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International Fusion Materials Irradiation Facility

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The International Fusion Materials Irradiation Facility, also known as IFMIF, is a projected material testing facility in which candidate materials for the use in an energy producing fusion reactor can be fully qualified. IFMIF will be an accelerator-driven neutron source producing a high intensity fast neutron flux with a spectrum similar to that expected at the first wall of a fusion reactor using a deuterium-lithium nuclear reaction. The IFMIF project was started in 1994 as an international scientific research program, carried out by Japan, the European Union, the United States, and Russia, and managed by the International Energy Agency. Since 2007, it has been pursued by Japan and the European Union under the Broader Approach Agreement in the field of fusion energy research, through the IFMIF/EVEDA project, which conducts engineering validation and engineering design activities for IFMIF.[1][2] The construction of IFMIF is recommended in the European Roadmap for Research Infrastructures Report, which was published by the European Strategy Forum on Research Infrastructures (ESFRI).[3]

IFMIF
A schematic representation of the target area of the International Fusion Material Irradiation Facility (IFMIF). A small target area is irradiated by a pair of deuteron beams to study the effects of intense neutron flux (produced by the interaction of deuterons with a stream of lithium) on materials.

Background

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The deuterium-tritium fusion reaction generates mono-energetic neutrons with an energy of 14.1 MeV. In fusion power plants, neutrons will be present at fluxes in the order of 1018 m−2s−1 and will interact with the material structures of the reactor by which their spectrum will be broadened and softened.[citation needed] A fusion relevant neutron source is an indispensable step towards the successful development of fusion energy.[4] Safe design, construction and licensing of a fusion power facility by the corresponding Nuclear Regulatory agency will require data on the plasma-facing materials degradation under neutron irradiation during the life-time of a fusion reactor. The main source of materials degradation is structural damage which is typically quantified in terms of displacements per atom (dpa).[5] Whereas in the currently constructed large fusion experiment, ITER, structural damage in the reactor steels will not exceed 2 dpa at the end of its operational life, damage creation in a fusion power plant is expected to amount to 15 dpa per year of operation.[6]

None of the commonly available neutron sources are adequate for fusion materials testing for various reasons. The accumulation of gas in the material microstructure is intimately related to the energy of the colliding neutrons. Due to the sensitivity of materials to the specificities in the irradiation conditions, such as the α-particle generation/dpa ratio at damage levels above 15 dpa per year of operation under temperature controlled conditions, material tests require the neutron source to be comparable to a fusion reactor environment.

In steels, the 54Fe(n,α)51Cr and 54Fe(n,p)54Mn reactions are responsible for most of the protons and α-particles produced, and these have an incident neutron energy threshold at 0.9 MeV and 2.9 MeV respectively.[7][8] Therefore, conventional fast fission reactors, which produce neutrons with an average energy around 1-2 MeV, cannot adequately match the testing requirements for fusion materials. In fact the leading factor for embrittlement, the generation of α-particles by transmutation, is far from realistic conditions (actually around 0.3 appm He/dpa).[9] Spallation neutron sources provide a wide spectrum of energies up to the order of hundreds of MeV leading to potentially different defect structures, and generating light transmuted nuclei that intrinsically affect the targeted properties of the alloy. Ion implantation facilities offer insufficient irradiation volume (maximum values of a few hundreds µm layer thickness) for standardized mechanical property tests. Also the low elastic scattering cross section for light ions makes damage levels above 10 dpa impractical.[10]

In 1947, Robert Serber demonstrated theoretically the possibility of producing high energy neutrons by a process in which high energy deuterons are stripped of their proton when hitting a target, while the neutron continues on its way.[11] In the 1970s, the first designs for high energy neutron sources using this stripping reaction were developed in the USA.[12][13] In the 1980s, the rapid advances in high-current linear accelerator technology led to the design of several accelerator-driven neutron sources for satisfying the requirements of a high-flux high-volume international fusion materials testing facility.[14][15] The Fusion Materials Irradiation Test (FMIT) facility based on a deuterium-lithium neutron source was proposed for fusion materials and technology testing.[16][17][18][19]

