BA IFERC Project Team

Aomori Shi, Japan

BA IFERC Project Team

Aomori Shi, Japan
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Nishitani T.,Japan Atomic Energy Agency | Garin P.,CEA Cadarache Center | Sugimoto M.,BA IFMIF EVEDA Project Team | Nakajima N.,BA IFERC Project Team | And 7 more authors.
Fusion Engineering and Design | Year: 2012

In the Broader Approach framework, the International Fusion Materials Irradiation Facility/Engineering Validation and Engineering Design Activities (IFMIF/EVEDA) project, the International Fusion Energy Research Center (IFERC) project, and the Satellite Tokamak project are implemented. In the IFMIF/EVEDA project, engineering design of IFMIF and engineering R&D include the construction and tests of an IFMIF prototype accelerator system up with a 9 MeV and CW deuteron beam, a liquid lithium test loop with free surface flow, and full scale irradiation test module including temperature control instrumentation. The commissioning of the EVEDA lithium test loop was completed in March 2011, and a lithium flow of ∼5 m/s was obtained. As a part of the IFERC project, R&Ds on reduced activation ferritic/martensitic steels as blanket structural material, SiC f/SiC composites as a flow channel insert material and/or alternative structural material, advanced tritium breeders and neutron multipliers, and tritium technology are carried out. At the beginning of 2011, the integrated DEMO design team was established among the IFERC project team and EU/JA home teams, where the design criteria, other design basis are discussed as an initial work. A high performance supercomputer with the peak performance of 1.3 Pflops is under installation at the Rokkasho BA site. © 2012 Elsevier B.V. All rights reserved.


Nishitani T.,Japan Atomic Energy Agency | Tanigawa H.,Japan Atomic Energy Agency | Nozawa T.,Japan Atomic Energy Agency | Jitsukawa S.,Japan Atomic Energy Agency | And 14 more authors.
Journal of Nuclear Materials | Year: 2011

As a part of the Broader Approach activities, R&D on blanket related materials, reduced-activation ferritic martensitic (RAFM) steels as a structural material, SiCf/SiC composites for flow channel insert in the liquid blanket and/or use as advanced structural material, advanced tritium breeders and neutron multiplier, has been initiated directed at DEMO. As part of the RAFM steel mass production development, a 5 ton heat of RAFM steel (F82H) was procured by Electro Slag Re-melting as the secondary melting method, which was effective in controlling unwanted impurities. An 11 ton heat of EUROFER was also produced. For the SiCf/SiC composite development, NITE- and CVI-SiCf/SiC composites were prepared as reference materials and preliminary mechanical and physical properties were measured. Also compatibility tests between SiC and Pb-17Li have been prepared, related to the He-cooled Li-Pb blanket concept. For the beryllide neutron multiplayer Be-Ti alloy development, large size rods of about 30 mm diameter were fabricated successfully in EU. © 2011 Elsevier B.V. All rights reserved.


De Tommasi G.,Fusion for Energy F4E | De Tommasi G.,University of Naples Federico II | Manduchi G.,Consorzio RFX | Muir D.G.,Culham Center for Fusion Energy | And 7 more authors.
Fusion Engineering and Design | Year: 2015

The ITER Remote Experimentation Centre (REC) is one of the projects under implementation within the BA agreement. The final objective of the REC is to allow researchers to take part in the experimentation on ITER from a remote location. Before ITER first operations, the REC will be used to evaluate ITER-relevant technologies for remote participation. Among the different software tools needed for remote participation, an important one is the Remote Data Access System (RDA), which provides a single software infrastructure to access data stored at the remotely participating experiment, regardless of the geographical location of the users. This paper introduces the European contribution to the RDA system for the REC. © 2015 Elsevier B.V.


Yamanishi T.,Japan Atomic Energy Agency | Asakura N.,Japan Atomic Energy Agency | Tobita K.,Japan Atomic Energy Agency | Ohira S.,Japan Atomic Energy Agency | And 5 more authors.
Fusion Engineering and Design | Year: 2015

The Broader Approach (BA) activities consists of three major projects: the International Fusion Energy Research Center (IFERC) project, the International Fusion Materials Irradiation Facility/Engineering Validation and Engineering Design Activities (IFMIF/EVEDA) project, and the Satellite Tokamak Programme (STP, JT-60SA). These projects have been carried out to obtain basic data for the design of DEMO fusion reactor from 2007. For 8-year activities, the above projects could produce a set of fruitful results for the DEMO reactor. DEMO design activity has been conducted to build a set of DEMO design bases in accordance with a series of discussion between EU and JA. In the DEMO R&D activities, five basic R&D subjects for a DEMO blanket system have been selected, and been studies under close collaborations between EU and JA: structure materials (RAFM steels and SiC/SiC composites), functional materials (tritium breeders and neutron multipliers), and tritium technology. Some additional R&D subjects recommended by peer review comments have also been studied successfully in recent years. Regarding the IFMIF/EVEDA project, some main components of the accelerator facility been designed and tested. The validation test using EVEDA Lithium Test Loop (ELTL) was also completed successfully in October 2014. © 2015.


