Engineering Validation Activities Research Articles

IFMIF/EVEDA achievements overview

In a fusion reactor, the plasma based on a deuterium-tritium reaction generates high energy neutron flux interacting with the materials of the plasma facing components. In order to study the irradiated behavior of these materials, the International Fusion Materials Irradiation Facility (IFMIF) was conceived to generate these fusion relevant neutrons through d-Li stripping source. IFMIF is presently in its Engineering Validation and Engineering Design Activities (EVEDA) phase under the Broader Approach agreement signed between EURATOM and Japanese Government in 2007. This agreement mandates the IFMIF/EVEDA project to validate the design of the different systems of IFMIF and to produce an integrated engineering design of IFMIF, together with the data necessary for future decisions on its construction and operation. While the Engineering Validation Activity (EVA) of the Lithium Target Facility and the Test Facility was completed by constructing prototypes, the EVA of the Accelerator Facility with the Linear IFMIF Prototype Accelerator (LIPAc) is still on-going at the Rokkasho Fusion Institute, Japan. This paper overviews the achievements in the previous phase ended on 31 March 2020 and the progress in the current phase to complete the commissioning of the LIPAc.

Overview of the IFMIF/EVEDA projectaaIn Memoriam Yoshikazu Okumura who passed away on 6 March 2017.

IFMIF, the International Fusion Materials Irradiation Facility, is presently in its engineering validation and engineering design activities (EVEDA) phase under the Broader Approach Agreement.The engineering design activity (EDA) phase was successfully accomplished within the allocated time.The engineering validation activity (EVA) phase has focused on validating the Accelerator Facility (AF), the Target Facility and the Test Facility (TF) by constructing prototypes. The ELTL at JAEA, Oarai successfully demonstrated the long-term stability of a Li flow under the IFMIF’s nominal operational conditions keeping the specified free-surface fluctuations below ±1 mm in a continuous manner for 25 d. A full-scale prototype of the high flux test module (HFTM) was successfully tested in the HELOKA loop (KIT, Karlsruhe), where it was demonstrated that the irradiation temperature can be set individually and kept uniform. LIPAc, designed and constructed in European labs under the coordination of F4E, presently under installation and commissioning in the Rokkasho Fusion Institute, aims at validating the concept of IFMIF accelerators with a D+ beam of 125 mA continuous wave (CW) and 9 MeV. The commissioning phases of the H+/D+ beams at 100 keV are progressing and should be concluded in 2017; in turn, the commissioning of the 5 MeV beam is due to start during 2017. The D+ beam through the superconducting cavities is expected to be achieved within the Broader Approach Agreement time frame with the superconducting cryomodule being assembled in Rokkasho.The realisation of a fusion-relevant neutron source is a necessary step for the successful development of fusion. The ongoing success of the IFMIF/EVEDA involves ruling out concerns about potential technical showstoppers which were raised in the past. Thus, a situation has emerged where soon steps towards constructing a Li(d,xn) fusion-relevant neutron source could be taken, which is also justified in the light of costs which are marginal to those of a fusion plant.

The design status of the liquid lithium target facility of IFMIF at the end of the engineering design activities

The International Fusion Material Irradiation Facility (IFMIF) is an experimental facility conceived for qualifying and characterizing structural materials for nuclear fusion applications. The Engineering Validation and Engineering Design Activity (EVEDA) is a fundamental step towards the final design. It presented two mandates: the Engineering Validation Activities (EVA), still on-going, and the Engineering Design Activities (EDA) accomplished on schedule in June 2013. Five main facilities are identified in IFMIF, among which the Lithium Target Facility constituted a technological challenge overcome thanks to the success of the main validation challenges impacting the design. The design of the liquid Lithium Target Facility at the end of the EDA phase is here detailed.

The engineering design evolution of IFMIF: From CDR to EDA phase

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.

Technical analysis of an early fusion neutron source based on the enhancement of the IFMIF/EVEDA accelerator prototype

In the framework of the Engineering Design and Engineering Validation Activities for the International Fusion Materials Irradiation Facility (IFMIF/EVEDA), three major prototypes have been designed and are being manufactured, commissioned and operated which are firstly the Accelerator Prototype (LIPAc) at Rokkasho, fully representative of the IFMIF low energy (9MeV) accelerator stage, secondly the EVEDA Lithium Test Loop (ELTL) at Oarai, and thirdly critical components of the High Flux Test Modules to be tested in the helium cooling loop (HELOKA-LP) at Karlsruhe. The present paper analyses possibilities from a technical point of view, for combining, modifying, and enhancing, at limited cost, selected components of the prototypes towards the realisation of an early reduced-flux neutron source, able nonetheless to start the testing of candidate DEMO materials and realising by this a first step towards the construction and operation of a complete IFMIF plant.Various options of deuteron beam parameters, such as energy, current and shape are analysed with respect to their technical challenges and the neutron yield resulting from the nuclear reaction with the Li target. Related requirements for the liquid Li target with respect to jet parameters are evaluated and the neutron mapping in the high flux region is presented underlying an analysis of the available volume for testing reduced activation ferritic martensitic (RAFM) steels at relevant structural damage levels.