The deuterium-lithium reaction exploited for IFMIF is able to provide an adequate fusion neutron spectrum as shown by the comparison of IFMIF with other available neutron sources.[20][21][22][23] In an experiment with 40 MeV deuterons from a cyclotron impinging on lithium, the neutron spectrum and the radioactivity production in the lithium were measured, and sufficient agreement with calculated estimates was found.[24]

Description

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IFMIF will consist of five major systems: an accelerator facility, a Li target facility, a test facility, a post-irradiation examination (PIE) facility and a conventional facility.[25][26][27] The whole plant must comply with international nuclear facility regulations. The energy of the beam (40 MeV) and the current of the parallel accelerators (2 x 125 mA) have been tuned to maximize the neutron flux (1018 m−2 s−1) while creating irradiation conditions comparable to those in the first wall of a fusion reactor. Damage rates higher than 20 dpa per year of operation could be reached in a volume of 0.5 L of its High Flux Test Module that can accommodate around 1000 small test specimens.[28] The small specimen testing techniques developed aim at full mechanical characterization (fatigue, fracture toughness, crack growth rate, creep and tensile stress) of candidate materials, and allow, besides a scientific understanding of fusion neutron induced degradation phenomena, the creation of the major elements of a fusion materials database suited for designing, licensing and reliably operating future fusion reactors. The main expected contributions of IFMIF to the nuclear fusion community are to:[29]

  1. provide data for the engineering design for DEMO,
  2. provide information to define performance limits of materials,
  3. contribute to the completion and validation of existing databases,
  4. contribute to the selection or optimization of different alternative fusion materials,
  5. validate the fundamental understanding of the radiation response of materials including benchmarking of irradiation effects modelling at length-scales and time-scales relevant for engineering application,
  6. tests blanket concept and functional materials prior to or complementary to ITER test blanket module testing.

IFMIF Intermediate Engineering Design

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The engineering design of the IFMIF plant is intimately linked with the validation activities and was conducted during the first phase of the so-called IFMIF Engineering Validation and Engineering Design Activities project (IFMIF/EVEDA). The IFMIF Intermediate Engineering Design Report was established in June 2013[26] and adopted by the stakeholders in December 2013. The IFMIF Intermediate Engineering Design defines the major systems in outline.

Accelerator facility (LiPac)

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The two accelerator CW deuteron beams of 5 MW each impinge in an overlapping manner at an angle of ±9° with a footprint of 200 mm x 50 mm and a steady time profile on the liquid Li jet, with the Bragg peak absorption region at about 20 mm depth.

Target facility

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The target facility, which holds the inventory of about 10 m3 of Li, forms and conditions the beam target. The Li screen fulfills two main functions: to react with the deuterons to generate a stable neutron flux in the forward direction and to dissipate the beam power in a continuous manner. The flowing Li (15 m/s; 250 °C) is shaped and accelerated in the proximity of the beam interaction region by a two-stage reducer nozzle forming a concave jet of 25 mm thickness with a minimum radius of curvature of 250 mm in the beam footprint area. The resulting centrifugal pressure raises the boiling point of the flowing Li and thus ensures a stable liquid phase. The beam power absorbed by the Li is evacuated by the heat removal system and the lithium is cooled to 250 °C by a serial of heat exchangers. The control of impurities, essential for the quality of the liquid screen, will be done through a tailored design of cold and hot trap systems, and purities of Li during operation better than 99.9% are expected. On-line monitoring of impurities will detect impurity levels over 50 ppm. Based on numerical analyses carried out in the last three decades, the beam-target interaction is not expected to have a critical impact on jet stability.[30]

Test facility

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The Test Facility will provide high, medium and low flux regions ranging from ›20 dpa/full power year (fpy) to ‹1 dpa /fpy with increasingly available irradiating volumes of 0.5 L, 6 L and 8 L that will house different metallic and non-metallic materials potentially subjected to the different irradiation levels in a power plant. More specifically, in the high flux region, fluences of 50 dpa in ‹3.5 years in a region of 0.5 L, together with power plant relevant fluences of ›120 dpa in ‹5 years in a region of 0.2 L, are planned. The high flux region will accommodate about 1000 small specimens assembled in 12 individual capsules independently temperature controlled that will allow not only mechanical characterization of the candidate structural materials tested, but also an understanding of the influence in their degradation with material temperature during irradiation.

