- Email: [email protected]
JA broader approach activities
Fusion Engineering and Design 82 (2007) 435–442
The EU/JA broader approach activities Shinzaburo Matsuda ∗ Japan Atomic Energy Agency, Higashiueno 6-9-3, Taito-ku, Tokyo 110-0015, Japan Received 1 August 2006; received in revised form 20 March 2007; accepted 20 March 2007 Available online 10 May 2007
Abstract The broader approach activities have been set up in a process of ITER construction negotiations. To develop the DEMO Fusion Power Plant, these activities are regarded necessary to be carried out in parallel to ITER and will be implemented jointly in a framework of bilateral agreement between EU and Japanese governments. The paper introduces their scientific and technological contents and timetables. © 2007 Elsevier B.V. All rights reserved. Keywords: ITER site decision; Broader approach; Joint Paper; EU/JA joint work; In support of ITER; International Fusion Energy Research Center; DEMO Design and R&D Coordination Center; ITER Remote Experimentation Center; Computational Simulation Center; IFMIF/EVEDA; Satellite Tokamak; JT-60SA
1. Introduction At the time of ITER site decision in Moscow on 28 June 2005, representatives of EURATOM (EU) and the Government of Japan (JA) set out the main principles for the implementation of the broader approach activities by the “Joint Paper” and jointly declared their intention to implement broader approach activities in support of ITER on a time frame compatible with its construction phase. This concept is derived from the socalled “fast track approach” in EU, and “the third basic fusion research and development program in Japan
(AEC)” seeking for early realization of fusion energy (Fig. 1). On the basis of this declaration, EU and JA started intense discussions on how to establish a framework and the details of activities for joint implementation by organizing technical working groups and governmental meetings. The paper introduces the agreed broader approach joint program and stresses that participation to a project of the broader approach activities is open to any other party to the ITER agreement.
2. Outline of the broader approach activities ∗
Tel.: +81 3 5246 2567; fax: +81 3 5246 2557. E-mail address: [email protected].
0920-3796/$ – see front matter © 2007 Elsevier B.V. All rights reserved. doi:10.1016/j.fusengdes.2007.03.038
The broader approach activities comprise the following three projects:
436
S. Matsuda / Fusion Engineering and Design 82 (2007) 435–442
Fig. 1. A road map toward fusion DEMO reactor from the Japanese Fusion Programme. In parallel to ITER, Blanket Materials Development and Satellite Tokamak Research will be needed.
(1) Engineering Validation and Engineering Design Activities for the International Fusion Materials Irradiation Facility (IFMIF/EVEDA). (2) International Fusion Energy Research Center (IFERC), comprising: (a) A DEMO Design and, R&D Coordination Center aiming at establishing a common basis for a DEMO design. (b) A Computational Simulation Center composed of super-computer facilities for largescale simulation activities. (c) An ITER Remote Experimentation Center to facilitate broad participation of scientists into ITER experiments. (3) Satellite Tokamak Programme including participation in the upgrade of JT-60 Tokamak to an advanced superconducting tokamak and par-
ticipation in its exploitation, to support ITER experimentation and research towards DEMO reactor. Thus, the objective of these activities is to prepare the scientific and technological basis complementary to ITER for DEMO reactor realization.
3. Administrative structure of broader approach The framework is established as a bilateral governmental agreement between the European Union and the Japanese government. The main body of the administrative structure of broader approach is represented by the Steering Committee, Project Committees, Project
S. Matsuda / Fusion Engineering and Design 82 (2007) 435–442
Leaders and Project Teams, and Implementing Agencies. The Steering Committee composed of representatives of EU and Japan, is responsible for the overall direction and supervision of the implementation of the BA Activities. Its functions include appointment of the Project Leaders, approval of the structure of the Project Teams, approval of the Project Plans, work programmes and annual reports for each project. In this the Steering Committee will be assisted by the Project Committees through their functions of making recommendation on the planning, monitoring and reporting on the progress of each project. For each project of the broader approach activities, a Project Leader is appointed who shall be responsible to the Steering Committee for the coordination of the implementation of the project, assisted by the respective Project Team, and shall reports to the Project Committee. Each party shall designate an Implementing Agency to discharge its obligations for the implementation of the activities making available the resources for their implementation. The Japanese Implementing Agency will host the Project Teams and will manage the cash contribution of the parties.