Nishitani T.,Japan Atomic Energy Agency | Tobita K.,Japan Atomic Energy Agency | Okano K.,BA IFERC Project Team | Sugimoto M.,Japan Atomic Energy Agency | And 4 more authors.
Fusion Science and Technology | Year: 2014

In the Broader Approach (BA) activities, cooperated work on the DEMO design is undertaken with the IFERC project team and home teams in the EU and Japan. System code benchmarking to establish the common design tools and the definition of critical design issues have been progressed so far. The BA DEMO design work is focusing on the common critical issues such as divertor design, remote maintenance scheme, and blanket design. In parallel, safety research for the fusion power plant started re-analyses, which include severe events such as total loss of coolant without any electric power. In the DEMO R&D activities, five R&D tasks related to blanket materials and technology are carried out intensively according to the common interests of the EU and Japan for DEMO. A neutron source using the IFMIF/EVEDA prototype accelerator and the IFMIF/EVEDA lithium target test loop is under discussion as one of the major activities after 2017.


Nishitani T.,Japan Atomic Energy Agency | Tanigawa H.,Japan Atomic Energy Agency | Yamanishi T.,Japan Atomic Energy Agency | Lorenzo S.C.,Fusion for Energy F4E | And 8 more authors.
Fusion Science and Technology | Year: 2012

In parallel to the ITER program, the Broader Approach (BA) activities with three projects are being implemented by the European Union (EU) and Japan. Five research and development (R&D) tasks, mainly on blanketrelated materials, are being carried out as the DEMO R&D program in the BA to establish key technologies required for the DEMO engineering design. The DEMO R&D building was constructed in March 2010, and the installation of research equipment was completed in March 2011. As the BA DEMO R&D, fabrication technology and/or characterization of reduced activation ferritic/ martensitic steels, SiC/SiC composites, and the advanced neutron multiplier and advanced tritium breeder have progressed in Japan and the EU. In the Inter national Fusion Materials Irradiation Facility (IFMIF)/ Engineering Design and Engineering Validation Activities (EVEDA) project, engineering design and validations have progressed. The injector of the IFMIF prototype accelerator produced first beam successfully in May 2011 and will be delivered to the Rokkasho BA site in 2012. The commissioning of the EVEDA lithium test loop was completed in March 2011, and a lithium flow of 25 mm thick at ∼5 m/s was obtained.


Nishitani T.,Japan Atomic Energy Agency | Sugimoto M.,Japan Atomic Energy Agency | Ohira S.,Japan Atomic Energy Agency | Yamanishi T.,Japan Atomic Energy Agency | And 9 more authors.
Fusion Engineering and Design | Year: 2013

In Rokkasho Japan, the International Fusion Energy Research Center (IFERC) project and the International Fusion Materials Irradiation Facility/Engineering Validation and Engineering Design Activities (IFMIF/EVEDA) project are on going under the Broader Approach framework. The IFERC project consists of three sub-projects; a fusion demonstration reactor (DEMO) Design and R&D Coordination Center, a Computational Simulation Center (CSC), and an ITER Remote Experimentation Center (REC). DEMO Design activity has been conducted by the IFERC project team in Rokkasho and home teams in EU and JA. In the DEMO R&D activity, five R&D tasks mainly of the blanket materials are carried out intensively. A supercomputer with 1.23 Pflops of LINPAC performance has been installed in December 2011, the operation started in January 2012. Discussion of overall plan of REC has started in 2012 between EU and Japan. In the IFMIF/EVEDA project, an IFMIF prototype accelerator system up to 9 MeV with 125 mA CW deuteron beam will be installed and tested in Rokkasho. Major components of the accelerator are under development or fabrication in EU. The first component of the accelerator, an injector with an ECR ion source, will be delivered to Rokkasho in March 2013. © 2013 Elsevier B.V. All rights reserved.

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