Metallurgical analysis of corroded bellows of bellow-sealed valve in lithium flow system

Asril Pramutadi Andi Mustari; Minoru Takahashi

doi:10.1016/j.fusengdes.2013.02.003

Metallurgical analysis of corroded bellows of bellow-sealed valve in lithium flow system

Asril Pramutadi Andi Mustari, Minoru Takahashi^*

^*Corresponding author for this work

Research output: Contribution to journal › Article › peer-review

7 Citations (Scopus)

Abstract

Liquid lithium has been one of the candidates of the tritium breeder and possibly a coolant for the blanket of fusion reactors. The observation of corrosion behavior was conducted on the bellows of the bellow-sealed valve used in a lithium circulation loop at 350-500 °C for about 1500 h. The results were obtained from observation of the surfaces and cross sections. The bellows was found to be fractured and detached. Selective elements were depleted on the surface.

Original language	English
Pages (from-to)	202-208
Number of pages	7
Journal	Fusion Engineering and Design
Volume	88
Issue number	4
DOIs	https://doi.org/10.1016/j.fusengdes.2013.02.003
Publication status	Published - 2013 May

Keywords

Bellow-sealed valve
Bellows
Cold work
Corrosion
Fatigue
Lithium

ASJC Scopus subject areas

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

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10.1016/j.fusengdes.2013.02.003

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abstract = "Liquid lithium has been one of the candidates of the tritium breeder and possibly a coolant for the blanket of fusion reactors. The observation of corrosion behavior was conducted on the bellows of the bellow-sealed valve used in a lithium circulation loop at 350-500 °C for about 1500 h. The results were obtained from observation of the surfaces and cross sections. The bellows was found to be fractured and detached. Selective elements were depleted on the surface.",

keywords = "Bellow-sealed valve, Bellows, Cold work, Corrosion, Fatigue, Lithium",

author = "Mustari, {Asril Pramutadi Andi} and Minoru Takahashi",

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AU - Takahashi, Minoru

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N2 - Liquid lithium has been one of the candidates of the tritium breeder and possibly a coolant for the blanket of fusion reactors. The observation of corrosion behavior was conducted on the bellows of the bellow-sealed valve used in a lithium circulation loop at 350-500 °C for about 1500 h. The results were obtained from observation of the surfaces and cross sections. The bellows was found to be fractured and detached. Selective elements were depleted on the surface.

AB - Liquid lithium has been one of the candidates of the tritium breeder and possibly a coolant for the blanket of fusion reactors. The observation of corrosion behavior was conducted on the bellows of the bellow-sealed valve used in a lithium circulation loop at 350-500 °C for about 1500 h. The results were obtained from observation of the surfaces and cross sections. The bellows was found to be fractured and detached. Selective elements were depleted on the surface.

KW - Bellow-sealed valve

KW - Bellows

KW - Cold work

KW - Corrosion

KW - Fatigue

KW - Lithium

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EP - 208

JO - Fusion Engineering and Design

JF - Fusion Engineering and Design

SN - 0920-3796

IS - 4

ER -

Metallurgical analysis of corroded bellows of bellow-sealed valve in lithium flow system

Abstract

Keywords

ASJC Scopus subject areas

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