4. Allocation of responsibilities and overall timetable In accordance with the Moscow Joint Paper, resources for the broader approach activities, lasting a period of about ten years, shall be equally provided by EU and Japan. The total amount will be equivalent to 92 Byen in total valued on May 2005. They will be contributed mostly in-kind, and allocation of procurements, tasks and responsibilities have been identified The relative allocation of the resources foreseen is shown in Table 1, in which the overall EU contribution is 339 MiEuro value May 2005, and the overall JA contribution is 46 Byen value May 2005. Table 2 shows the time schedule for each project. The IFMIF/EVEDA and IFERC projects will be implemented in Japan at Rokkasho while the Satellite Tokamak Programme will be implemented at JT-60 Naka in Japan.
437
Table 1 Relative allocation of the resources for each of the project in percentages Project
EU
JA
Sum
IFMIF-EVEDA IFERC Satellite Tokamak (JT-60SA)
14.4 12.0 23.6
7.6 18.7 23.6
22.0 30.7 47.3
Total
50
50
100
The overall EU contribution is 339 MiEuro value May 2005, and the overall JA contribution is 46 Byen value May 2005.
5. International Fusion Materials Irradiation Facility (IFMIF)/Engineering Validation and Engineering Design Activities (EVEDA) The main objective of IFMIF Engineering Validation, Engineering Design Activities (EVEDA) phase, lasting 6 years from the beginning of the broader approach, is to prepare for the construction of the IFMIF intense 14 MeV neutron source for DEMO relevant materials testing (Fig. 2). A Joint Team will be set up in Rokkasho. The Conceptual Design of IFMIF has been carried out under the IEA activities, and the Comprehensive Design Report has been published [1]. The broader approach IFMIF/EVEDA project is in line with the objectives in this report, but essential modifications were made to better guarantee the success of the IFMIF project and reduce its construction time by adding to the EVEDA phase the construction of a prototype low energy accelerator. The main areas of activity during EVEDA are: (1) Engineering design of the IFMIF facility. (2) Design and construction of the low energy section of one of the two IFMIF accelerators up to the first cavity of the Drift Tube Linac. Tests with full power beam will be conducted on the system installed in Rokkasho. (3) Design, construction and tests of a scale 1:3 model of the target facility. (4) Design, construction and tests of mock-ups of the test facility. Engineering design of the IFMIF facility will be conducted basically in accordance with the allocation of the R&D activities. R&D activities are composed of accelerator facility, target facility and test facility. EU is the
438
S. Matsuda / Fusion Engineering and Design 82 (2007) 435–442
major contributor on the accelerator and on the test facility. For the low energy prototype accelerator, EU is responsible to manufacture and test most of the accelerator components including cold test before shipping to Rokkasho, and Japan will contribute a part of the activities, such as the control system. For the target facility, Japan will make major contribution such as construction and testing of 1:3 model, and purification of the lithium. For the test facility, EU will make major contribution. Upon the appointment of the Project Leader, the EVEDA activities are expected to start at the beginning of 2007. 6. International Fusion Research Center (IFERC)
Table 2 Provisional schedule for implementation of each broader approach project
In order to contribute to the ITER project and promote a possible early realization of DEMO, the International Fusion Energy Research Center (IFERC) shall perform the following three design, research and development tasks at Rokkasho (Fig. 3): (1) DEMO Design and R&D Coordination. (2) Fusion Computer Simulation. (3) ITER Remote Experimentation. The three tasks above will be implemented in three individual Centers in IFERC, but the outcome of these tasks shall be exploited and integrated into further design activities of the DEMO power reactors. Their respective missions and activities are defined. 6.1. The DEMO Design and R&D Coordination Centre The DEMO Design and R&D Coordination Centre shall play a central role in coordinating scientific and technological activities necessary to design a DEMO power reactor. The expected products will include conceptual designs of DEMO, in which the outcome of R&D activities are reflected. Main activities to be carried out are: • DEMO conceptual design activities including development of a road-map, identification of physics and
S. Matsuda / Fusion Engineering and Design 82 (2007) 435–442
439
Fig. 2. International Fusion Materials Irradiation Facility (IFMIF) and its Engineering Design Activities (EVEDA).
engineering design and R&D issues, and their coordination. • Research and development activities on DEMO technologies: ◦ Potential activities of common interest for EU and Japan foreseen are R&D on SiCf /SiC composites, tritium technology, materials engineering, advanced neutron multiplier, and advanced tritium breeders for DEMO blanket. The detailed programme will be decided by the Steering Committee following an assessment by European and Japanese experts. ◦ Starting from a first phase of meetings and workshops lasting about three years to establish a common base for DEMO design, it is envisaged that a small joint team will be established to coordinate conceptual design and related R&D activities that would be carried out in the parties.
