of Evaluation 3.
oftheformulationofthedeuteriumexperimentexecutionplanasalsobaseduponthe opinions of local residents?
theopinionsoflocalresidents?
㔜Ỉ⣲ᐇ㦂䛾┠ⓗ䛿㐺ษ䛛䚸䜎䛯䛭䛾┠ⓗ䜢㐩ᡂ䛩䜛◊✲ィ⏬ཬ䜃Ᏻ඲䜢☜ಖ䛩䜛ᐇ᪋యไ䛸䛺䛳䛶䛔䜛䛛䚹(3Ͳ2)Aresafetymanagementequipment,facilities,andexperimentequipmentbeingplanned appropriately for the safe accomplishment of the deuterium experimentplannedappropriatelyforthesafeaccomplishmentofthedeuteriumexperiment
andtosupportmanagement?
Ᏻ඲⟶⌮ᶵჾ䞉タഛ䚸ᐇ㦂ᶵჾ➼䛿㔜Ỉ⣲ᐇ㦂䜢Ᏻ඲䛻㐙⾜䛧䚸⥔ᣢ⟶⌮䛩䜛䛯䜑䛻㐺ษ䛻ィ⏬䛥䜜䛶䛔䜛䛛䚹(3Ͳ3)Inordertosafelyaccomplishthedeuteriumexperiment,arevarioustypesof
(3
3) I
d t
f l
li h th d t i
i
t
i
t
f
regulationsbeingformulatedappropriately?
㔜Ỉ⣲ᐇ㦂䜢Ᏻ඲䛻㐙⾜䛩䜛䛯䜑䛻䚸つ๎㢮䛿㐺ษ䛻⟇ᐃ䛥䜜䛶䛔䜛䛛䚹((3Ͳ4)Aretheoperationmanual,theradiationmanagementmanual,andtheemergency
)
h
i
l h
di i
l
d h
manualbeingformulatedappropriately?
㐠㌿䝬䝙䝳䜰䝹䚸ᨺᑕ⥺⟶⌮䝬䝙䝳䜰䝹䚸⥭ᛴ᫬䝬䝙䝳䜰䝹➼䛿㐺ษ䛻⟇ᐃ䛥䜜䛶䛔䜛䛛䚹(3Ͳ5)Aretheorganizationandthesystemforsafetymanagementwhenthedeuterium
experimentsarebeingconductedbeingconstructedappropriately?
㔜Ỉ⣲ᐇ㦂䜢ᐇ᪋䛩䜛㝿䛾Ᏻ඲⟶⌮䛾䛯䜑䛾⤌⧊䚸యไ➼䜢㐺ษ䛻ᵓ⠏䛧䛶䛔䜛䛛䚹(3Ͳ6)Areeducationandtrainingforthesafeexecutionofthedeuteriumexperiments,and
nurturingforthoseresponsibleforsafetymanagementbeingundertaken
appropriately?
㔜Ỉ⣲ᐇ㦂䛾Ᏻ඲䛺㐙⾜䛻ྥ䛡䛯ᩍ⫱䞉カ⦎ཬ䜃Ᏻ඲⟶⌮㈐௵⪅䛾㣴ᡂ䛿㐺ษ䛻ィ⏬䛥䜜䛶䛔䜛䛛䚹

60/91

The operation manual, the radiation management
manual, and the emergency

We are preparing the following three manuals
manuals.
䚽 Facility Operation Manual䚽 Radiation Management Manual for Facility
䚽 Emergency Manual
These manuals stimulate revision to better things while
using them.
them

61/91

- Facility Operation Manual 䚽 Preparing the Operation Manual for the Facilities which will
be used in the Deuterium Experiment.
䚽 This manual is prepared as one of materials which we
decide whether this facility should remove before deuterium
experiment or not.
䚽 Each facility is checked its rating, usefulness and theresistivity against neutron exposure.
䚽 Facility which is not submitted these materials and not
cleared check is removed before the Deuterium Experiment.