Post-irradiation facility

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The Post-Irradiation Examination facility, an essential part of IFMIF, is hosted in a wing of the main building in order to minimize the handling operations of irradiated specimens.[31] It will not only allow testing irradiated specimens out of the different testing modules, but also characterizing metallographically the specimens after destructive testing.

IFMIF Engineering Validation Activities

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Fig. 7. LEBT image of the deuteron injector of the Linear IFMIF Accelerator Prototype Accelerator (LIPAc) under installation in Rokkasho, Japan.

To minimise the risks in constructing IFMIF, the IFMIF/EVEDA project has constructed or is constructing prototypes of those systems which face the main technological challenges that have been identified throughout the years of international cooperation in establishing a fusion relevant neutron source,[17][32] namely 1) the Accelerator Facility, 2) the Target Facility, and 3) the Test Facility.[33][34] An Accelerator Prototype (LIPAc), designed and constructed mainly in European laboratories CEA, CIEMAT, INFN and SCK•CEN under the coordination of F4E and under installation at Rokkasho at JAEA premises, is identical to the IFMIF accelerator design up to its first superconductive accelerating stage (9 MeV energy, 125 mA of D+ in Continuous Wave (CW) current), and will become operational in June 2017.[35] A Li Test Loop (ELTL) at the Oarai premises of JAEA, integrating all elements of the IFMIF Li target facility, was commissioned in February 2011,[36] and is complemented by corrosion experiments performed at a Li loop (Lifus6) in ENEA, Brasimone.[37] A High Flux Test Module (two different designs accommodating either Reduced Activation Ferritic-Martensitic steels (RAFM) or SiC),[38][39][40] with a prototype of the capsules housing the small specimens were irradiated in the BR2 research reactor of SCK•CEN [41] and tested in the cooling helium loop HELOKA of the Karlsruhe Institute of Technology, Karlsruhe,[42] together with a Creep Fatigue Test Module [43] manufactured and tested at full scale at the Paul Scherrer Institute. Detailed specific information on the ongoing validation activities is being made available in related publications.[44][45][46][47][48][49][50]

See also

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  • ITER (International Thermonuclear Experimental Reactor, and Latin for "the way")