6.2. Fusion Computer Simulation Centre (CSC) Mission and scope is to establish a Centre of Excellence (COE) for the simulation and modeling of plasma regimes of ITER, of JT-60SA and other fusion experiments, and for the design of DEMO, etc. Simulation research in the CSC will cover areas of fusion science and technology, which need modeling and high performance computing. This will include theory, simulations and analyses of experimental results of ITER, JT-60SA and other fusion experiments. Areas of simulation research will cover: • plasma core simulation of fusion reactor; • first principle simulations; • numerical approach for physics and technology of plasma-wall interaction and of plasma facing components (including relevant material research);
440
S. Matsuda / Fusion Engineering and Design 82 (2007) 435–442
Fig. 3. Activities in the International Fusion Energy Research Center (IFERC) and its relation to other project. IFERC is composed of “DEMO Design and R&D Coordination Center”, “Fusion Computer Simulation Center”, and “ITER Remote Experimentation Center”.
• development of structural and functional materials; • neutronics calculation for fusion reactors. The supercomputer of the center is expected to have a performance in excess of 200 Tera-flops in the case of a scalar. The computer shall be externally accessible, with sufficient transmission rate to Europe including the ITER site. The computational resources and the grid bandwidth have to be in a reasonable relation. A high performance computer will be made available in 2012. Before the computer becomes available, co-operative preparation activities including decision for the performance target and simulation code development shall be implemented. As for the operation, projects on topical areas may be carried out entirely as joint projects or within one party (EU/JA).
6.3. ITER Remote Experimentation Center (REC) The REC will be developed as a remote control room for experimental campaigns preparation and data analysis for ITER. The REC should be able in the future to monitor the ITER plant status, presenting the main machine and plasma parameters in real time, and accessing promptly the experimental data for further analysis at REC, prepare and transfer pulse parameter files to CODAC. The REC will be tested on JT-60SA at the end of its upgrade. The objectives of REC during the broader approach period are: • to demonstrate the functionality of a Remote Experimentation Centre on JT-60SA before actual use for ITER experimentation;
S. Matsuda / Fusion Engineering and Design 82 (2007) 435–442
441
• to develop a Burning Tokamak Simulator in conjunction with the CSC to be used in the preparation of ITER Operation. To implement these activities, the REC should include a fast network connection to transfer data and experimental parameters, a computer system for analysis, which will be also linked to the supercomputer and other systems in CSC. The REC will operate during the 2 last years of the BA period. Design and development of REC should start in 2012. The future possible use of the REC on ITER will be discussed with the ITER parties and the ITER organization.
7. Satellite Tokamak Programme (JT-60SA) The JT-60SA proposal consists of upgrading JT-60U, mainly by making it a superconducting tokamak with ITER and DEMO relevant features. A joint-EU and Japan experts WG has been set up to review whether the Japanese JT-60SA proposal were suitable as a possible ITER satellite tokamak in the broader approach context. The WG has also assessed the progress towards DEMO that could be achieved with JT-60SA in complement to ITER. The WG has shown the design has the capability to address key physics issues for ITER/DEMO and would be strengthened by: • the extension of the heating and current drive (H&CD) capability to 41 MW for 100 s; • the inclusion of an option for upgrading to metallic Plasma Facing Components; • the increase in the neutron budget to allow for a comprehensive exploitation of the device capabilities. These changes with respect to the original JT60SA proposal are being taken into account. Thus the main design features are the following (Fig. 4 and Table 3). The JT-60SA is a tokamak with superconducting TF and PF magnets capable of confining break-even class high temperature plasma for 100s with intensive heating and current drive power of 41 MW. The JT60SA device incorporates wide flexibility in plasma
Fig. 4. Birds eye view of JT-60SA.