62/91

- Model of the Facility Operation Manual -‫ۑۑۑۑ‬㐠㌿࣐ࢽࣗ࢔ࣝ㸦᱌㸧ᖺ᭶᪥
㸯㸬┠ⓗࡇࡢ࣐ࢽࣗ࢔ࣝࡣࠊ‫ࢆۑۑۑۑ‬Ᏻ඲࡟⾜࠺ࡓࡵࠊᚲせ࡞஦㡯ࢆᐃࡵࡿࡶࡢ࡜ࡍࡿࠋ㸰㸬㐠㌿࣭┘どయไ࡟ࡘ࠸࡚㐠㌿࡟ᣊࢃࡿ㈐௵యไࢆ᫂☜࡟ࡋ࡚࠾ࡃࡇ࡜ࠋ
㸱㸬ᐃᮇⅬ᳨࡟ࡘ࠸࡚
ู㏵ᐃࡵࡿ㡯┠࡟ᚑ࠸ࠊᐃᮇⅬ᳨ࢆᐇ᪋ࡍࡿࡇ࡜ࠋ㸲㸬㐠㌿㛤ጞࡢᡭ⥆ࡁ࡟ࡘ࠸࡚
ጞᴗ๓Ⅼ᳨ᨺᑕ⥺⥲ྜ┘どࢩࢫࢸ࣒ࡀືసࡋ࡚࠸ࡿࡇ࡜
ࢆ☜ㄆࡍࡿࠋ
 ጞᴗⅬ᳨⾲࡟ᇶ࡙ࡁᶵჾ࣭タഛࡢⅬ᳨ࢆᐇ᪋ጞᴗⅬ᳨⾲࡟ᇶ࡙ࡁᶵჾ࣭タഛࡢⅬ᳨ࢆᐇ᪋ࡍࡿࠋ㸦ᶵჾẖ࡟ࠊࡑࡢᚲせᛶ࡟ᛂࡌ࡚☜ㄆ㡯┠ࢆタࡅࡿࠋ㸧ᶵჾࡢసື
㸦ᶵჾẖ࡟グ㏙ࡍࡿࠋ㸧䠑䠊㐠㌿᫬䛻䛴䛔䛶䞉ᢸᙜ⪅䛒䜛䛔䛿㐠㌿ဨ䛿䚸ᖖ䛻䚸ᶵჾ䛾೺඲ᛶ䛾☜ㄆ䛻ດ䜑ᢸᙜ⪅䛒䜛䛔䛿㐠㌿ဨ䛿䚸ᖖ䛻䚸ᶵჾ䛾೺඲ᛶ䛾☜ㄆ䛻ດ䜑䜛䛣䛸䚹䞉సᴗ᫬䛻䛿䚸ᖖ᫬ᨺᑕ⥺䝰䝙䝍䜢┘ど䛧䚸␗ᖖ䛾䛒䛳䛯ሙྜ䛻䛿䚸┤䛱䛻䠆䠆䠆䛻㐃⤡䛩䜛䛣䛸䚹䠄ᶵჾẖ䛻䚸䛭䛾ᚲせᛶ䛻ᛂ䛨䛶㡯┠䜢タ䛡䜛䚹䠅䠒䠊㐠㌿⤊஢᫬䛾ᡭ⥆䛝䛻䛴䛔䛶㌿⤊ ᫬⥆
6Ͳ1.೵Ṇసᴗ
6Ͳ2.㐠㌿ᚋ䛾Ⅼ᳨⤊஢Ⅼ᳨⾲䛻ᇶ䛵䛝ᶵჾ䞉タഛ䛾Ⅼ᳨䜢ᐇ᪋䛩䜛䚹⤊஢䜢ᶵჾ㈐௵⪅䠄ྡ⛠䠛䠅䛜☜ㄆ䜢⾜䛖䛣䛸䚹䠓䠊␗ᖖ᫬䛾ᑐᛂ䛻䛴䛔䛶
ู㏵ᐃ䜑䜛␗ᖖ᫬ᑐᛂ䝬䝙䝳䜰䝹䛻ᚑ䛳䛶䚸⾜䛖䛣䛸䚹
䠔䠊䛭䛾௚

௨ୖ

63/91

- Operation Manual for Vacuum Evacuation System

64/91

- Radiation Management Manual for Facility 䚽 Deuterium Experiment : We have to keep the NIFS
management level for an exhaust,
drainage and dose level at the siteboundary.
䚽 Port related Work : We have to minimize the tritium
leakage into the environment.
In addition to the Facility Operation Manual, we pushforward the preparation of the Radiation Management
Manual in the viewpoint of the radiation management every
apparatus.

65/91- Model of the Radiation Management Manual -66/91

- Radiation Management Manual
for LHD Operation Monitoring System -67/91- Emergency Manual We are preparing the Emergency Manual during the Deuterium
Experiment to keep the consistency with the conventionaldidisastert prevention
ti manual.
l䚽 Basic way of thinking to an emergency and a disasterWe have to pay attention to a neutron and tritium which have a
possibility to give influence to environment, when a disaster and/or an
accident occurs.
occursFollowings are basic way of thinking to the deuterium experiment safety
at an emergency and a disaster.
1) Minimize the quantity of occurring tritium,
2) Limit the quantity of tritium remaining in a VV which does not exceed
th managementt level,
thell even if a gross quantity
tit iis released,ld3) Keep the management level of the radiological generations, such as
Ar-41,
Ar
41, which have a possibility to give influence on the environment4) Pay attention severely to a leak of the recovered water.
68/91

- Network at Emergency -69/91- Self Fire Brigade (Plan at D-experiment) -70/91

- Emergency Manual -71/91(3Ͳ4)Aretheoperationmanual,theradiationmanagementmanual,and
theemergencymanualbeingformulatedappropriately?
SincetheequipmentwasinstalledintheLHDhallandtheLHDbasementandtheseareais
setastheControlledAreaafterthestartofthedeuteriumexperiment,"Radiation
ManagementManual","FacilityOperationManual"and"Radiationandequipment
controlledareamanagementManual"areprovidedandrevisedforeachequipment.Each
manualhasbeenwritteninauniformformatalongthemodelthathasbeencreatedbytheDevelopmentTaskForceTeamforLHDDeuteriumProgram.
h D l
T kF
T
f LHD Di
P
"RadiationandequipmentcontrolledareamanagementManual"iswrittenfortheradiationsourcehandling,radiationgeneratingdevice,andthedevicesthatgenerate
radiation
source handling radiation generating device and the devices that generateradiationinoperationevenwhenLHDisnotoperating.Thismanualisdevelopedto
controlthesafetyevenduringnonͲexperimentalperiod.
“EmergencyManual”iswrittenaboutthecommunicationsystem,thedisasterprevention
system,theresponsibilityatthetimeoftheexperiment,etc.takingintoaccounttheconventional disaster prevention manual In particular the security about a radiation andconventionaldisasterpreventionmanual.Inparticular,thesecurityaboutaradiationand
tritiumisensuredbysettingthetopprioritytochecktheRIsafekeepingfacilitiesandthe
tritiumrecoverysystemintheEmergencyManualforthedeuteriumexperiment.For
example, workers’safetyisensuredtosetthetimethatworkercanstayintheLHDhall,
example,workers
safety is ensured to set the time that worker can stay in the LHD hall,whenworkerentersintotheLHDhall,intheviewpointoftheradiationexposure.
72/91