References

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  1. ^ Fusion For Energy. "Understanding Fusion – Broader Approach". fusionforenergy.europa.eu. Archived from the original on 2016-06-13. Retrieved 2016-07-06.
  2. ^ Knaster, J.; Arbeiter, F.; Cara, P.; Chel, S.; Facco, A.; Heidinger, R.; Ibarra, A.; Kasugai, A.; Kondo, H. (2016). "IFMIF, the European–Japanese efforts under the Broader Approach agreement towards a Li(d,xn) neutron source: Current status and future options". Nuclear Materials and Energy. 9: 46–54. Bibcode:2016NMEne...9...46K. doi:10.1016/j.nme.2016.04.012.
  3. ^ "Roadmap – ESFRI – Research Infrastructures – Research – European Commission". ec.europa.eu. Retrieved 2016-07-06.
  4. ^ "Fusion Electricity A roadmap to the realisation of fusion energy" (PDF). EFDA. 2012. Archived from the original (PDF) on 2017-05-30. Retrieved 2016-07-06.
  5. ^ Norgett, M. J.; Robinson, M. T.; Torrens, I. M. (1975). "A proposed method of calculating displacement dose rates". Nuclear Engineering and Design. 33 (1): 50–54. Bibcode:1975NuEnD..33...50N. doi:10.1016/0029-5493(75)90035-7.
  6. ^ Gilbert, M.R.; Dudarev, S.L.; Zheng, S.; Packer, L.W.; Sublet, J.-Ch. (2012). "An integrated model for materials in a fusion power plant: transmutation, gas production, and helium embrittlement under neutron irradiation" (PDF). Nuclear Fusion. 52 (8): 083019. Bibcode:2012NucFu..52h3019G. doi:10.1088/0029-5515/52/8/083019. S2CID 59044552.
  7. ^ Yiğit, M.; Tel, E.; Tanır, G. (2012). "Calculations of (n,α) Cross Sections on Some Structural Fusion Materials for Fusion Reactor Technology". Journal of Fusion Energy. 32 (3): 336–343. Bibcode:2013JFuE...32..336Y. doi:10.1007/s10894-012-9574-9. ISSN 0164-0313. S2CID 122884246.
  8. ^ Kaplan, A.; Özdoğan, H.; Aydın, A.; Tel, E. (2012). "Deuteron-Induced Cross Section Calculations of Some Structural Fusion Materials". Journal of Fusion Energy. 32 (1): 97–102. Bibcode:2013JFuE...32...97K. doi:10.1007/s10894-012-9532-6. ISSN 0164-0313. S2CID 120970285.
  9. ^ Stoller, Roger E (2000). "The role of cascade energy and temperature in primary defect formation in iron". Journal of Nuclear Materials. 276 (1–3): 22–32. Bibcode:2000JNuM..276...22S. doi:10.1016/S0022-3115(99)00204-4.
  10. ^ Mazey, D. J. (1990). "Fundamental aspects of high-energy ion-beam simulation techniques and their relevance to fusion materials studies". Journal of Nuclear Materials. 174 (2): 196–209. Bibcode:1990JNuM..174..196M. doi:10.1016/0022-3115(90)90234-E.
  11. ^ Serber, Robert (1947). "The Production of High Energy Neutrons by Stripping". Physical Review. 72 (11): 1008–1016. Bibcode:1947PhRv...72.1008S. doi:10.1103/PhysRev.72.1008. hdl:2027/mdp.39015074120836.
  12. ^ Grand, P.; Batchelor, K.; Blewett, J. P.; Goland, A.; Gurinsky, D.; Kukkonen, J.; Jr, C. L. Snead (1976). "An Intense Li(d,n) Neutron Radiation Test Facility for Controlled Thermonuclear Reactor Materials Testing". Nuclear Technology. 29 (3): 327–336. Bibcode:1976NucTe..29..327G. doi:10.13182/NT76-A31598. ISSN 0029-5450.
  13. ^ Grand, P.; Goland, A. N. (1977). "An intense neutron source based upon the deuteron-stripping reaction". Nuclear Instruments and Methods. 145 (1): 49–76. Bibcode:1977NucIM.145...49G. doi:10.1016/0029-554X(77)90557-2. ISSN 0029-554X.
  14. ^ Lawrence, G. P.; Bhatia, T. S.; Blind, B.; Guy, F. W.; Krakowski, R. A.; Neuschaefer, G. H.; Schnurr, N. M.; Schriber, S. O.; Varsamis, G. L. (1989). "High-performance deuterium-lithium neutron source for fusion materials and technology testing". Proceedings of the 1989 IEEE Particle Accelerator Conference, . 'Accelerator Science and Technology. Vol. 1. pp. 684–687. Bibcode:1989pac..conf..684L. doi:10.1109/PAC.1989.73222. S2CID 111079257.
