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Journal Articles

Approach to the lifetime assessment of the bayonet back plate for IFMIF target

Agostini, P.*; Ida, Mizuho; Miccich$`e$, G.*; Nakamura, Hiroo; Turroni, P.*

Fusion Engineering and Design, 84(2-6), p.364 - 368, 2009/06

 Times Cited Count:4 Percentile:65.85(Nuclear Science & Technology)

In the International Fusion Materials Irradiation Facility (IFMIF), a back-plate of liquid lithium (Li) target is most severely irradiated by high flux of neutrons. The conceptual configuration of the IFMIF target, based on the bayonet back plate, has been developed. The life time analysis of the back-plate has to be made carefully, in order to credibly estimate its expected replacement frequency. The various interconnections between the main damaging causes were discussed in order to evidence the most plausible reasons of the back-plate malfunctioning. The results were as follows. Under IFMIF Li condition with nitrogen content of 10 wppm or less, the erosion/corrosion rate of the back-plate made of the reduced activation ferritic steel is 0.003 mm/year or less. Even in case that the Bragg peak of heat deposition by deuterons approaches to the back-plate by 1 mm, temperature of the back-plate increases by only 12 degrees or less, and induced fatigue load is well low. Thermal stress due to the neutron irradiation is 93 MPa at the back-plate center, which is well below the plastic limit. The positive shift in the ductile brittle transition temperature (DBTT), the most effective factor, reduces the back-plate lifetime to three months or shorter under irradiation damage rate of 60 dpa/year. However, the lifetime can be recovered by the post irradiation annealing heat treatment.

Journal Articles

Status of engineering design of liquid lithium target in IFMIF-EVEDA

Nakamura, Hiroo; Agostini, P.*; Ara, Kuniaki; Fukada, Satoshi*; Furuya, Kazuyuki*; Garin, P.*; Gessii, A.*; Giusti, D.*; Groeschel, F.*; Horiike, Hiroshi*; et al.

Fusion Engineering and Design, 84(2-6), p.252 - 258, 2009/06

 Times Cited Count:25 Percentile:12.45(Nuclear Science & Technology)

Journal Articles

Latest design of liquid lithium target in IFMIF

Nakamura, Hiroo; Agostini, P.*; Ara, Kuniaki; Cevolani, S.*; Chida, Teruo*; Ciotti, M.*; Fukada, Satoshi*; Furuya, Kazuyuki*; Garin, P.*; Gessii, A.*; et al.

Fusion Engineering and Design, 83(7-9), p.1007 - 1014, 2008/12

 Times Cited Count:14 Percentile:27.98(Nuclear Science & Technology)

This paper describes the latest design of liquid lithium target system in IFMIF. Design requirement of the Li target is to provide a stable Li jet with a speed of 20 m/s to handle an averaged heat flux of 1 GW/m$$^{2}$$. A double reducer nozzle and a concaved flow are applied to the target design. On Li purification, a cold trap and two kinds of hot trap are applied to control impurities below permissible levels. Nitrogen concentration shall be controlled below 10 wppm by one of the hot trap. Tritium concentration shall be controlled below 1 wppm by an yttrium hot trap. To maintain reliable continuous operation, various diagnostics are attached to the target assembly. Among the target assembly, a back-plate made of RAFM is located in the most severe region of neutron irradiation (50 dpa/y). Therefore, two design options of replaceable back wall and their remote handling systems are under investigation.

Oral presentation

Status of IFMIF target system development

Nakamura, Hiroo; Ida, Mizuho; Miyashita, Makoto; Yoshida, Eiichi; Ara, Kuniaki; Nishitani, Takeo; Okumura, Yoshikazu; Horiike, Hiroshi*; Kondo, Hiroo*; Terai, Takayuki*; et al.

no journal, , 

no abstracts in English

Oral presentation

Status of liquid lithium target activities in IFMIF-EVEDA

Nakamura, Hiroo; Agostini, P.*; Groeschel, F.*

no journal, , 

In this presentation, status of the liquid lithium (Li) target activities will be presented. In International Fusion Materials Irradiation Facility (IFMIF), intense neutron flux is produced by D-Li stripping reaction. The liquid Li target system consists of a target assembly, a main loop and a purification loop. Design requirement is to provide a stable Li jet at a maximum speed of 20 m/s. A cold trap and two kinds of hot trap are applied to control impurities below 10 wppm for nitrogen and 1 wppm for tritium. To maintain reliable continuous operation, various diagnostics are attached. The backplate made of RAFMs is located in the most severe region of neutron irradiation (60 dpa/y). Life time of the backplate will be evaluated considering DBTT etc. For replacement of the backplate by remote handling, two design options of replaceable backplate are investigated. In the EVEDA, Li test loop is planned and will start till early 2011.

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