(3Ͳ1)IsthefundamentalconceptregardingsafetymanagementappropriateatthetimePoints of Evaluation 3.
oftheformulationofthedeuteriumexperimentexecutionplanasalsobaseduponthe opinions of local residents?
theopinionsoflocalresidents?
㔜Ỉ⣲ᐇ㦂䛾┠ⓗ䛿㐺ษ䛛䚸䜎䛯䛭䛾┠ⓗ䜢㐩ᡂ䛩䜛◊✲ィ⏬ཬ䜃Ᏻ඲䜢☜ಖ䛩䜛ᐇ᪋యไ䛸䛺䛳䛶䛔䜛䛛䚹(3Ͳ2)Aresafetymanagementequipment,facilities,andexperimentequipmentbeingplanned appropriately for the safe accomplishment of the deuterium experimentplannedappropriatelyforthesafeaccomplishmentofthedeuteriumexperiment
andtosupportmanagement?
Ᏻ඲⟶⌮ᶵჾ䞉タഛ䚸ᐇ㦂ᶵჾ➼䛿㔜Ỉ⣲ᐇ㦂䜢Ᏻ඲䛻㐙⾜䛧䚸⥔ᣢ⟶⌮䛩䜛䛯䜑䛻㐺ษ䛻ィ⏬䛥䜜䛶䛔䜛䛛䚹(3Ͳ3)Inordertosafelyaccomplishthedeuteriumexperiment,arevarioustypesof
(3
3) I
d t
f l
li h th d t i
i
t
i
t
f
regulationsbeingformulatedappropriately?
㔜Ỉ⣲ᐇ㦂䜢Ᏻ඲䛻㐙⾜䛩䜛䛯䜑䛻䚸つ๎㢮䛿㐺ษ䛻⟇ᐃ䛥䜜䛶䛔䜛䛛䚹((3Ͳ4)Aretheoperationmanual,theradiationmanagementmanual,andtheemergency
)
h
i
l h
di i
l d h
manualbeingformulatedappropriately?
㐠㌿䝬䝙䝳䜰䝹䚸ᨺᑕ⥺⟶⌮䝬䝙䝳䜰䝹䚸⥭ᛴ᫬䝬䝙䝳䜰䝹➼䛿㐺ษ䛻⟇ᐃ䛥䜜䛶䛔䜛䛛䚹(3Ͳ5)Aretheorganizationandthesystemforsafetymanagementwhenthedeuterium
experimentsarebeingconductedbeingconstructedappropriately?
㔜Ỉ⣲ᐇ㦂䜢ᐇ᪋䛩䜛㝿䛾Ᏻ඲⟶⌮䛾䛯䜑䛾⤌⧊䚸యไ➼䜢㐺ษ䛻ᵓ⠏䛧䛶䛔䜛䛛䚹(3Ͳ6)Areeducationandtrainingforthesafeexecutionofthedeuteriumexperiments,and
nurturingforthoseresponsibleforsafetymanagementbeingundertaken
appropriately?
㔜Ỉ⣲ᐇ㦂䛾Ᏻ඲䛺㐙⾜䛻ྥ䛡䛯ᩍ⫱䞉カ⦎ཬ䜃Ᏻ඲⟶⌮㈐௵⪅䛾㣴ᡂ䛿㐺ษ䛻ィ⏬䛥䜜䛶䛔䜛䛛䚹73/91

the organization and the system
for safety management
NIFS Safety Promoting Organization
Director General organizes the Safety and Health Committee as a
general safety and health manager based on the Industrial Safety and
Health Law.
Law
Member of the S&H Committee are the safety officer, the health officer,
industrial physician and a few selected NIFS staff.
Meeting is held once in a month and things about safety and health are
discussed.
Division of Health and Safety Promotion, which has 10 offices, carries
outt theth safety
f t andd heathh th relatedl t d mattertt pointed
i t d outt byb the
th abovebcommittee.
Radiation Control office is expanded and performs the administrative
task in the deuterium experiment while getting support of the Radiation
Safetyy Committee (p(plan).
)
74/91

- Structure of NIFS Safety Promoting Organization General Safety and HealthManager

Director General
Electrical Licensed
EngineerManagers of each
Department
Operation Chief

SafetyS
f t andd
HealthCommittee

License Engineer for
Radiation

H lth Officer
HealthOffi
Safety Officer
I d t i l Ph
Industrial
Physiciani i

Safety Technology
Supervisor

Staff

Division Director of Health and Safety Promotion
Environmental Safety Control Office
Health Control OfficeFire and Disaster Prevention Office
Radiation Control OfficeElectrical Equipment and Work Control Office

On-Site Safety
Control

Machinery and Equipment Control OfficeHigh Pressure Gas Control Office
Hazardous Materials Control Office
New Experimental Safety Assessment Office
Safety Handbook Publishing Office
75/91- Radiation Safety System NIFS Radiation Safety System
Control office which will be expanded to deal with the deuterium
experiment performs the administrative.
The Safety Monitoring Committee is organized by the local government
as a third party organization independent of NIFS, and performs
monitoringit i aboutb t theth security
it off theth deuteriumd t iexperiment.
itAfter the deuterium experiment begins, the Monitoring of various
apparatuses, facilities is performed for 24 hours in a whole year.