  15. ^ Lawrence, George P. (1991). "Accelerator-driven neutron sources for fusion materials testing". Journal of Fusion Energy. 10 (4): 319–326. Bibcode:1991JFuE...10..319L. doi:10.1007/BF01052133. ISSN 0164-0313. S2CID 119831986.
  16. ^ Hagan, J. W.; Opperman, E. K.; Trego, A. L. (1984). "The fusion materials irradiation test (FMIT) facility". Journal of Nuclear Materials. 123 (1): 958–964. Bibcode:1984JNuM..123..958H. doi:10.1016/0022-3115(84)90201-0.
  17. ^ a b Pottmeyer, E. W. (1979). "The fusion materials irradiation test facility at Hanford". Journal of Nuclear Materials. 85: 463–465. Bibcode:1979JNuM...85..463P. doi:10.1016/0022-3115(79)90531-2.
  18. ^ Brackenbury, P. J.; Bazinet, G. D.; Miller, W. C. (1983). "Fusion Materials Irradiation Test (FMIT) facility lithium system: a design and development status". Hanford Engineering Development Lab. {{cite journal}}: Cite journal requires |journal= (help)
  19. ^ Mann, F. M.; Schmittroth, F.; Carter, L. L. (1981). "Neutron environment in d + Li facilities". Journal of Nuclear Materials. 104: 1439–1443. Bibcode:1981JNuM..104.1439M. doi:10.1016/0022-3115(82)90802-9. ISSN 0022-3115.
  20. ^ Lawrence, G. P.; Varsamis, G. L.; Bhatia, T. S.; Blind, B.; Guy, F. W.; Krakowski, R. A.; Neuschaefer, G. H.; Schnurr, N. M.; Schriber, S. O. (1989-12-01). "A high-flux accelerator-based neutron source for fusion technology and materials testing". Journal of Fusion Energy. 8 (3–4): 201–227. Bibcode:1989JFuE....8..201L. doi:10.1007/BF01051650. ISSN 0164-0313. S2CID 110414439.
  21. ^ "IFMIF/EVEDA – the future on fusion materials".
  22. ^ Zinkle, Steven J.; Möslang, Anton (2013). "Evaluation of irradiation facility options for fusion materials research and development". Fusion Engineering and Design. Proceedings of the 27th Symposium On Fusion Technology (SOFT-27); Liège, Belgium, September 24–28, 2012. 88 (6–8): 472–482. Bibcode:2013FusED..88..472Z. doi:10.1016/j.fusengdes.2013.02.081.
  23. ^ Vladimirov, P; Möslang, A (2004). "Comparison of material irradiation conditions for fusion, spallation, stripping and fission neutron sources". Journal of Nuclear Materials. Proceedings of the 11th International Conference on Fusion Reactor Materials (ICFRM-11). 329–333, Part A: 233–237. Bibcode:2004JNuM..329..233V. doi:10.1016/j.jnucmat.2004.04.030.
  24. ^ U. v. Möllendorff, F. Maekawa, H. Giese, H. Feuerstein: A nuclear simulation experiment for the International Fusion Materials Irradiation Facility (IFMIF). Forschungszentrum Karlsruhe, Report FZKA-6764 (2002) Download Archived 2014-02-27 at the Wayback Machine
  25. ^ IFMIF International Team, IFMIF Comprehensive Design Report, IEA on-line publication
  26. ^ a b IFMIF Intermediate Engineering Design Report: IFMIF Plant Design Description document (not available on-line; delivered upon request at ifmif-eveda@ifmif.org)
  27. ^ Möslang, A. (1998). "IFMIF – International Fusion Materials Irradiation Facility Conceptual Design Evaluation Report" (PDF). Annual Report ... / Institute for Nuclear Waste Disposal. Forschungszentrum Karlsruhe. ISSN 0947-8620. Archived from the original (PDF) on 2016-08-17. Retrieved 2016-07-06.
  28. ^ Garin, P.; Diegele, E.; Heidinger, R.; Ibarra, A.; Jitsukawa, S.; Kimura, H.; Möslang, A.; Muroga, T.; Nishitani, T. (2011). "IFMIF specifications from the users point of view". Fusion Engineering and Design. Proceedings of the 26th Symposium of Fusion Technology (SOFT-26). 86 (6–8): 611–614. Bibcode:2011FusED..86..611G. doi:10.1016/j.fusengdes.2011.01.109.
