Overview of test modules for Advanced Fusion Neutron Source A-FNS
•Establishment of basic specifications and concepts on the test modules for A-FNS.•Structural design on the test module taken into account the replacement with the remote handling.•Establishment of methodology on the replacement of the test module.•Design of the test module on the maximum value of t...
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Veröffentlicht in: | Fusion engineering and design 2020-06, Vol.155, p.111714, Article 111714 |
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Format: | Artikel |
Sprache: | eng |
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Zusammenfassung: | •Establishment of basic specifications and concepts on the test modules for A-FNS.•Structural design on the test module taken into account the replacement with the remote handling.•Establishment of methodology on the replacement of the test module.•Design of the test module on the maximum value of the cumulative neutron displacement damage of 20 dpa in accumulated irradiation for two years.•Design of connection way of electrical cables from the test module from the viewpoint of facilitation of disconnection and connection.
We have conducted a conceptual design on the test modules for Advanced Fusion Neutron Source A-FNS. Fusion neutron irradiation tests are performed using a variety of the test modules in A-FNS. We acquire the irradiation data on the fusion reactor materials, based on which the construction phase of the fusion DEMO DT reactor is to be decided. We established basic specifications and concepts on the test modules. Structural design on the test module was conducted taking into account the replacement with the remote handling, and we established the basic structural concept and the replacement methodology. By applying the methodology in this study, only capsules can be easily replaced from the test module. Nuclear analyses were performed for the test module. The maximum value of the neutron displacement damage on the blanket structural material test specimen is 10 dpa in accumulated irradiation for one year, and we can acquire the irradiation data on the cumulative damage of 20 dpa, which is requirement value as the initial irradiation data for the construction of a DEMO reactor, in accumulated irradiation for two years. Thermal analyses were conducted for the test specimens in irradiation, and it was confirmed their temperatures could satisfy the design specifications. |
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ISSN: | 0920-3796 1873-7196 |
DOI: | 10.1016/j.fusengdes.2020.111714 |