76/91

Ͳ RadiationControlSystemͲSafetyMonitoring
Committee

Director General
Radiation Protection
Supervisors
Radiation Safety Committee

Chief of Radiation Control Office
Device Managers(Heatings)
Device Managers(Diag’s)Radiation
Controlled Area
M
Manager(LHD Room)Operations Chiefs of Work with X-rays(Diag. bldg. : X-ray emitting device)(Fusion Eng. Res. bldg. : ESCA, XRD)

Health andS f t
SafetyCommittee

DivisionDi
ision Director of Healthand Safety Promotion

underPlanning
Device Manager(LHD VV)

General Health and
Safety Supervisor

Radiation Control
OfficeDevice Radiation Controlled Area Manager(Heating Room : ECH)
Device Radiation Controlled Area Manager(Fusion Eng. Res. bldg. : NBI)
Section Members
Dep. Engn. & Techn. Services
Dep. Helical Research
Radiation Controlled Area Manager((HIBP))

Radiation Controlled Area Manager(Exhaust gas processing area)

Radiation Controlled Area Manager(RI analysis area)

Radiation Controlled Area Manager(RI Storage area)

Environmental Radiation Control
Manager
77/91(3Ͳ5)Aretheorganizationandthesystemforsafetymanagementwhenthedeuteriumexperimentsarebeingconductedbeingconstructed
appropriately?
SafetymanagementsystemofNIFSisestablishedbasedontheIndustrialSafetyand
HealthLawandisconsistoftheGeneralSafetyandhealthmanager,whoistheDirector
General,theHealthOfficer,theSafetyOfficerandtheIndustrialPhysician.TheSafetyand
HealthCommitteeisorganizedabovememberandafewadditionalmembers,anddiscussthethingsrelatedtohealthandsafetyonameetingonceamonth.Furthermore,Division
ofHealthandSafetyPromotionwith10officesisorganizedbytheDirectorGeneral.This
divisioniscarryingoutmatterspointedoutbythiscommitteeandmakesplanfor
improvementofthesafetyandpreventiontheworkͲrelatedaccident.
f h
f
d
h
k l d
d
Afterthestartofthedeuteriumexperiment,theRadiationControlOfficeisexpandedand
d l ith th
dealswiththesafetymanagement.Inaddition,theRadiationSafetyCommittee(tentativef t
t I dditi
th R di ti S f t C
itt (t t tiname)isestablishedasaradiationmanagementsectionotherthantheRadiationControl
Office.AndSafetyMonitoringCommittee(tentativename)isestablishedbythelocal
government and monitors the safety
governmentandmonitorsthesafety.

78/91

(3Ͳ5)Aretheorganizationandthesystemforsafetymanagementwhenthedeuteriumexperimentsarebeingconductedbeingconstructed
appropriately?
MonitoringtheequipmentandmanagementoftheDisposalͲbyͲStorageFacilityareparts
ofthefunctionoftheIntegratedRadiationMonitoringSystem,andthesearecarriedout
in24ͲhoursbothexperimentalandnonͲexperimentalperiod.Whenthereisan
abnormality,necessarystaffisassembledinaccordancewithemergencycontactnetworkanddealswithcorrespondence.

79/91(3Ͳ1)IsthefundamentalconceptregardingsafetymanagementappropriateatthetimePoints of Evaluation 3.
oftheformulationofthedeuteriumexperimentexecutionplanasalsobaseduponthe opinions of local residents?
theopinionsoflocalresidents?
㔜Ỉ⣲ᐇ㦂䛾┠ⓗ䛿㐺ษ䛛䚸䜎䛯䛭䛾┠ⓗ䜢㐩ᡂ䛩䜛◊✲ィ⏬ཬ䜃Ᏻ඲䜢☜ಖ䛩䜛ᐇ᪋యไ䛸䛺䛳䛶䛔䜛䛛䚹(3Ͳ2)Aresafetymanagementequipment,facilities,andexperimentequipmentbeingplanned appropriately for the safe accomplishment of the deuterium experimentplannedappropriatelyforthesafeaccomplishmentofthedeuteriumexperiment
andtosupportmanagement?
Ᏻ඲⟶⌮ᶵჾ䞉タഛ䚸ᐇ㦂ᶵჾ➼䛿㔜Ỉ⣲ᐇ㦂䜢Ᏻ඲䛻㐙⾜䛧䚸⥔ᣢ⟶⌮䛩䜛䛯䜑䛻㐺ษ䛻ィ⏬䛥䜜䛶䛔䜛䛛䚹(3Ͳ3)Inordertosafelyaccomplishthedeuteriumexperiment,arevarioustypesof
(3
3) I
d t
f l
li h th d t i
i
t
i
t
f
regulationsbeingformulatedappropriately?
㔜Ỉ⣲ᐇ㦂䜢Ᏻ඲䛻㐙⾜䛩䜛䛯䜑䛻䚸つ๎㢮䛿㐺ษ䛻⟇ᐃ䛥䜜䛶䛔䜛䛛䚹((3Ͳ4)Aretheoperationmanual,theradiationmanagementmanual,andtheemergency
)
h
i
l h
di i
l d h
manualbeingformulatedappropriately?
㐠㌿䝬䝙䝳䜰䝹䚸ᨺᑕ⥺⟶⌮䝬䝙䝳䜰䝹䚸⥭ᛴ᫬䝬䝙䝳䜰䝹➼䛿㐺ษ䛻⟇ᐃ䛥䜜䛶䛔䜛䛛䚹(3Ͳ5)Aretheorganizationandthesystemforsafetymanagementwhenthedeuterium
experimentsarebeingconductedbeingconstructedappropriately?
㔜Ỉ⣲ᐇ㦂䜢ᐇ᪋䛩䜛㝿䛾Ᏻ඲⟶⌮䛾䛯䜑䛾⤌⧊䚸యไ➼䜢㐺ษ䛻ᵓ⠏䛧䛶䛔䜛䛛䚹(3Ͳ6)Areeducationandtrainingforthesafeexecutionofthedeuteriumexperiments,
andnurturingforthoseresponsibleforsafetymanagementbeingundertaken
appropriately?
㔜Ỉ⣲ᐇ㦂䛾Ᏻ඲䛺㐙⾜䛻ྥ䛡䛯ᩍ⫱䞉カ⦎ཬ䜃Ᏻ඲⟶⌮㈐௵⪅䛾㣴ᡂ䛿㐺ษ䛻ィ⏬䛥䜜䛶䛔䜛䛛䚹80/91

