Preliminary design of a graphite irradiation tensile creep experiment in the target region of the high flux isotope reactor

J. L. McDuffee; T. D. Burchell; D. W. Heatherly; K. R. Thoms

doi:10.1016/j.jnucmat.2008.07.031

Preliminary design of a graphite irradiation tensile creep experiment in the target region of the high flux isotope reactor

J. L. McDuffee
, T. D. Burchell
, D. W. Heatherly
, K. R. Thoms

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

5 Scopus citations

Abstract

Up to four irradiation tensile creep tests are planned for the target region of the high flux isotope reactor on two graphite grades: PCEA and NBG-18. The initial experiment is designed for an irradiation temperature of 600 °C and at fluences between 1 × 10²² n/cm² and 1.4 × 10²² n/cm² (E > 50 keV).

Original language	English
Pages (from-to)	119-123
Number of pages	5
Journal	Journal of Nuclear Materials
Volume	381
Issue number	1-2
DOIs	https://doi.org/10.1016/j.jnucmat.2008.07.031
State	Published - Oct 31 2008
Externally published	Yes

Funding

This work is sponsored by the U.S. Department of Energy, Office of Nuclear Energy Science and Technology under contract DE-AC05-00OR22725 with Oak Ridge National Laboratory, managed by UT-Battelle, LLC.

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10.1016/j.jnucmat.2008.07.031

Cite this

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title = "Preliminary design of a graphite irradiation tensile creep experiment in the target region of the high flux isotope reactor",

abstract = "Up to four irradiation tensile creep tests are planned for the target region of the high flux isotope reactor on two graphite grades: PCEA and NBG-18. The initial experiment is designed for an irradiation temperature of 600 °C and at fluences between 1 × 1022 n/cm2 and 1.4 × 1022 n/cm2 (E > 50 keV).",

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AU - Heatherly, D. W.

AU - Thoms, K. R.

PY - 2008/10/31

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N2 - Up to four irradiation tensile creep tests are planned for the target region of the high flux isotope reactor on two graphite grades: PCEA and NBG-18. The initial experiment is designed for an irradiation temperature of 600 °C and at fluences between 1 × 1022 n/cm2 and 1.4 × 1022 n/cm2 (E > 50 keV).

AB - Up to four irradiation tensile creep tests are planned for the target region of the high flux isotope reactor on two graphite grades: PCEA and NBG-18. The initial experiment is designed for an irradiation temperature of 600 °C and at fluences between 1 × 1022 n/cm2 and 1.4 × 1022 n/cm2 (E > 50 keV).

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JO - Journal of Nuclear Materials

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ER -

Preliminary design of a graphite irradiation tensile creep experiment in the target region of the high flux isotope reactor

Abstract

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