Rokkasho, Japan
Rokkasho, Japan

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Kondo H.,Japan Atomic Energy Agency | Furukawa T.,Japan Atomic Energy Agency | Hirakawa Y.,Japan Atomic Energy Agency | Nakamura K.,Japan Atomic Energy Agency | And 17 more authors.
Nuclear Fusion | Year: 2011

The engineering validation and engineering design activity (EVEDA) for the International Fusion Materials Irradiation Facility (IFMIF) is proceeding as one of the ITER broader approach activities. In the concept of the IFMIF, two 40 MeV deuteron beams are injected into a liquid Li stream (Li target) flowing at a velocity of 15 m s-1. The EVEDA Li test loop (ELTL) is aimed at validating the hydraulic stability of the Li target at a velocity up to 20 m s-1 under a vacuum condition of 10-3 Pa as the most important issue. Construction of the ELTL, which is the largest liquid metal loop possessing 5.0 m3 Li for the fusion research ever, was completed in the O-arai Research & Development Center in the Japan Atomic Energy Agency on 22 November 2010. This paper presents the design and fabrication technology of a target assembly called integrated target assembly, in which the Li target is produced by a contraction nozzle along a concave channel. There are two concepts regarding the target assembly: the integrated target assembly and the bayonet target assembly. Both target assemblies are outlined in this paper, and then the newly proposed design of the integrated target assembly for the ELTL and its fabrication technology are given. The integrated target assembly was processed by a five-axis milling machine and the processing accuracy was measured by 3D measurement tools. Finally, methods applied for the validation of the stability of the Li target are introduced in this paper. © 2011 IAEA, Vienna.


Knaster J.,IFMIF EVEDA Project Team | Arbeiter F.,Karlsruhe Institute of Technology | Cara P.,F4E | Favuzza P.,ENEA | And 10 more authors.
Nuclear Fusion | Year: 2013

The Engineering Validation and Engineering Design Activities (EVEDA) for the International Fusion Materials Irradiation Facility (IFMIF), an international collaboration under the Broader Approach Agreement between Japan Government and EURATOM, aims at allowing a rapid construction phase of IFMIF in due time with an understanding of the cost involved. The three main facilities of IFMIF (1) the Accelerator Facility, (2) the Target Facility and (3) the Test Facility are the subject of validation activities that include the construction of either full scale prototypes or smartly devised scaled down facilities that will allow a straightforward extrapolation to IFMIF needs. By July 2013, the engineering design activities of IFMIF matured with the delivery of an Intermediate IFMIF Engineering Design Report (IIEDR) supported by experimental results. The installation of a Linac of 1.125 MW (125 mA and 9 MeV) of deuterons started in March 2013 in Rokkasho (Japan). The world's largest liquid Li test loop is running in Oarai (Japan) with an ambitious experimental programme for the years ahead. A full scale high flux test module that will house ∼1000 small specimens developed jointly in Europe and Japan for the Fusion programme has been constructed by KIT (Karlsruhe) together with its He gas cooling loop. A full scale medium flux test module to carry out on-line creep measurement has been validated by CRPP (Villigen). © 2013 IAEA, Vienna.


Pruneri G.,IFMIF EVEDA | Ibarra A.,CIEMAT | Heidinger R.,F4E | Knaster J.,IFMIF EVEDA Project Team | Sugimoto M.,Japan Atomic Energy Agency
Fusion Engineering and Design | Year: 2016