  29. ^ A. Moeslang, Development of a Reference Test Matrix for IFMIF Test Modules, Final report on the EFDA Task TW4-TTMI-003D4, (2006)
  30. ^ Knaster, J.; Bernardi, D.; García, A.; Groeschel, F.; Heidinger, R.; Ida, M.; Ibarra, A.; Micchiche, G.; Nitti, S. (2014-10-01). "Assessment of the beam–target interaction of IFMIF: A state of the art". Fusion Engineering and Design. Proceedings of the 11th International Symposium on Fusion Nuclear Technology-11 (ISFNT-11) Barcelona, Spain, 15–20 September 2013. 89 (7–8): 1709–1716. Bibcode:2014FusED..89.1709K. doi:10.1016/j.fusengdes.2014.01.011.
  31. ^ Wakai, Eiichi; Kogawara, Takafumi; Kikuchi, Takayuki (2010). "Design status of post irradiation examination facilities in IFMIF/EVEDA" (PDF). Journal of Plasma and Fusion Research SERIES. 9: 242–247. ISSN 1883-9630.
  32. ^ Kondo, T.; Ohno, H.; Mizumoto, M.; Odera, M. (1989). "Selective energy neutron source based on the D-Li stripping reaction". Journal of Fusion Energy. 8 (3–4): 229–235. Bibcode:1989JFuE....8..229K. doi:10.1007/BF01051651. ISSN 0164-0313. S2CID 120175278.
  33. ^ Garin, Pascal; Sugimoto, Masayoshi (2009). "Main baseline of IFMIF/EVEDA project". Fusion Engineering and Design. Proceedings of the 25th Symposium on Fusion Technology(SOFT-25). 84 (2–6): 259–264. Bibcode:2009FusED..84..259G. doi:10.1016/j.fusengdes.2008.12.040.
  34. ^ Knaster, J.; Arbeiter, F.; Cara, P.; Favuzza, P.; Furukawa, T.; Groeschel, F.; Heidinger, R.; Ibarra, A.; Matsumoto, H. (2013). "IFMIF: overview of the validation activities" (PDF). Nuclear Fusion. 53 (11): 116001. Bibcode:2013NucFu..53k6001K. doi:10.1088/0029-5515/53/11/116001. S2CID 55145355.[permanent dead link‍]
  35. ^ Cara, P.; Gex, D.; Heidinger, R.; Beauvais, P.-Y.; Bredy, P.; Chel, S.; Desmons, M.; Gastinel, P.; Gobin, R. (2012). "Overview and Status of the Linear IFMIF Prototype Accelerator" (PDF). Proc. Of 24th IAEA Fusion Energy Conference.
  36. ^ Kondo, H.; Furukawa, T.; Hirakawa, Y.; Iuchi, H.; Kanemura, T.; Ida, M.; Watanabe, K.; Horiike, H.; Yamaoka, N. (2012). "Completion of IFMIF/EVEDA lithium test loop construction". Fusion Engineering and Design. Tenth International Symposium on Fusion Nuclear Technology (ISFNT-10). 87 (5–6): 418–422. Bibcode:2012FusED..87..418K. doi:10.1016/j.fusengdes.2011.11.011.
  37. ^ Aiello, A.; Tincani, A.; Favuzza, P.; Nitti, F. S.; Sansone, L.; Miccichè, G.; Muzzarelli, M.; Fasano, G.; Agostini, P. (2013). "Lifus (lithium for fusion) 6 loop design and construction". Fusion Engineering and Design. Proceedings of the 27th Symposium On Fusion Technology (SOFT-27); Liège, Belgium, September 24–28, 2012. 88 (6–8): 769–773. Bibcode:2013FusED..88..769A. doi:10.1016/j.fusengdes.2013.02.129.
  38. ^ Klueh, R. L.; Bloom, E. E. (1985). "The development of ferritic steels for fast induced-radioactivity decay for fusion reactor applications". Nuclear Engineering and Design. Fusion. 2 (3): 383–389. doi:10.1016/0167-899X(85)90026-6.
  39. ^ Arbeiter, Frederik; Chen, Yuming; Dolensky, Bernhard; Freund, Jana; Heupel, Tobias; Klein, Christine; Scheel, Nicola; Schlindwein, Georg (2012). "Overview of results of the first phase of validation activities for the IFMIF High Flux Test Module". Fusion Engineering and Design. Tenth International Symposium on Fusion Nuclear Technology (ISFNT-10). 87 (7–8): 1506–1509. Bibcode:2012FusED..87.1506A. doi:10.1016/j.fusengdes.2012.03.045.
  40. ^ Abe, T.; Kishimoto, H.; Nakazato, N.; Park, J. S.; Jung, H. C.; Kohno, Y.; Kohyama, A. (2012). "SiC/SiC composite heater for IFMIF". Fusion Engineering and Design. Tenth International Symposium on Fusion Nuclear Technology (ISFNT-10). 87 (7–8): 1258–1260. Bibcode:2012FusED..87.1258A. doi:10.1016/j.fusengdes.2012.02.124.
