Modified formula for the assessment of the thermal response of neutron irradiated CFC

V. Barabash; L. L. Snead

doi:10.1016/j.jnucmat.2004.04.215

Modified formula for the assessment of the thermal response of neutron irradiated CFC

V. Barabash
, L. L. Snead

Materials Science and Engineering

ITER

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

2 Scopus citations

Abstract

The available thermal conductivity data for various neutron-irradiated 2-3 dimensional carbon fibre composite materials have been collected and have been critically reviewed with respect to possible application in the ITER divertor. The empirical correlations are proposed that match the thermal conductivity data and allow interpolate or extrapolate of the behaviour in the wide temperature (∼150-3000 °C) and fluence (0-0.1 dpa) ranges of interest for ITER. These include the correlations for materials with 'high' (≳200 W/mK) initial thermal conductivity and for materials with moderate (∼100 W/mK) thermal conductivity. Using the proposed formula the thermal performance of CFC armoured ITER divertor is assessed.

Original language	English
Pages (from-to)	860-864
Number of pages	5
Journal	Journal of Nuclear Materials
Volume	329-333
Issue number	1-3 PART A
DOIs	https://doi.org/10.1016/j.jnucmat.2004.04.215
State	Published - Aug 1 2004
Event	Proceedings of the 11th Conference on Fusion Research - Kyoto, Japan Duration: Dec 7 2003 → Dec 12 2003

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10.1016/j.jnucmat.2004.04.215

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title = "Modified formula for the assessment of the thermal response of neutron irradiated CFC",

abstract = "The available thermal conductivity data for various neutron-irradiated 2-3 dimensional carbon fibre composite materials have been collected and have been critically reviewed with respect to possible application in the ITER divertor. The empirical correlations are proposed that match the thermal conductivity data and allow interpolate or extrapolate of the behaviour in the wide temperature (∼150-3000 °C) and fluence (0-0.1 dpa) ranges of interest for ITER. These include the correlations for materials with 'high' (≳200 W/mK) initial thermal conductivity and for materials with moderate (∼100 W/mK) thermal conductivity. Using the proposed formula the thermal performance of CFC armoured ITER divertor is assessed.",

author = "V. Barabash and Snead, \{L. L.\}",

year = "2004",

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doi = "10.1016/j.jnucmat.2004.04.215",

language = "English",

volume = "329-333",

pages = "860--864",

journal = "Journal of Nuclear Materials",

issn = "0022-3115",

number = "1-3 PART A",

note = "Proceedings of the 11th Conference on Fusion Research ; Conference date: 07-12-2003 Through 12-12-2003",

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TY - JOUR

T1 - Modified formula for the assessment of the thermal response of neutron irradiated CFC

AU - Barabash, V.

AU - Snead, L. L.

PY - 2004/8/1

Y1 - 2004/8/1

N2 - The available thermal conductivity data for various neutron-irradiated 2-3 dimensional carbon fibre composite materials have been collected and have been critically reviewed with respect to possible application in the ITER divertor. The empirical correlations are proposed that match the thermal conductivity data and allow interpolate or extrapolate of the behaviour in the wide temperature (∼150-3000 °C) and fluence (0-0.1 dpa) ranges of interest for ITER. These include the correlations for materials with 'high' (≳200 W/mK) initial thermal conductivity and for materials with moderate (∼100 W/mK) thermal conductivity. Using the proposed formula the thermal performance of CFC armoured ITER divertor is assessed.

AB - The available thermal conductivity data for various neutron-irradiated 2-3 dimensional carbon fibre composite materials have been collected and have been critically reviewed with respect to possible application in the ITER divertor. The empirical correlations are proposed that match the thermal conductivity data and allow interpolate or extrapolate of the behaviour in the wide temperature (∼150-3000 °C) and fluence (0-0.1 dpa) ranges of interest for ITER. These include the correlations for materials with 'high' (≳200 W/mK) initial thermal conductivity and for materials with moderate (∼100 W/mK) thermal conductivity. Using the proposed formula the thermal performance of CFC armoured ITER divertor is assessed.

UR - https://www.scopus.com/pages/publications/3342882869

U2 - 10.1016/j.jnucmat.2004.04.215

DO - 10.1016/j.jnucmat.2004.04.215

M3 - Conference article

AN - SCOPUS:3342882869

SN - 0022-3115

VL - 329-333

SP - 860

EP - 864

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

IS - 1-3 PART A

T2 - Proceedings of the 11th Conference on Fusion Research

Y2 - 7 December 2003 through 12 December 2003

ER -

Modified formula for the assessment of the thermal response of neutron irradiated CFC

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