shape and divertor configuration with plasma aspect ratio down to 2.6, elongation up to 1.83, triangularity up to 0.6, single and double null divertors. It also incorporates a stabilizing shell and in-vessel coils for fast feedback control of plasma position. Sector coils for stabilization of RWM and error field correction coils are foreseen inside and outside of vacuum vessel, respectively. The cost review has shown a good agreement between the EU and JA estimates and, on this basis, Table 3 Major parameters of JT-60SA Plasma current Major radius Minor radius Elongation κ95 Triangularity δ95 Toroidal field Bt Safety factor q95 Flat top H&CD power Perp NB Co P-NB CTR P-NB N-NB ECRP PFC heat flux Annual neutron
5.5 MA/3.5 MA 3.01 m/3.16 m 1.14 m/1.02 m 1.83/1.7 0.57/0.33 2.72/2.59 3.77/3.0 100 s (8 h) 41 MW × l00 s 16 MW 4 MW 4 MW 10 MW 7 MW 10 MW/m2 4 × 1021
442
S. Matsuda / Fusion Engineering and Design 82 (2007) 435–442
the procurement allocation between EU and Japan has been decided. Since the construction and exploitation of the JT-60SA is conducted under the Satellite Tokamak Programme and the Japanese national programme, the exploitation opportunities of the JT-60SA are agreed to be equally shared between the national programme and the Satellite Tokamak Programme. Construction of the JT-60SA will start immediately after the ratification of the agreement. It will take about seven years before the first plasma and about three years of exploitation can be planned within the present broader approach period. Modalities for further exploitation of the facility beyond this period will be discussed later by EU and Japan.
Acknowledgements The framework of the broader approach activities has been developed by the EU and the Japanese Government, and the author would like to express sincere thanks to the persons involved from both sides. The author also would like to thank Drs. M. Gasparotto, R. Andrearni and S. Paidassi for their comments and supports in preparing the manuscript.
Reference [1] IFMIF Comprehensive Design Report, IFMIF International Team, 2004, IEA on-line publication, http://www.iea.org/ Textbase/techno/technologies/fusion/IFMIF-CDR PartA.pdf.
The EU/JA broader approach activities Shinzaburo Matsuda ∗ Japan Atomic Energy Agency, Higashiueno 6-9-3, Taito-ku, Tokyo 110-0015, Japan Received 1 August 2006; received in revised form 20 March 2007; accepted 20 March 2007 Available online 10 May 2007
Abstract The broader approach activities have been set up in a process of ITER construction negotiations. To develop the DEMO Fusion Power Plant, these activities are regarded necessary to be carried out in parallel to ITER and will be implemented jointly in a framework of bilateral agreement between EU and Japanese governments. The paper introduces their scientific and technological contents and timetables. © 2007 Elsevier B.V. All rights reserved. Keywords: ITER site decision; Broader approach; Joint Paper; EU/JA joint work; In support of ITER; International Fusion Energy Research Center; DEMO Design and R&D Coordination Center; ITER Remote Experimentation Center; Computational Simulation Center; IFMIF/EVEDA; Satellite Tokamak; JT-60SA
1. Introduction At the time of ITER site decision in Moscow on 28 June 2005, representatives of EURATOM (EU) and the Government of Japan (JA) set out the main principles for the implementation of the broader approach activities by the “Joint Paper” and jointly declared their intention to implement broader approach activities in support of ITER on a time frame compatible with its construction phase. This concept is derived from the socalled “fast track approach” in EU, and “the third basic fusion research and development program in Japan
(AEC)” seeking for early realization of fusion energy (Fig. 1). On the basis of this declaration, EU and JA started intense discussions on how to establish a framework and the details of activities for joint implementation by organizing technical working groups and governmental meetings. The paper introduces the agreed broader approach joint program and stresses that participation to a project of the broader approach activities is open to any other party to the ITER agreement.
2. Outline of the broader approach activities ∗
Tel.: +81 3 5246 2567; fax: +81 3 5246 2557. E-mail address: [email protected].