Fusion Technology Activities through the Broader Approach IFMIF-EVEDA Project

The International Fusion Materials Irradiation Facility (IFMIF) Engineering Design and Engineering Validation Activities (EVEDA) started in 2007 under the framework of the Broader Approach (BA) Agreement between EU and Japan with the objective of developing a complete engineering design of the IFMIF together with accompanying sub projects to validate the major elements of the technologies essential for the IFMIF Plant. By June 2013, engineering design of IFMIF will be completed by delivering Interim IFMIF Engineering Design Report (IIEDR) with feedback from the validation activities of IFMIF/EVEDA except the Oarai Lithium Loop and Accelerator Prototype validation activities. A present status of the engineering design of the IFMIF and the important outcome of the validation activities already achieved in terms of the confirmation and validation of the design concept chosen are presented.

Progress in IFMIF Engineering Validation and Engineering Design Activities

The International Fusion Materials Irradiation Facility (IFMIF) Engineering Design and Engineering Validation Activities (EVEDA) are being developed in a joint project in the framework of the Broader Approach (BA) Agreement between EU and Japan. This project has now entered into a crucial phase as the engineering design of IFMIF is now being formulated in a series of 3 subsequent phases for delivering an Interim IFMIF Engineering Design Report (IIEDR) by mid of 2013. Content of these phases is explained, including the plant configuration detailing the 5 IFMIF facilities and their systems. Together with the Engineering Design Activities, prototyping sub-projects are pursued in the Engineering Validation Activities which consist of the design, manufacturing and testing of the following prototypical systems: Linear IFMIF Prototype Accelerator (LIPAc), EVEDA Lithium Test Loop (ELTL), and High Flux Test Module (HFTM) with the prototypical helium cooling loop (HELOKA). Highlights are described from recent experiments in the Engineering Validation Activities.

Overview of Materials Research and IFMIF/EVEDA under the Broader Approach Framework

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 blanket-related 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 International 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.

IFMIF/EVEDA: Adjustment of Scope and Recent Technical Achievements

The International Fusion Materials Irradiation Facility (IFMIF) aiming at generating a material database for DEMO and future fusion power plants is commonly understood by the European Union and Japan as one of the pillars toward DEMO, and IFMIF Engineering Design and Engineering Validation Activities (EVEDA) have been conducted since mid 2007 in the framework of the Broader Approach Agreement. So far the main efforts have been focused on validation work to provide information necessary for engineering design. In 2010, the scope of the project was revised to set priority on the validation of an accelerator prototype while extending the duration up to mid 2017, while the other activities will be completed in mid 2013 as the primary plan, and the goal of engineering design has been modified to accomplish the Intermediate Report. In 2011, several outcomes of validation of major components have been achieved: (1) first operation of an ion injector has been conducted, (2) a lithium test loop was constructed and commissioned, and (3) test pieces for fission reactor irradiation have been manufactured. This paper summarizes the status of all activities and expected outcomes of the IFMIF/EVEDA project.

Overview of Materials Research and IFMIF/EVEDA Under the Broader Approach Framework

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 (RD) tasks, mainly on blanket-related materials, are being carried out as the DEMO RD program in the BA to establish key technologies required for the DEMO engineering design. The DEMO RD building was constructed in March 2010, and the installation of research equipment was completed in March 2011. As the BA DEMO RD, 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 film thick at similar to 5 m/s was obtained.

Status of IFMIF EVEDA, One Year After Its Start-Up

The Engineering Design and Engineering Validation Activities (EVEDA) of IFMIF, the International Fusion Materials Irradiation Facility, are started as one of three projects of the Broader Approach Agreement as the collaborative works between Japan and Europe, in June 2007.The main objective of the project is deliver the detailed, complete, and fully integrated engineering design the IFMIF. The designs of key subsystems are validated by executing prototyping or mockup studies. The main outcomes one year after the start of the project are: the design of the prototype accelerator of low-energy part up to 9 MeV with 125 mA continuous wave deuteron beam was updated and optimized to employ the superconducting resonators as the main linac; the purification methods for controlling the erosion/corrosion and radioactive products in the flowing lithium used as the neutron producing target material were examined under the laboratory-scale; and the concept of the irradiation test modules was elaborated further by conducting thermo-mechanical and hydraulic analyses.