education and, and nurturing responsible person forthe safetyy managementg

Education- General Safety Lectures and Radiation Safety Lectures areheld twice for each in the end of fiscal year for the workers
including students to renew the permission of working in thenext fiscal year.
- Radiation Safety Lectures after the deuterium experimentstart
t t are also
l hheld
ld ttwicei iin a year. F
For a person who
h enterst
the radiation controlled area, new lecture of the non sealed
RI treatment is opened.
opened81/91

Education for the visiting co-researchers• Safety education– All the co-researchers
co researchers are requested to take a safety lecture anda radiation safety lecture before they start the collaboration work.
– A guide line is presented in the “NIFS Safety Handbook”– A covenant should be signed after the lecture.

• Radiation
R di ti safety
f t controlt l– Co-researchers who want to engage in the controlled area (ex.
LHD hall) should be registered as radiation worker before they
start the research• Registration should be carried out at their own universities• If theirth i universityi
it could
ld nott go ththroughh th
the registrationi t ti procedure,d
NIFS would do it instead– A card key to access the controlled area is issued to theradiation worker
82/91

Education for the foreign co-researchers䚽Safety education for theforeign co-researchers is
carriedi d out iin E
Englishli h bby theirh icaretaker- All the co-researchers
co researchers arerequested to take a safety lecture
before start of their collaboration
work in the controlled area.
- A guide line is presented in the“NIFS Safety Handbook”- A covenantt should
h ld bbe signedid afterft
the lecture䚽Warning
g signs
g are presented
in English.
䚽English version of NIFS
S f t Handbook
SafetyH db k iis available.
il bl
83/91

Training and Nurturing for Safety Responsible Manager

Training
For a pperson who want to work in LHD,, it is necessary
y to take class not
only for "a vacuum work in LHD“ but also for "the tritium safely handlingcourse" which is held in the Hydrogen Isotope Research Center in Toyama
University In this class,
University.
class students learn the actual tritium handling
handling.
The contents of the training are as follows.
䞉 knowledge about tritium䞉 the lecture about the radiation preventive rule䞉 the tritium measurement using the tritium detecting device
䞉 tritium decontamination
䞉 trainingt i i off safe
f portt workk
Identification of completion is conferred on a person of completion by thecenter.

84/91

Safety Lecture

Tritium Safely Handling Course

85/91- Training Program of Tritium Safely Handling Course -86/91

Drills
Disaster Drill in NIFS
Disaster p
prevention drill in LHD is held once a yyear.
Toki south fire department participates this drill.
The training includes the report to the local governments.
The radiation control office which is incorporated in the self-defense
disaster prevention team supports the radiation-related correspondence.

Fire Drill in LHD
Fire Drill in LHD during
g experimentpp
period is p
performed some times in a
year.

These Drills are opened to the governments and the
media.
87/91

Disaster Drill in NIFS

Fire Drill in LHD

88/91

Training and Nurturing for Safety Responsible
Manager

Nurturing for Safety Responsible Manager
Detailed knowledge about the radiation is necessary on pushing forward adeuterium experiment safely.
Therefore NIFS recommends to be qualified the license of "first class chief
responsible for handling of radioactive substances" to several people
every year.
Eight people passed it and were able to acquire a qualification so far.
Seven qualified people already exist.
exist
Nine people passed a subject examination this year and they can get aqualification when they receive the technical training.
NIFS iis goingi tot increasei
qualifiedlifi d people
l iin ffuture.
t

89/91

(3Ͳ6)Areeducationandtrainingforthesafeexecutionofthedeuterium
experiments,andnurturingforthoseresponsibleforsafety
management being undertaken appropriately?
managementbeingundertakenappropriately?
Assameasbefore,educationandtrainingsystemismaintainedafterthestartofthe
deuterium experiment and the fresh training course and field education is conducted for
deuteriumexperiment,andthefreshtrainingcourseandfieldeducationisconductedfor
newworkersandupdatecourseforthecontinuators.However,thefreshtrainingcourseareperformedfortwodaysincorporatingthetrainingusingunsealedRIhandling.
InNIFS,thedisasterdrillfortheentireInstituteiscurrentlyconductedonceinayear
combinedwiththereporttrainingtothelocalgovernment,andhastheparticipationofthe Toki south fire department. Also, in LHD, the Fire Drill is conducted at least once atheTokisouthfiredepartment.Also,inLHD,theFireDrillisconductedatleastoncea
yearassumingfireandearthquakeduringtheexperimentalperiod.
pqpTheRadiationControlOfficeisincorporatedintheworksquadoftheprivatedisaster
preventionbrigade,andsupportstheradiationrelatedstepaccordingtotheirduties.Forthedeuteriumexperiment,itisplannedtoincreasetheripenessofthetrainingbyincreasingthenumberoftrainingandperformingitregularlyandtoperformanecessaryactionasfaraspossible.