0920-3796/$ – see front matter © 2007 Elsevier B.V. All rights reserved. doi:10.1016/j.fusengdes.2007.03.038
The broader approach activities comprise the following three projects:
436
S. Matsuda / Fusion Engineering and Design 82 (2007) 435–442
Fig. 1. A road map toward fusion DEMO reactor from the Japanese Fusion Programme. In parallel to ITER, Blanket Materials Development and Satellite Tokamak Research will be needed.
(1) Engineering Validation and Engineering Design Activities for the International Fusion Materials Irradiation Facility (IFMIF/EVEDA). (2) International Fusion Energy Research Center (IFERC), comprising: (a) A DEMO Design and, R&D Coordination Center aiming at establishing a common basis for a DEMO design. (b) A Computational Simulation Center composed of super-computer facilities for largescale simulation activities. (c) An ITER Remote Experimentation Center to facilitate broad participation of scientists into ITER experiments. (3) Satellite Tokamak Programme including participation in the upgrade of JT-60 Tokamak to an advanced superconducting tokamak and par-
ticipation in its exploitation, to support ITER experimentation and research towards DEMO reactor. Thus, the objective of these activities is to prepare the scientific and technological basis complementary to ITER for DEMO reactor realization.
3. Administrative structure of broader approach The framework is established as a bilateral governmental agreement between the European Union and the Japanese government. The main body of the administrative structure of broader approach is represented by the Steering Committee, Project Committees, Project
S. Matsuda / Fusion Engineering and Design 82 (2007) 435–442
Leaders and Project Teams, and Implementing Agencies. The Steering Committee composed of representatives of EU and Japan, is responsible for the overall direction and supervision of the implementation of the BA Activities. Its functions include appointment of the Project Leaders, approval of the structure of the Project Teams, approval of the Project Plans, work programmes and annual reports for each project. In this the Steering Committee will be assisted by the Project Committees through their functions of making recommendation on the planning, monitoring and reporting on the progress of each project. For each project of the broader approach activities, a Project Leader is appointed who shall be responsible to the Steering Committee for the coordination of the implementation of the project, assisted by the respective Project Team, and shall reports to the Project Committee. Each party shall designate an Implementing Agency to discharge its obligations for the implementation of the activities making available the resources for their implementation. The Japanese Implementing Agency will host the Project Teams and will manage the cash contribution of the parties.
4. Allocation of responsibilities and overall timetable In accordance with the Moscow Joint Paper, resources for the broader approach activities, lasting a period of about ten years, shall be equally provided by EU and Japan. The total amount will be equivalent to 92 Byen in total valued on May 2005. They will be contributed mostly in-kind, and allocation of procurements, tasks and responsibilities have been identified The relative allocation of the resources foreseen is shown in Table 1, in which the overall EU contribution is 339 MiEuro value May 2005, and the overall JA contribution is 46 Byen value May 2005. Table 2 shows the time schedule for each project. The IFMIF/EVEDA and IFERC projects will be implemented in Japan at Rokkasho while the Satellite Tokamak Programme will be implemented at JT-60 Naka in Japan.
437
Table 1 Relative allocation of the resources for each of the project in percentages Project
EU
JA
Sum
IFMIF-EVEDA IFERC Satellite Tokamak (JT-60SA)
14.4 12.0 23.6
7.6 18.7 23.6
22.0 30.7 47.3
Total
50
50
100
The overall EU contribution is 339 MiEuro value May 2005, and the overall JA contribution is 46 Byen value May 2005.
