Case study on tritium inventory in the fusion DEMO plant at JAERI

Hirofumi Nakamura; Shinji Sakurai; Satoshi Suzuki; Takumi Hayashi; Mikio Enoeda; Kenji Tobita

doi:10.1016/j.fusengdes.2005.10.009

Case study on tritium inventory in the fusion DEMO plant at JAERI

Hirofumi Nakamura, Shinji Sakurai, Satoshi Suzuki, Takumi Hayashi, Mikio Enoeda, Kenji Tobita

Research output: Contribution to journal › Conference article › peer-review

50 Citations (Scopus)

Abstract

Case studies on tritium inventory and permeation in a fusion demo plant designed by JAERI (DEMO(J05)) have been carried out using several data sets on the tritium transport properties of the candidate materials of the plasma facing components. The results have been compared with the design guidelines for loss of tritium into the components or coolant for tritium accountancy (1.4 kg/y) and tritium concentration in the coolant (0.37 GBq/cm³) for DEMO(J05). The results revealed that tritium concentration and inventory in the coolant attributed to permeation from the blanket (plasma facing first wall and breeding region) is expected to be much higher both of these guidelines unless designated permeation barriers are used. Therefore, permeation must be reduced by a factor of 100 in order to satisfy the guidelines. Tungsten coating on the first wall and glassy coating on the blanket cooling tubes may be good countermeasures for permeation reduction in DEMO(J05).

Original language	English
Pages (from-to)	1339-1345
Number of pages	7
Journal	Fusion Engineering and Design
Volume	81
Issue number	8-14 PART B
DOIs	https://doi.org/10.1016/j.fusengdes.2005.10.009
Publication status	Published - 2006 Feb
Externally published	Yes
Event	Proceedings of the Seventh International Symposium on Fusion Nuclear Technology ISFNT-7 Part B - Duration: 2005 May 22 → 2005 May 27

Keywords

Fusion demo plant
Tritium inventory
Tritium permeation

ASJC Scopus subject areas

Civil and Structural Engineering
Nuclear Energy and Engineering
Materials Science(all)
Mechanical Engineering

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10.1016/j.fusengdes.2005.10.009

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title = "Case study on tritium inventory in the fusion DEMO plant at JAERI",

abstract = "Case studies on tritium inventory and permeation in a fusion demo plant designed by JAERI (DEMO(J05)) have been carried out using several data sets on the tritium transport properties of the candidate materials of the plasma facing components. The results have been compared with the design guidelines for loss of tritium into the components or coolant for tritium accountancy (1.4 kg/y) and tritium concentration in the coolant (0.37 GBq/cm3) for DEMO(J05). The results revealed that tritium concentration and inventory in the coolant attributed to permeation from the blanket (plasma facing first wall and breeding region) is expected to be much higher both of these guidelines unless designated permeation barriers are used. Therefore, permeation must be reduced by a factor of 100 in order to satisfy the guidelines. Tungsten coating on the first wall and glassy coating on the blanket cooling tubes may be good countermeasures for permeation reduction in DEMO(J05).",

keywords = "Fusion demo plant, Tritium inventory, Tritium permeation",

author = "Hirofumi Nakamura and Shinji Sakurai and Satoshi Suzuki and Takumi Hayashi and Mikio Enoeda and Kenji Tobita",

note = "Copyright: Copyright 2008 Elsevier B.V., All rights reserved.; Proceedings of the Seventh International Symposium on Fusion Nuclear Technology ISFNT-7 Part B ; Conference date: 22-05-2005 Through 27-05-2005",

year = "2006",

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doi = "10.1016/j.fusengdes.2005.10.009",

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AU - Nakamura, Hirofumi

AU - Sakurai, Shinji

AU - Suzuki, Satoshi

AU - Hayashi, Takumi

AU - Enoeda, Mikio

AU - Tobita, Kenji

PY - 2006/2

Y1 - 2006/2

N2 - Case studies on tritium inventory and permeation in a fusion demo plant designed by JAERI (DEMO(J05)) have been carried out using several data sets on the tritium transport properties of the candidate materials of the plasma facing components. The results have been compared with the design guidelines for loss of tritium into the components or coolant for tritium accountancy (1.4 kg/y) and tritium concentration in the coolant (0.37 GBq/cm3) for DEMO(J05). The results revealed that tritium concentration and inventory in the coolant attributed to permeation from the blanket (plasma facing first wall and breeding region) is expected to be much higher both of these guidelines unless designated permeation barriers are used. Therefore, permeation must be reduced by a factor of 100 in order to satisfy the guidelines. Tungsten coating on the first wall and glassy coating on the blanket cooling tubes may be good countermeasures for permeation reduction in DEMO(J05).

AB - Case studies on tritium inventory and permeation in a fusion demo plant designed by JAERI (DEMO(J05)) have been carried out using several data sets on the tritium transport properties of the candidate materials of the plasma facing components. The results have been compared with the design guidelines for loss of tritium into the components or coolant for tritium accountancy (1.4 kg/y) and tritium concentration in the coolant (0.37 GBq/cm3) for DEMO(J05). The results revealed that tritium concentration and inventory in the coolant attributed to permeation from the blanket (plasma facing first wall and breeding region) is expected to be much higher both of these guidelines unless designated permeation barriers are used. Therefore, permeation must be reduced by a factor of 100 in order to satisfy the guidelines. Tungsten coating on the first wall and glassy coating on the blanket cooling tubes may be good countermeasures for permeation reduction in DEMO(J05).

KW - Fusion demo plant

KW - Tritium inventory

KW - Tritium permeation

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Case study on tritium inventory in the fusion DEMO plant at JAERI

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Keywords

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