Japanese endeavors to establish technological bases for DEMO

Yamada, H.; Kasada, Ryuta; Ozaki, Akira; Sakamoto, R.; Sakamoto, Y.; Takenaga, H.; Tanaka, Teruya; Tanigawa, Hisashi; Okano, Kunihiko; Tobita, K.; Kaneko, O.; Ushigusa, K.

doi:10.1016/j.fusengdes.2015.12.035

Cited by 19 publications

(5 citation statements)

References 5 publications

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“…This problem had an impact on the arguments about the goals of DEMO among the Japanese fusion community in the 2010s, and thus the target on the output has been updated to "steady and stable power generation beyond several hundreds of MW" (Ref. 12). Such a change in the development policy created the circumstances to explore a DEMO concept with a larger R p and lower P fus .…”

Section: Demo Development Strategymentioning

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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Section: Demo Development Strategymentioning

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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“…Various countries and regions, including China, the United States, the European Union, Russia, Japan, Korea and India, are preparing for a fusion demonstration reactor (DEMO), laying an essential foundation for the future commercial fusion power plant (FPP). [10][11][12][13] However, fusion energy is not born to be safe and there are risks similar to those of nuclear fission reactors. In a D-T tokamak fusion reactor, the mobilizable radioactive inventories, about 10 kg tritium, 100 to 1000 kg dust and much activated corrosion products (ACPs), are widely distributed.…”

Section: Introductionmentioning

confidence: 99%

“…Remarkable progress has been made toward realizing fusion's potential. Various countries and regions, including China, the United States, the European Union, Russia, Japan, Korea and India, are preparing for a fusion demonstration reactor (DEMO), laying an essential foundation for the future commercial fusion power plant (FPP) 10‐13 …”

Section: Introductionmentioning

confidence: 99%

Quantitative safety goals for fusion power plants: Rationales and suggestions

Wang

Chen

et al. 2021

Int J Energy Res

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“…'Japan's Roadmap and Action Plan to Promote Research and Development Towards Fusion Prototype Reactors', published in 2018, stated that the Japanese Project of development of fusion power plant will decide to go into the construction phase of the fusion DEMO DT reactor around 2035 [1]. The decision will be made by checking and reviewing the results of the engineering design and R & D on the fusion DEMO DT reactor.…”

Section: Introductionmentioning

confidence: 99%

Conceptual design of advanced fusion neutron source (A-FNS) and irradiation test modules

Sato¹,

Kasugai²,

Ochiai³

et al. 2021

Nucl. Fusion

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We have established a conceptual design of Advanced Fusion Neutron Source (A-FNS). In order to obtain irradiation data required in qualifying materials of fusion DEMO DT reactor, we newly designed nine test modules (TMs) to be implemented in the A-FNS. The design of the test modules is based on a new distinctive maintenance scheme: ‘horizontal maintenance method integrated with the shielding plug’. By integrating the TMs with the shield plug and transferring those from the test cell to the access cell, we can avoid disconnecting and connecting the huge amounts of the pipes and cables by means of the remote handling inside the test cell. We determined a configuration of the TMs in the test cell so as to achieve the required irradiation data for each of the test modules. The maximum dpa of F82H specimens in the TM for blanket structural material was about 10 dpa/fpy, which was designed to fulfil critical requirement by accumulated irradiation for two years and operation duration for four years with the operation availability of 50%. A-FNS was designed so that the huge amounts of neutrons generated can be utilized for various non-fusion purposes as well as the fusion materials irradiation. We newly designed a module to produce the significant amount of 99Mo for a medical purpose. The module for such a non-fusion purpose can be installed in the test cell with the compatibility of the fusion materials irradiation tests.

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Japanese endeavors to establish technological bases for DEMO

Cited by 19 publications

References 5 publications

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

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

Quantitative safety goals for fusion power plants: Rationales and suggestions

Conceptual design of advanced fusion neutron source (A-FNS) and irradiation test modules

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