Validation of miniature test specimens for post-irradiation thermal diffusivity measurement

Masafumi Akiyoshi; Ryuta Kasada; Yuko Ishibashi; Lauren M. Garrison; Josina W. Geringer; Wallace D. Porter; Yutai Katoh

doi:10.1016/j.fusengdes.2018.03.008

Validation of miniature test specimens for post-irradiation thermal diffusivity measurement

Masafumi Akiyoshi, Ryuta Kasada, Yuko Ishibashi, Lauren M. Garrison, Josina W. Geringer, Wallace D. Porter, Yutai Katoh

Materials Design Division

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

3 Citations (Scopus)

Abstract

Radioactivity levels for conventional thermal diffusivity test specimens are often prohibitively high for examination with candidate metallic materials, such as tungsten and reduced activation steels for fusion energy. Therefore, in the ongoing Japan–US PHENIX project, irradiation in the high flux isotope reactor (HFIR) was performed with the miniature specimen form of diameter (D) 3 mm × thickness (T) 1/2 mm small disk for thermal diffusivity measurement. In this study, the thermal diffusivity measurement of this miniature specimen is validated using a Netzsch LFA-467 ‘Hyper Flash’ thermal analyzer and ‘graphene nanoplatelets containing agent’. With careful surface treatment and data analysis, the miniature specimens showed almost the same value as the diameter 10 mm standard specimens.

Original language	English
Pages (from-to)	513-517
Number of pages	5
Journal	Fusion Engineering and Design
Volume	136
DOIs	https://doi.org/10.1016/j.fusengdes.2018.03.008
Publication status	Published - 2018 Nov

Keywords

Ceramics
Miniature specimen
Neutron irradiation
Thermal diffusivity
Tungsten

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.2018.03.008

Cite this

@article{e7617e5607d0431bb1a04fe74b0f7ef4,

title = "Validation of miniature test specimens for post-irradiation thermal diffusivity measurement",

abstract = "Radioactivity levels for conventional thermal diffusivity test specimens are often prohibitively high for examination with candidate metallic materials, such as tungsten and reduced activation steels for fusion energy. Therefore, in the ongoing Japan–US PHENIX project, irradiation in the high flux isotope reactor (HFIR) was performed with the miniature specimen form of diameter (D) 3 mm × thickness (T) 1/2 mm small disk for thermal diffusivity measurement. In this study, the thermal diffusivity measurement of this miniature specimen is validated using a Netzsch LFA-467 {\textquoteleft}Hyper Flash{\textquoteright} thermal analyzer and {\textquoteleft}graphene nanoplatelets containing agent{\textquoteright}. With careful surface treatment and data analysis, the miniature specimens showed almost the same value as the diameter 10 mm standard specimens.",

keywords = "Ceramics, Miniature specimen, Neutron irradiation, Thermal diffusivity, Tungsten",

author = "Masafumi Akiyoshi and Ryuta Kasada and Yuko Ishibashi and Garrison, {Lauren M.} and Geringer, {Josina W.} and Porter, {Wallace D.} and Yutai Katoh",

note = "Funding Information: This work was supported by the Joint Usage/Research Program on Zero-Emission Energy Research, Institute of Advanced Energy, Kyoto University H29A-11 . Publisher Copyright: {\textcopyright} 2018 Elsevier B.V.",

year = "2018",

month = nov,

doi = "10.1016/j.fusengdes.2018.03.008",

language = "English",

volume = "136",

pages = "513--517",

journal = "Fusion Engineering and Design",

issn = "0920-3796",

publisher = "Elsevier BV",

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TY - JOUR

T1 - Validation of miniature test specimens for post-irradiation thermal diffusivity measurement

AU - Akiyoshi, Masafumi

AU - Kasada, Ryuta

AU - Ishibashi, Yuko

AU - Garrison, Lauren M.

AU - Geringer, Josina W.

AU - Porter, Wallace D.

AU - Katoh, Yutai

N1 - Funding Information: This work was supported by the Joint Usage/Research Program on Zero-Emission Energy Research, Institute of Advanced Energy, Kyoto University H29A-11 . Publisher Copyright: © 2018 Elsevier B.V.

PY - 2018/11

Y1 - 2018/11

N2 - Radioactivity levels for conventional thermal diffusivity test specimens are often prohibitively high for examination with candidate metallic materials, such as tungsten and reduced activation steels for fusion energy. Therefore, in the ongoing Japan–US PHENIX project, irradiation in the high flux isotope reactor (HFIR) was performed with the miniature specimen form of diameter (D) 3 mm × thickness (T) 1/2 mm small disk for thermal diffusivity measurement. In this study, the thermal diffusivity measurement of this miniature specimen is validated using a Netzsch LFA-467 ‘Hyper Flash’ thermal analyzer and ‘graphene nanoplatelets containing agent’. With careful surface treatment and data analysis, the miniature specimens showed almost the same value as the diameter 10 mm standard specimens.

AB - Radioactivity levels for conventional thermal diffusivity test specimens are often prohibitively high for examination with candidate metallic materials, such as tungsten and reduced activation steels for fusion energy. Therefore, in the ongoing Japan–US PHENIX project, irradiation in the high flux isotope reactor (HFIR) was performed with the miniature specimen form of diameter (D) 3 mm × thickness (T) 1/2 mm small disk for thermal diffusivity measurement. In this study, the thermal diffusivity measurement of this miniature specimen is validated using a Netzsch LFA-467 ‘Hyper Flash’ thermal analyzer and ‘graphene nanoplatelets containing agent’. With careful surface treatment and data analysis, the miniature specimens showed almost the same value as the diameter 10 mm standard specimens.

KW - Ceramics

KW - Miniature specimen

KW - Neutron irradiation

KW - Thermal diffusivity

KW - Tungsten

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DO - 10.1016/j.fusengdes.2018.03.008

M3 - Article

AN - SCOPUS:85042906124

SN - 0920-3796

VL - 136

SP - 513

EP - 517

JO - Fusion Engineering and Design

JF - Fusion Engineering and Design

ER -

Validation of miniature test specimens for post-irradiation thermal diffusivity measurement

Abstract

Keywords

ASJC Scopus subject areas

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