90/91

(3Ͳ6)Areeducationandtrainingforthesafeexecutionofthedeuterium
experiments,andnurturingforthoseresponsibleforsafety
management being undertaken appropriately?
managementbeingundertakenappropriately?
Inordertogetaknowledgeofradiationsafetyinmanyresearchersandtechnicalofficers,
NIFS encourages the qualification of “firstͲclass
NIFSencouragesthequalificationoffirst classradiationprotectionsupervisor
radiation protection supervisor”toafew
to a few
peopleeveryyear,asaneffortofnurturingthesafetyresponsiblereader.8persongot
thisqualificationbythiseffort.Includingtheexistingqualifiedpersonnel,thereare9
researchers and 7 technical officers who have been qualified. Also, 9 person has passed
researchersand7technicalofficerswhohavebeenqualified.Also,9personhaspassed
thewrittentest,anditispossibletoqualifywhenreceivingthetechnicaltraining.Inthe
future,Itisplannedtogotoincreasethequalifiedpersoninfuture.
Tritiumisproducedduringthedeuteriumexperimentsameasaneutron.Thereisa
possibilitytocontactwithtritiumintheworkssuchasinͲvesselworkingandportworking.
Toaccomplishsuchworksafely,itisnecessaryaresponsiblepersonwhohasaknowledge
andanexperiencetotreattritiumsafely.Inordertonurturesucharesponsibleperson,
“thetritiumsafelyhandlingcourse”isheldintheHydrogenIsotopeResearchCenterin
ToyamaUniversityasapartoftheresearchcollaboration.Thecontentsofthetrainingare
knowledgeabouttritium,thelectureabouttheradiationpreventionregulations,the
tritiummeasurement,tritiumdecontamination,andsafelyportworkusingthedevice
whichreallyhandlestritium.Anidentificationofcompletionisconferredonacompleted
personbythecenter.17peoplehavecompletedthetrainingsofar.
b h
l h
l d h
i i
f
91/91

M２

4. Understanding by Society and Citizens(1) Is enhanced understanding of the safety of the deuterium
experiment being advanced appropriately to local residents?
(2) Is promotion of the deuterium experiment plan being designed inconjunction with local governments?
(3) Is the importance of fusion research and its safety being widely
disseminated in society?

1/13

4. Understanding by Society and Citizens(1) Is enhanced understanding of the safety of the deuterium
experiment being advanced appropriately to local residents?
(2) Is promotion of the deuterium experiment plan being designed inconjunction with local governments?
(3) Is the importance of fusion research and its safety being widely
disseminated in society?

2/13

５

Outreach activities to increase social recognition (1)NIFS has been focusing on the following activities with a view toincrease social recognition of the necessity of fusion research and also
NIFS’sNIFS s scientific achievements
achievements.
30

Number of Times

800
700

ParticipanP
nts- Explanation about LHD and
Deuterium Experiment toincrease local citizen’s
recognition of NIFS’s scientificachievementshit- Forums take place at community
centers at Toki City, Tajimi City,
andd Mizunami
Mi
i City,Cit sincei
2006- In FY 2014, 309 citizens joined
the Forum- Total: 4,190
4 190(for 9 years)

900

25

24 24

24

600

25
20

44

500

36 25 17 19
89 125 150 157

400
300

37
200 129329
100

34
23 23 23 23
232

30

15

163 49152 42504
288 306 296

126

0

Web

338

147
236
120

10
5

Numbe
er of Timees

Public Forum0
Mizunami
Tajimii
Toki
Times- Release off information
by web pagesf
FY- Upgrading of Q&A web page
- Creation of special website featuring scientific events, symposia and conferences3/13

Outreach activities to increase social recognition (2)Publications- Design and publication of the PR magazines and leaflets:
Plasma-kun
kun Dayori
Dayori” and “NIFS
NIFS NEWS”
NEWS issued every 2 months“Plasma“Fusion – Energy to Pave the Way for Future”,“NIFS Do Research Aimed at Extracting Energy from Sea Water”,
Introduction to NIFS and the NIFS TourTour”,“Introduction
and “Welcome to NIFS”

Participation in the local events and festivals- Science Fair in Mizunami City
- Toki Pottery Festival in Toki City
- Oroshi
O hi Pottery
P
Festival
F i l iin Toki
T ki CiCity- Tajimi Pottery Festival in Tajimi City
- Tajimi Festival in Tajimi City
- Children'sChild ' A
Artt F
Festival
ti l iin Tajimi
T ji i City
Cit etc.
t䞉Achievement in FY 2013
- Scientific Handcraft: 29 times- Scientific Experiments: 6 times- Participants: about 1,100 children

4/13

(1) Is enhanced understanding of the safety of the deuterium
experiment being advanced appropriately to local residents?

1 Public forum has been held at 23 – 30 places every year since 2006 to
1.
explain the LHD deuterium experiment, and the total participants werecounted to 4,190 for 9 years, leading to increasing in the local citizen’s
recognition of the NIFS’s
NIFS s scientific achievements and the safety of thedeuterium experiment.
2. Safety information and the Q&A on the deuterium experiment are
uploaded on the NIFS Web site.
3. PR magazines and leaflets are constantly published to the local
residence, and public visitors are positively accepted to show LHD,
counted to over 4,000 people per year.

5/13

4. Understanding by Society and Citizens(1) Is enhanced understanding of the safety of the deuterium
experiment being advanced appropriately to local residents?
(2) Is promotion of the deuterium experiment plan being designed inconjunction with local governments?
(3) Is the importance of fusion research and its safety being widely
disseminated in society?