  41. ^ Gouat, P.; Jacquet, P.; Van Houdt, B.; Brichard, B.; Leysen, W.; Massaut, V. (2011). "Present status of the Belgian contribution to the validation and design activities for the development of the IFMIF radiation-testing modules". Fusion Engineering and Design. Proceedings of the 26th Symposium of Fusion Technology (SOFT-26). 86 (6–8): 627–631. Bibcode:2011FusED..86..627G. doi:10.1016/j.fusengdes.2011.04.012.
  42. ^ Schlindwein, Georg; Arbeiter, Frederik; Freund, Jana (2012). "Start-up phase of the HELOKA-LP low pressure helium test facility for IFMIF irradiation modules". Fusion Engineering and Design. Tenth International Symposium on Fusion Nuclear Technology (ISFNT-10). 87 (5–6): 737–741. Bibcode:2012FusED..87..737S. doi:10.1016/j.fusengdes.2012.02.020.
  43. ^ Vladimirov, P.; Möslang, A.; Marmy, P. (2008). "Nuclear responses in IFMIF creep-fatigue testing machine". Fusion Engineering and Design. Proceedings of the Eight International Symposium of Fusion Nuclear TechnologyISFNT-8 SI. 83 (10–12): 1548–1552. Bibcode:2008FusED..83.1548V. doi:10.1016/j.fusengdes.2008.06.019.
  44. ^ Knaster, J.; Arbeiter, F.; Cara, P.; Favuzza, P.; Furukawa, T.; Groeschel, F.; Heidinger, R.; Ibarra, A.; Matsumoto, H. (2013). "IFMIF: overview of the validation activities" (PDF). Nuclear Fusion. 53 (11): 116001. Bibcode:2013NucFu..53k6001K. doi:10.1088/0029-5515/53/11/116001. S2CID 55145355.[permanent dead link‍]
  45. ^ Pérez, M.; Heidinger, R.; Knaster, J.; Sugimoto, M. (2013). "IFMIF: Steps toward realization". 2013 IEEE 25th Symposium on Fusion Engineering (SOFE). pp. 1–8. doi:10.1109/SOFE.2013.6635327. ISBN 978-1-4799-0171-5. S2CID 32440078.
  46. ^ Sugimoto, M.; Imai, T.; Okumura, Y.; Nakayama, K.; Suzuki, S.; Saigusa, M. (2002). "Issues to be verified by IFMIF prototype accelerator for engineering validation". Journal of Nuclear Materials. 307–311, Part 2: 1691–1695. Bibcode:2002JNuM..307.1691S. doi:10.1016/S0022-3115(02)01023-1.
  47. ^ Knaster, Juan; Cara, Philippe; Mosnier, Alban; Chel, Stéphane; Molla, Joaquin; Suzuki, Hiromitsu (2013). "Installation and Commissioning of the 1.1 MW Deuteron Prototype Linac for IFMIF". Proc. The 4th International Particle Accelerator Conference (IPAC 2013): TUOAB101.
  48. ^ Gobin, R.; Bogard, D.; Cara, P.; Chauvin, N.; Chel, S.; Delferrière, O.; Harrault, F.; Mattei, P.; Mosnier, A. (2014). "International Fusion Materials Irradiation Facility injector acceptance tests at CEA/Saclay: 140 mA/100 keV deuteron beam characterization". Review of Scientific Instruments. 85 (2): 02A918. Bibcode:2014RScI...85bA918G. doi:10.1063/1.4827678. ISSN 1089-7623. PMID 24593497.
  49. ^ Shidara, Hiroyuki; Knaster, Juan; Bogard, Daniel; Chauvin, Nicolas; Girardot, Patrick; Gobin, Raphael; Harrault, Francis; Loiseau, Denis; Nghiem, Phu Anh Phi (2013). "Installation Status of Deuteron Injector of IFMIF Prototype Accelerator in Japan". Proc. 4th International Particle Accelerator Conference (IPAC 2013): MOPEA032.
  50. ^ Kondo, H.; Kanemura, T.; Furukawa, T.; Hirakawa, Y.; Groeschel, F.; Wakai, E. (2014). "The start-up and observation of the Li target in the EVEDA Li test loop". Fusion Engineering and Design. Proceedings of the 11th International Symposium on Fusion Nuclear Technology-11 (ISFNT-11) Barcelona, Spain, 15–20 September 2013. 89 (7–8): 1688–1693. Bibcode:2014FusED..89.1688K. doi:10.1016/j.fusengdes.2014.02.022.
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