Japanese Fusion Materials Development Path to DEMO

Muroga, T.; Tanigawa, Hiroyasu

doi:10.1080/15361055.2017.1330641

Cited by 4 publications

(3 citation statements)

References 13 publications

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“…Figure 2 shows the prediction of loss of elongation of RAFM by irradiation and strategy of testing [6]. From previous neutron irradiation experiments with fission test reactors, it is found that the total elongation of RAFM tends to be harden to around 10% and keeps the value of around 7%.…”

Section: Reduced Activation Ferritic-martensitic Irradiationmentioning

confidence: 99%

Conceptual design progress of advanced fusion neutron source

et al. 2020

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Based on the results of the IFMIF/EVEDA project in the broader approach (BA) activities, the conceptual design of the Advanced Fusion Neutron Source (A-FNS) to obtain irradiation data of DEMO blanket materials is under consideration in Japan. This paper describes the progress of the A-FNS conceptual design, which consists of a 40 MeV, 125 mA deuteron beam, a liquid lithium target system, and a test and post-irradiation test facilities. the main objectives of the A-FNS are the acquisition of RAFM irradiation data up to 2035 and the tritium recovery test on the blanket. In addition, it is expected to be used for various neutron researches. The technical design activities of the A-FNS are focused on improvement of the lithium target design, review of impurity criteria, remote handling, and irradiation application plan.

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Section: Reduced Activation Ferritic-martensitic Irradiationmentioning

confidence: 99%

Conceptual design progress of advanced fusion neutron source

et al. 2020

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“…To enable the construction and operation of DEMO, it is necessary to evaluate precisely the behavior of materials in DEMO environments. For this purpose, construction of a high-quality material irradiation database is thought to be essential [22]. However, irradiation data can contain various problems.…”

Section: Proposals Regarding the Future Direction Of Irradiation Rese...mentioning

confidence: 99%

Challenge to Performance Evaluation of Fusion Reactor Materials by Fission Neutron and Charged Particle Irradiation

Muroga

2023

MSF

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Since there are no fusion reactors generating high-flux 14 MeV neutrons, it is necessary to evaluate materials’ performance in fusion reactors based on a correlation of fission neutron and charged particle irradiations. However, the irradiation tests involve various issues which prevent simple correlation and evaluation. In this paper, the issues related to irradiation temperature control and dose rate effects are pointed out and analyzed, and proposals regarding future irradiation tests are given.

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“…The A-FNS generates the large number of neutrons with the broad energy peak of around 14 MeV as shown in figure 1. The ratio of the produced amounts of the helium in the iron to the amounts of the displaced atoms caused by the neutron irradiations is a factor of around 15 [17,[38][39][40][41][42]. Since it is almost the same value as that at the first wall of the Japanese fusion DEMO reactor, the irradiation tests by using A-FNS are very useful for validation of DEMO materials design.…”

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 Fusion Materials Development Path to DEMO

Cited by 4 publications

References 13 publications

Conceptual design progress of advanced fusion neutron source

Conceptual design progress of advanced fusion neutron source

Challenge to Performance Evaluation of Fusion Reactor Materials by Fission Neutron and Charged Particle Irradiation

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

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