6/13

Cooperation with Local Autonomies
Agreement for the LHD Deuterium Experiment- 1997: NIFS makes mention on tritium generation in D-D experiment- 1998: Consultation on letter of agreement starts with local autonomies- 2000: NIFS advances letter of agreement to councils and citizens- 2001: Citizens take the case to council for common
nuisance for abort of D-D experiment- 2003:
2003 Adj
Adjustmenttt off common nuisanceiunsuccessful
f l- 2006: Public forums start at local community centers- 2007: Committee of Safety Evaluation of D-Dexperiment organized- 2011: Great Higashi-Nihon earthquake- 2012: NIFS asks conclusion of letter of agreement to local autonomies- 2013: Concluded the Agreement for D-D experiment with local autonomies
Collaboration Research with “Toki“Toki City Plasma Research Committee”- In 1979 move of IPP Nagoya Univ. to Toki City makes
collaborationll b ti researchh startt t- Mainly with elementary, junior-high and high school
teachers at Toki City, and occasionally with scienceteachers at Tajimi City and Ena City
- Activity contents are as follows:䞉 holding of lecture meeting on energy and environment䞉 measurement of environmental radio-activities at 18 locations in Tono region

7/13(2) Is promotion of the deuterium experiment plan being
designed in conjunction with local governments?

1 Negotiation with local governments is fluently made to establish mutual
1.
understanding for the NIFS activities including the deuterium
experiment.
2. Public forums held by NIFS have been supported by the residents’associations, as well as the local governments.
3 Agreement for the deuterium experiment was concluded with the local
3.
governments, and based on this agreement the safety monitoring
committee is organized for the deuterium experiment by the local
governments.
4. Collaboration research with “Toki-City plasma research committee” iscarried out on measurement of environmental radio-activities, andpromotest theth understandingd t di off th
the safety
f t off theth deuteriumd t iexperiment.
i
t

8/13

4. Understanding by Society and Citizens(1) Is enhanced understanding of the safety of the deuterium
experiment being advanced appropriately to local residents?
(2) Is promotion of the deuterium experiment plan being designed inconjunction with local governments?
(3) Is the importance of fusion research and its safety being widely
disseminated in society?

9/13

Release of Information to Public (1)NIFS has been conducting various events and activities for the purposeof informing the public about our research activities.
Open Campus- Once a year in autumn, since 1998
- More than 40 events such as NIFS introduction
introduction,science experiments, and open lecturePa
articipantssFusion Festa in Tokyo- Once a year in Tokyo as science event along the lines ofOpen Campus, since 2010
- Openp lectures and experience-basedpevent like scientifichandcraft
5,000
4,500
4,000
3 500
3,500
3,000
2,500
2,000
1,500
1 000
1,000
500
0

Open Campus
Fusion Festa in Tokyo

FY

10/13

Release of Information to Public (2)Open Lectures for Local Residents- Every year in July and during the International
Toki Conference
Conference, two academic lectures are given forcity residents.
- Showing panels and LHD model at NINS Symposium

7,000

500
450

Visitors

6,000

400

5,000

350

4,000

300

NIFS Tour
3 000
3,000
Th
h t theth year, NIFS welcomesli it- Throughout
visitors
2,000
for the facility tour.
- Visitors can see several experimental facilities
1,000
and hear a summary of NIFS research activities
activities.
0- Tour is on weekday and takes about 90 minutes.
- Three staffed specializing in NIFS tour.

250
200

Times

Release of information by Mailing Lists- “Mail News”: release of event information inaccordance with holding period(registered number: 1,157)- “Mail Magazine”: research activities of NIFS
disseminated twice a month(registered number: 361)

150
100
50
0

FY 11/13

Release of Information to Public (3)Number of SSH

Number off students

Numberu be oof studestudents
ts

Number oof SSH

Educational contributions- Educational partnership activities of Super
Science High School (SSH) :22 high schools, 809 students participated.
- Visiting lectures: 7 high schools- Internshippp
programsgfor jjunior-highg school,, highgschool and technical college students:
7 schools, 21 students

FY

Press Release- 10 times in FY2013- Providing news to Japan Science and Technology Agency(JST) Science Portal,
Portal Science Media Center of Japan,
Japan The
American Association for the Advancement of Science (AAAS)“Eurek Alert!” both at home and abroad.

12/13

(3) Is the importance of fusion research and its safety being
widely disseminated in society?

1 Open campus has been held every year since 1998
1.
1998, showing the NIFS
research activities, and the participant is over 2,000.
2. “Fusion Festa in Tokyo” has been held every year since 2010, forshowing the importance of the fusion energy development widely to
public people, and the participant is over 2,100.
3 Open academic lectures are given for city residents twice a year
3.
year.
4. NIFS research activities are disseminated as a “Mail Magazine” twice amonth.
5. Super Science High School (SSH) activities and the internship programsfor students should contribute to public science education.
6 These6.
Th
activities,
i ii
as wellll as theh ffrequent press releases,lcontribute
ibtowide dissemination of the importance of fusion research in society.