In 2013, the IFMIF, the International Fusion Material Irradiation Facility, presently in its Engineering Validation and Engineering Design Activities (EVEDA) phase, framed by the Broader Approach Agreement between Japan and EURATOM, accomplished in 2013 its mandate to provide the engineering design of the plant on schedule [1]. The IFMIF aims to qualify and characterize materials that are capable of withstanding the intense neutron flux originated in D-T reactions of future fusion reactors due to a neutron flux with a broad peak at 14 MeV, which is able to provide >20 dpa/fpy on small specimens in this EVEDA phase. The successful operation of such a challenging plant demands a careful assessment of the Conventional Facilities (CF), which have adequate redundancies to allow for the target plant availability [2]. The present paper addresses the design proposed in the IFMIF Intermediate Engineering Design Report regarding the CF, particularly the IFMIF's Nuclear and Industrial HVAC design. A preliminary feasibility study, including the initial configuration, calculations and reliability/availability analysis, were performed. The nuclear HVAC design was developed progressively; first, by establishing a conceptual design, starting from the system functional description, followed by the identification of the corresponding interfacing systems and their technical requirements. Once the technical requirements were identified, safety zones were identified based on the radiation classification, frequency dose and parameter of Derivate Air Contamination (DAC). The zone color was determined to match the room's radiation classification. The system design was further developed by defining and creating a Block Diagram with basic and additional information, eventually resulting in a Process Flow Diagram concurrent with the equipment layout definition. Subsequently, we studied and developed the various Piping & instrumentation diagrams (P&ID's), air duct layout and equipment list for different air handling units, air ducting as well as a layout plan of the equipment piping, which was eventually integrated into the 3D model of the building and coordinated with others subsystems of the IFMIF. © 2015 Elsevier B.V. All rights reserved.


Pruneri G.,IFMIF EVEDA | Ibarra A.,CIEMAT | Heidinger R.,F4E | Knaster J.,IFMIF EVEDA Project Team | Sugimotoc M.,Japan Atomic Energy Agency
Proceedings - Symposium on Fusion Engineering | Year: 2016

This IFMIF, the International Fusion Material Irradiation Facility, presently in its Engineering Validation and Engineering Design Activities (EVEDA) phase, framed by the Broader Approach Agreement between Japan and EURATOM, has accomplished in 2013, on schedule, its mandate on the engineering design of the plant [1]. © 2015 IEEE.


Wakai E.,Japan Atomic Energy Agency | Kikuchi T.,Japan Atomic Energy Agency | Yokomine T.,Kyoto University | Yamamoto M.,IFMIF EVEDA Project Team | And 2 more authors.
Fusion Science and Technology | Year: 2012

International Fusion Materials Irradiation Facility/ Engineering Validation and Engineering Design Activity (IFMIF/EVEDA) was started in 2007 in the joint program between Japan (JA) and the European Union (EU). IFMIF has mainly three facilities, i.e., test facility, lithium target facility, and accelerator facility. In this program, there are three subjects of the JA team in the test facility such as the design of the post irradiation examination (PIE) facility, the design and validation of the high flux test module, and the evaluation of the small size specimen technique. In this paper, the test matrix of the IFMIF was evaluated. All test matrixes depend on the requirement of a database preparation schedule and the irradiation volume of irradiation modules such as high flux test module (HFTM), medium flux test module (MFTM) and low flux test module (LFTM), but the engineering design of HFTM is mainly proceeding. Accordingly, the lists of the experiments of small size specimens set in the HFTM to be performed in the PIE laboratories have been carefully analyzed. In the design of HFTM, two types of HFTM are proposed for RAFM steel irradiation by the EU KIT team and for the advanced materials by the JA team, and the difference was summarized.


Kogawara T.,Japan Atomic Energy Agency | Wakai E.,Japan Atomic Energy Agency | Kikuchi T.,Japan Atomic Energy Agency | Yamamoto M.,IFMIF EVEDA Project Team | Molla J.,IFMIF EVEDA Project Team
Fusion Engineering and Design | Year: 2011

The international fusion materials irradiation facility (IFMIF) is an accelerator-based intense 14 MeV neutron source for testing fusion reactor materials. Under broader approach (BA) agreement between EURATOM and Japan, the engineering validation and engineering design activity (EVEDA) were started from 2007. The IFMIF needs the post irradiation examination (PIE) facilities to generate a materials irradiation database for the design and licensing of fusion DEMO reactors. In this study we examined and discussed about the safety such as remote handling, hot cell design, and the equipments and apparatus of hot cells, and we summarized a basic design guideline for the preliminary engineering design of the PIE facilities. © 2011 Elsevier B.V. All rights reserved.