5. International Fusion Materials Irradiation Facility (IFMIF)/Engineering Validation and Engineering Design Activities (EVEDA) The main objective of IFMIF Engineering Validation, Engineering Design Activities (EVEDA) phase, lasting 6 years from the beginning of the broader approach, is to prepare for the construction of the IFMIF intense 14 MeV neutron source for DEMO relevant materials testing (Fig. 2). A Joint Team will be set up in Rokkasho. The Conceptual Design of IFMIF has been carried out under the IEA activities, and the Comprehensive Design Report has been published [1]. The broader approach IFMIF/EVEDA project is in line with the objectives in this report, but essential modifications were made to better guarantee the success of the IFMIF project and reduce its construction time by adding to the EVEDA phase the construction of a prototype low energy accelerator. The main areas of activity during EVEDA are: (1) Engineering design of the IFMIF facility. (2) Design and construction of the low energy section of one of the two IFMIF accelerators up to the first cavity of the Drift Tube Linac. Tests with full power beam will be conducted on the system installed in Rokkasho. (3) Design, construction and tests of a scale 1:3 model of the target facility. (4) Design, construction and tests of mock-ups of the test facility. Engineering design of the IFMIF facility will be conducted basically in accordance with the allocation of the R&D activities. R&D activities are composed of accelerator facility, target facility and test facility. EU is the
438
S. Matsuda / Fusion Engineering and Design 82 (2007) 435–442
major contributor on the accelerator and on the test facility. For the low energy prototype accelerator, EU is responsible to manufacture and test most of the accelerator components including cold test before shipping to Rokkasho, and Japan will contribute a part of the activities, such as the control system. For the target facility, Japan will make major contribution such as construction and testing of 1:3 model, and purification of the lithium. For the test facility, EU will make major contribution. Upon the appointment of the Project Leader, the EVEDA activities are expected to start at the beginning of 2007. 6. International Fusion Research Center (IFERC)
Table 2 Provisional schedule for implementation of each broader approach project
In order to contribute to the ITER project and promote a possible early realization of DEMO, the International Fusion Energy Research Center (IFERC) shall perform the following three design, research and development tasks at Rokkasho (Fig. 3): (1) DEMO Design and R&D Coordination. (2) Fusion Computer Simulation. (3) ITER Remote Experimentation. The three tasks above will be implemented in three individual Centers in IFERC, but the outcome of these tasks shall be exploited and integrated into further design activities of the DEMO power reactors. Their respective missions and activities are defined. 6.1. The DEMO Design and R&D Coordination Centre The DEMO Design and R&D Coordination Centre shall play a central role in coordinating scientific and technological activities necessary to design a DEMO power reactor. The expected products will include conceptual designs of DEMO, in which the outcome of R&D activities are reflected. Main activities to be carried out are: • DEMO conceptual design activities including development of a road-map, identification of physics and
S. Matsuda / Fusion Engineering and Design 82 (2007) 435–442
439
Fig. 2. International Fusion Materials Irradiation Facility (IFMIF) and its Engineering Design Activities (EVEDA).
engineering design and R&D issues, and their coordination. • Research and development activities on DEMO technologies: ◦ Potential activities of common interest for EU and Japan foreseen are R&D on SiCf /SiC composites, tritium technology, materials engineering, advanced neutron multiplier, and advanced tritium breeders for DEMO blanket. The detailed programme will be decided by the Steering Committee following an assessment by European and Japanese experts. ◦ Starting from a first phase of meetings and workshops lasting about three years to establish a common base for DEMO design, it is envisaged that a small joint team will be established to coordinate conceptual design and related R&D activities that would be carried out in the parties.
6.2. Fusion Computer Simulation Centre (CSC) Mission and scope is to establish a Centre of Excellence (COE) for the simulation and modeling of plasma regimes of ITER, of JT-60SA and other fusion experiments, and for the design of DEMO, etc. Simulation research in the CSC will cover areas of fusion science and technology, which need modeling and high performance computing. This will include theory, simulations and analyses of experimental results of ITER, JT-60SA and other fusion experiments. Areas of simulation research will cover: • plasma core simulation of fusion reactor; • first principle simulations; • numerical approach for physics and technology of plasma-wall interaction and of plasma facing components (including relevant material research);
440
S. Matsuda / Fusion Engineering and Design 82 (2007) 435–442
Fig. 3. Activities in the International Fusion Energy Research Center (IFERC) and its relation to other project. IFERC is composed of “DEMO Design and R&D Coordination Center”, “Fusion Computer Simulation Center”, and “ITER Remote Experimentation Center”.
• development of structural and functional materials; • neutronics calculation for fusion reactors. The supercomputer of the center is expected to have a performance in excess of 200 Tera-flops in the case of a scalar. The computer shall be externally accessible, with sufficient transmission rate to Europe including the ITER site. The computational resources and the grid bandwidth have to be in a reasonable relation. A high performance computer will be made available in 2012. Before the computer becomes available, co-operative preparation activities including decision for the performance target and simulation code development shall be implemented. As for the operation, projects on topical areas may be carried out entirely as joint projects or within one party (EU/JA).