13/13

Results of the Evaluation through the 2014 External Evaluation of the“Deuterium Experiment Implementation Plan”
Number of persons

Items[1](1)Implem
entation[2](2)Prepara [3](1)Fundam [3](2)Plan of[1](2)Researc[1](3)System [2](1)Mainten
system totion system ental way of safetyh plan toance offor joint
conduct
thinking for related
andheighten
research and equipment
research planequipment
maintenance safety
academic
and facilities
joint use
and tomanagement and facilities
systemvalue
managesafety

D

8
9
2
0
0

4
13
2
0
0

8
8
3
0
0

6
12
1
0
0

9
9
1
0
0

3
12
2
0
0

9
7
3
0
0

Avg.
points

4.32

4.11

4.26

4.26

4.42

4.06

4.32

S
A
B
C

S
A
B
C
D

4
11
4
0
0

3
11
3
1
0

6
8
5
0
0

9
8
2
0
0

14
4
0
1
0

11
7
1
0
0

8
11
0
0
0

4.00

3.89

4.05

4.37

4.63

4.53

4.42

Evaluation Response Table
Evaluate extremely highEvaluate highly
PraisedSatisfactory
Not satisfactory

5
4
3
2
1

※ The evaluation results combine theresults from the members based in Japanand the members based abroad. As there
are committee members who did not
respond to all items, the number of
responses differs for each item.

Points for Evaluation

Items
[1]

[4](3)Dissemi[3](6)Educati
nation of theon and[4](1)Enhanc [4](2)Coordin importance[3](3)Appropr [3](4)Appropr [3](5)Formulatraining, andand theation withement oftion ofiate
iate
nurturing ofsafety ofunderstandin local
formulation formulation organization
persons ingovernments fusion
g in safety
and systemof regulations of manuals
charge ofresearchsafetytowardi t（Research Plan）

Are the purposes of the deuterium experiment appropriate? Further, is this a research plan that will achieve its goals and an
implementation system that will protect safety?
Is this a plan that will contribute to advancing our comprehensive understanding of toroidal plasmas and that will heighten the[1](2)
academic value toward achieving fusion?
I thi
Isthis a planl thatth t upon implementationi lt ti will
ill develop
d l a systemtforf joint
j i t use andd joint
j i t researchh thatth t enables
bl theth participation
ti i ti off[1](3)
a wide range of researchers?
[1](1)［2］（Deuterium Experiment Preparation System）

Aiming toward the start of the deuterium experiment in 2016, is this plan appropriate for the preparation of equipment andfacilities?
Is the preparation system leading toward the start of the deuterium experiment appropriate? Is the preparation of facilities[2](2)and instruments including safety equipment advancing appropriately?
[2](1)［3］（Safety Management Plan）

Is the fundamental way of thinking regarding safety management appropriate for the formulation of a deuterium experiment
implementation plan that considers the opinions of local residents?
Will the safety management instruments and the equipment, and the experiment equipment be appropriately planned to safely[3](2)
perform the deuterium experiment and be appropriately planned for operation and maintenance?
[3](1)[3](3) In order to safely accomplish the deuterium experiment, are regulations being appropriately formulated?
[3](4) Are the operation manual, the radiation management manual, and the emergency manual being appropriately formulated?

Are the organization of and the system for safety management upon the implementation of the deuterium experiment being
appropriately constructed?
Are education and training for the safe performance of the deuterium experiment and the nurturing of the person in charge[3](6)
for safety management being appropriately planned?
[3](5)［4］（Society and Understanding）[4](1)

Toward local residents, is enhancement of their understanding of the safety of the deuterium experiment being appropriately
advanced?

[4](2) Is communication with local governments being planned in promoting the deuterium experiment plan?
[4](3) Is the importance and the safety of fusion research being spread widely throughout society?

Average Score by Evaluation Item
5.00
4.75
4.50
4.25
4.00
3.75
3.50
3.25
3.00
2.75
2.50
2.25
2.00
1.75
1.50
1.25
1.00

Avg. points[4](3)Dissemin[1](1)Impleme[3](6)Educatio
ation of the[1](2)Research[3](1)Fundame
ntation system[1](3)System [2](1)Maintena [2](2)Preparati[3](2)Plan of [3](3)Appropri [3](4)Appropri [3](5)Formulati n and training, [4](1)Enhanceplan tontal way of[4](2)Coordina importancefor jjoint
safety‐related
to conduct
nce ofon system
y
and
y
ate
ate
on of
and nurturingg
ment ofti withtion
ith local
l l andd theth safety
f t
h i htheightenthi ki forthinkingfresearch plan
research andequipment maintenanceequipment formulation of formulation of organization of persons in understanding
academicsafetyof fusion
governments
and to manage
charge ofin safety
joint use
and facilities
systemand facilities
regulations
manuals
and systemvaluemanagement
researchsafetysafetytoward society
4.32

4.11

4.26

4.26

4.42

4.06

4.32

4.00

3.89

4.05

4.37

[1](1)Implementation system to conduct
research plan and to manage safety
5.00[4](3)Dissemination of the importance and[1](2)Research plan to heighten academic
the safety of fusion research toward society

4.50

4.42

4.00

[4](2)Coordination with local governments

value

4.32
4.11

[1](3)System for joint research and joint
use

3.50

4.53

4.26

3.00
2.50

[4](1)Enhancement of understanding insafety

4.26

2.00

4.63

[2](1)Maintenance of equipment andfacilities

1.50
1.00

[3](6)Education and training, and nurturing
4.37
of persons in charge of safety

4.42 [2](2)Preparation system and maintenancesystem4.06[3](5)Formulation of organization andsystem4.05[3](1)Fundamental way of thinking forsafety management

3.89

4.00

4.32

[3](4)Appropriate formulation of manuals[3](3)Appropriate formulation ofregulations[3](2)Plan of safety‐related equipment andfacilities

4.63

4.53

Average score per item

4.42

Inter-University Research Institute Corporation
National Institutes of Natural Sciences

National Institute for Fusion Science322-6 Oroshi-cho, Toki, Gifu, 509-5292, Japan

http://www.nifs.ac.jp/