Design Strategy and Recent Design Activity on Japan’s DEMO

Tobita, K.; Asakura, N.; Hiwatari, Ryoji; Someya, Youji; Utoh, Hiroyasu; Katayama, Kazunari; Nishimura, A.; Sakamoto, Y.; Homma, Y.; Kudo, Hironobu; Miyoshi, Y.; Nakamura, Makoto; Tokunaga, Shunsuke; Aoki, Akira

doi:10.1080/15361055.2017.1364112

Cited by 45 publications

(16 citation statements)

References 17 publications

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“…For the next step devices, e.g., DEMO, [45,46,[48][49][50][51] or a future fusion reactor including Chinese experimental fusion test reactor, [52] the limits on power exhaust, availability, and lifetime are even more demanding, as conventional monoblocks are allowing for 10 MW m À2 , [20,21] and transmutation and radiation damage can quickly diminish the thermal conductivity to 50%. [53,54] Radiation effects including neutron embrittlement [55] do limit actively cooled W components in DEMO to about 3-5 MW m À2 due to the diminished thermal conductivity and the need to replace CuCrZr with steels with their low thermal conductivity.…”

Section: Materials For Fusionmentioning

confidence: 99%

Fusion Materials Development at Forschungszentrum Jülich

Coenen

2020

Adv Eng Mater

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Material issues pose a significant challenge for the design of future fusion reactors. From a historic point of view, the material mix used for the first wall of a fusion reactor has continually evolved, from original steel vessels to carbon and other low-Z materials such as beryllium to tungsten as the primary candidate for a reactor's first wall armor and divertor material. For materials considered for fusion applications, a highly integrated approach is necessary. Resilience against neutron damage, good power exhaust, and oxidation resistance during accidental air ingress are design relevant issues while deciding on new materials or improving upon baseline materials. Neutron-induced effects, e.g., transmutation adding to embrittlement, retention, and changes to thermomechanical properties, are crucial to material performance. In this contribution, the recent progress (2013-2019) in fusion materials development for current and future fusion devices, at Forschungszentrum Jülich GmbH, with activities focussing on advanced materials and their characterization is given. It is a continuation and extension of the work given by Coenen et al.

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Section: Materials For Fusionmentioning

confidence: 99%

Fusion Materials Development at Forschungszentrum Jülich

Coenen

2020

Adv Eng Mater

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“…31 In contrast, Be 12 V and Be 13 Zr do not require homogenization treatment. In addition, Be 12 V and Be 13 Zr have more excellent oxidation resistance than Be 12 Ti and show lower H 2 generation with water vapor, 32,33 which is advantageous in terms of safety.…”

Section: Breeding Blanketmentioning

confidence: 99%

Japan’s Efforts to Develop the Concept of JA DEMO During the Past Decade

Tobita

Hiwatari

Sakamoto

et al. 2019

Fusion Science and Technology

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This paper summarizes the evolution of Japanese DEMO design studies in a retrospective manner by highlighting efforts to resolve critical design issues on DEMO. Japan is currently working on the conceptual study of a steady-state DEMO (JA DEMO) with a major radius Rp of 8.5 m and fusion power Pfus of 1.5 to 2 GW based on water-cooled solid breeding blanket with pressurized water reactor water condition (290ºC to 325ºC, 15.5 MPa). Such a lower Pfus allows to find realistic design solutions for divertor heat removal. Recognizing that divertor heat removal is one of the most challenging issues on DEMO, the divertor design has been carried out in different approaches, including numerical divertor plasma simulation, magnetic configurations, heat sink design, etc. It is noteworthy that the latest divertor simulation led to a design window allowing divertor heat removal of the peak heat flux of <10 MW/m 2 . The breeding blanket (BB) design has been concentrated on simplification of the internal structure and pressure tightness of the BB casing against the in-box loss-of-coolant accident. Due to a large amount of radioactive waste generated in periodic replacement of in-vessel components, downsizing of waste-related facilities has come to be regarded as a significant design issue. A possible waste management for reducing temporary waste storage was proposed, and its impact on the plant layout was assessed.

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“…Of course, it depends on the fusion power. Because of the limitation of the heat load of the diverter, 1.5 to 2.0 GW class DEMO is considering in Japan [3]. If the size becomes 1.5 times, the volume will become 3.375 times and the weight will become 3.3 times if the average density is almost the same.…”

Section: Introductionmentioning

confidence: 99%

Study on Assembly of TF Coil and Vacuum Vessel for Fusion DEMO

Nishimura

2021

Plasma and Fusion Research

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ITER is in the integration phase and a fusion DEMO is being designed conceptually. The size of the DEMO will be around 1.5 time larger than the ITER and the weight will be about three times larger than the ITER. The TF coil and the vacuum vessel of the DEMO will become very heavy and extremely large. Although the central support structure will be used in the ITER for the assembly of TF coils and vacuum vessels, the central cylinder concept is proposed in this study to avoid the huge concentrated load at the center of the device floor during assembly. In addition, the welding joint between the vacuum vessels is discussed under the limited conditions supposed on the DEMO. Since the vacuum vessel will become the nuclear boundary, all weld lines will be expected to be examined by ultrasonic testing and/or radiographic testing to ensure the soundness of the welds.

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Design Strategy and Recent Design Activity on Japan’s DEMO

Cited by 45 publications

References 17 publications

Fusion Materials Development at Forschungszentrum Jülich

Fusion Materials Development at Forschungszentrum Jülich

Japan’s Efforts to Develop the Concept of JA DEMO During the Past Decade

Study on Assembly of TF Coil and Vacuum Vessel for Fusion DEMO

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