Kondo H.,Japan Atomic Energy Agency | Kanemura T.,Japan Atomic Energy Agency | Furukawa T.,Japan Atomic Energy Agency | Hirakawa Y.,Japan Atomic Energy Agency | And 2 more authors.
Fusion Engineering and Design | Year: 2015

The International Fusion Materials Irradiation Facility (IFMIF) is an accelerator-based D+-Li neutron source in which two 40-MeV-D+ beams with a total current of 250mA are injected into a liquid Li stream flowing at 15m/s (Li target). The EVEDA Li test loop (ELTL), which simulates the hydraulic conditions of the Li target and a part of the purification system envisaged in IFMIF, is a main activity in the Li target facility of the IFMIF/EVEDA project and has been implemented under the Broader Approach (BA) agreement since 2007. The key issues to be validated in ELTL were as follows: (1) validation of the Li target, Li target diagnostics, and cold trap (CT), and (2) validation of long-term operation. This study describes the stability of the Li target in an integrated long-term operation run of the entire system as a demonstration of the IFMIF Li target facility. The Li target was continuously operated with the CT for 571h, and its stability was evaluated periodically using a high-precision Li target diagnostic. Therefore, the Li target essentially satisfied the stability requirement of <±1mm throughout the continuous operation. © 2015 Elsevier B.V.


Kondo H.,Japan Atomic Energy Agency | Kanemura T.,Japan Atomic Energy Agency | Furukawa T.,Japan Atomic Energy Agency | Hirakawa Y.,Japan Atomic Energy Agency | And 2 more authors.
Fusion Engineering and Design | Year: 2014

Engineering Validation and Engineering Design Activities (EVEDA) for the International Fusion Materials Irradiation Facility (IFMIF) have been carried out under the "Broader Approach" (BA) agreement. As a major activity for the Li target facility, the EVEDA Li test loop (ELTL) was constructed at the Japan Atomic Energy Agency's Oarai site to validate the hydraulic conditions of the IFMIF Li target. This paper presents the first operational results of the Li target in the ELTL. A series of tests were performed to check the operational performance of the Li target. The conclusions are as follows: (1) the start-up procedure of the Li target was examined and consequently achieved the Li target and (2) the Li target whose velocity was 20 m/s under pressurized and vacuum conditions was observed by image devices and confirmed to be stable. © 2014 Elsevier B.V.


Gobin R.,CEA Saclay Nuclear Research Center | Bogard D.,CEA Saclay Nuclear Research Center | Cara P.,Fusion for Energy | Chauvin N.,CEA Saclay Nuclear Research Center | And 8 more authors.
Review of Scientific Instruments | Year: 2014

In the framework of the ITER broader approach, the International Fusion Materials Irradiation Facility (IFMIF) deuteron accelerator (2 × 125 mA at 40 MeV) is an irradiation tool dedicated to high neutron flux production for future nuclear plant material studies. During the validation phase, the Linear IFMIF Prototype Accelerator (LIPAc) machine will be tested on the Rokkasho site in Japan. This demonstrator aims to produce 125 mA/9 MeV deuteron beam. Involved in the LIPAc project for several years, specialists from CEA/Saclay designed the injector based on a SILHI type ECR source operating at 2.45 GHz and a 2 solenoid low energy beam line to produce such high intensity beam. The whole injector, equipped with its dedicated diagnostics, has been then installed and tested on the Saclay site. Before shipment from Europe to Japan, acceptance tests have been performed in November 2012 with 100 keV deuteron beam and intensity as high as 140 mA in continuous and pulsed mode. In this paper, the emittance measurements done for different duty cycles and different beam intensities will be presented as well as beam species fraction analysis. Then the reinstallation in Japan and commissioning plan on site will be reported. © 2013 AIP Publishing LLC.


Perez M.,IFMIF EVEDA Project Team
Fusion Engineering and Design | Year: 2015

The International Fusion Materials Irradiation Facility (IFMIF), presently in its Engineering Design and Engineering Validation Activities (EVEDA) phase, started in 2007 under the framework of the Broader Approach (BA) Agreement between Japanese Government and EURATOM. The mandate assigned was to develop an integrated engineering design of IFMIF together with accompanying sub-projects to validate the major technological challenges that included the construction of either full scale prototypes or cleverly devised scaled down facilities, which are essential to reliably face the construction of IFMIF on schedule and cost. The Engineering Design Activities were accomplished on-schedule with the release of its "Intermediate Engineering Design Report (IIEDR)" in June 2013 compliant with our mandate. This paper highlights the design improvements implemented from the previous Conceptual Design Phase. © 2015 Elsevier B.V.

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