6.3. ITER Remote Experimentation Center (REC) The REC will be developed as a remote control room for experimental campaigns preparation and data analysis for ITER. The REC should be able in the future to monitor the ITER plant status, presenting the main machine and plasma parameters in real time, and accessing promptly the experimental data for further analysis at REC, prepare and transfer pulse parameter files to CODAC. The REC will be tested on JT-60SA at the end of its upgrade. The objectives of REC during the broader approach period are: • to demonstrate the functionality of a Remote Experimentation Centre on JT-60SA before actual use for ITER experimentation;
S. Matsuda / Fusion Engineering and Design 82 (2007) 435–442
441
• to develop a Burning Tokamak Simulator in conjunction with the CSC to be used in the preparation of ITER Operation. To implement these activities, the REC should include a fast network connection to transfer data and experimental parameters, a computer system for analysis, which will be also linked to the supercomputer and other systems in CSC. The REC will operate during the 2 last years of the BA period. Design and development of REC should start in 2012. The future possible use of the REC on ITER will be discussed with the ITER parties and the ITER organization.
7. Satellite Tokamak Programme (JT-60SA) The JT-60SA proposal consists of upgrading JT-60U, mainly by making it a superconducting tokamak with ITER and DEMO relevant features. A joint-EU and Japan experts WG has been set up to review whether the Japanese JT-60SA proposal were suitable as a possible ITER satellite tokamak in the broader approach context. The WG has also assessed the progress towards DEMO that could be achieved with JT-60SA in complement to ITER. The WG has shown the design has the capability to address key physics issues for ITER/DEMO and would be strengthened by: • the extension of the heating and current drive (H&CD) capability to 41 MW for 100 s; • the inclusion of an option for upgrading to metallic Plasma Facing Components; • the increase in the neutron budget to allow for a comprehensive exploitation of the device capabilities. These changes with respect to the original JT60SA proposal are being taken into account. Thus the main design features are the following (Fig. 4 and Table 3). The JT-60SA is a tokamak with superconducting TF and PF magnets capable of confining break-even class high temperature plasma for 100s with intensive heating and current drive power of 41 MW. The JT60SA device incorporates wide flexibility in plasma
Fig. 4. Birds eye view of JT-60SA.
shape and divertor configuration with plasma aspect ratio down to 2.6, elongation up to 1.83, triangularity up to 0.6, single and double null divertors. It also incorporates a stabilizing shell and in-vessel coils for fast feedback control of plasma position. Sector coils for stabilization of RWM and error field correction coils are foreseen inside and outside of vacuum vessel, respectively. The cost review has shown a good agreement between the EU and JA estimates and, on this basis, Table 3 Major parameters of JT-60SA Plasma current Major radius Minor radius Elongation κ95 Triangularity δ95 Toroidal field Bt Safety factor q95 Flat top H&CD power Perp NB Co P-NB CTR P-NB N-NB ECRP PFC heat flux Annual neutron
5.5 MA/3.5 MA 3.01 m/3.16 m 1.14 m/1.02 m 1.83/1.7 0.57/0.33 2.72/2.59 3.77/3.0 100 s (8 h) 41 MW × l00 s 16 MW 4 MW 4 MW 10 MW 7 MW 10 MW/m2 4 × 1021
442
S. Matsuda / Fusion Engineering and Design 82 (2007) 435–442
the procurement allocation between EU and Japan has been decided. Since the construction and exploitation of the JT-60SA is conducted under the Satellite Tokamak Programme and the Japanese national programme, the exploitation opportunities of the JT-60SA are agreed to be equally shared between the national programme and the Satellite Tokamak Programme. Construction of the JT-60SA will start immediately after the ratification of the agreement. It will take about seven years before the first plasma and about three years of exploitation can be planned within the present broader approach period. Modalities for further exploitation of the facility beyond this period will be discussed later by EU and Japan.
Acknowledgements The framework of the broader approach activities has been developed by the EU and the Japanese Government, and the author would like to express sincere thanks to the persons involved from both sides. The author also would like to thank Drs. M. Gasparotto, R. Andrearni and S. Paidassi for their comments and supports in preparing the manuscript.
Reference [1] IFMIF Comprehensive Design Report, IFMIF International Team, 2004, IEA on-line publication, http://www.iea.org/ Textbase/techno/technologies/fusion/IFMIF-CDR PartA.pdf.