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Title: Hydrogen Release from Irradiated Vanadium Alloy V-4Cr-4Ti

Abstract

The present work is an attempt to obtain data concerning the influence of neutron and ? irradiation upon hydrogen retention in V-4Cr-4Ti vanadium alloy. The experiments on in-pile loading of vanadium alloy specimens at the neutron flux density 1014 n/cm2s, hydrogen pressure of 80 Pa, and temperatures of 563, 613, and 773 K were carried out using the IVG.1M reactor of the Kazakhstan National Nuclear Center. A preliminary set of loading/degassing experiments with non-irradiated material has been carried out to obtain data on hydrogen interaction with vanadium alloy. The, data presented in this work are related both to non-irradiated and irradiated samples.

Authors:
; ; ; ; ;
Publication Date:
Research Org.:
Idaho National Laboratory (INL)
Sponsoring Org.:
USDOE
OSTI Identifier:
924524
Report Number(s):
INEEL/CON-99-00078
Journal ID: ISSN 0920-3796; TRN: US200809%%365
DOE Contract Number:  
DE-AC07-99ID-13727
Resource Type:
Conference
Resource Relation:
Journal Volume: 51-52; Conference: 5th International Symposium on Fusion Nuclear Technology,Rome, Italy,09/19/1999,09/24/1999
Country of Publication:
United States
Language:
English
Subject:
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE; FLUX DENSITY; HYDROGEN; IRRADIATION; KAZAKHSTAN; NEUTRON FLUX; NEUTRONS; RETENTION; VANADIUM ALLOYS; hydrogen retention and release; irradiated materials; vanadium alloys

Citation Formats

Klepikov, A. Kh., Romanenko, O. G., Chikhray, E. V., Tazhibaeva, I. L., Shestakov, V. P., and Longhurst, Glen Reed. Hydrogen Release from Irradiated Vanadium Alloy V-4Cr-4Ti. United States: N. p., 1999. Web. doi:10.1016/S0920-3796(00)00305-7.
Klepikov, A. Kh., Romanenko, O. G., Chikhray, E. V., Tazhibaeva, I. L., Shestakov, V. P., & Longhurst, Glen Reed. Hydrogen Release from Irradiated Vanadium Alloy V-4Cr-4Ti. United States. doi:10.1016/S0920-3796(00)00305-7.
Klepikov, A. Kh., Romanenko, O. G., Chikhray, E. V., Tazhibaeva, I. L., Shestakov, V. P., and Longhurst, Glen Reed. Wed . "Hydrogen Release from Irradiated Vanadium Alloy V-4Cr-4Ti". United States. doi:10.1016/S0920-3796(00)00305-7. https://www.osti.gov/servlets/purl/924524.
@article{osti_924524,
title = {Hydrogen Release from Irradiated Vanadium Alloy V-4Cr-4Ti},
author = {Klepikov, A. Kh. and Romanenko, O. G. and Chikhray, E. V. and Tazhibaeva, I. L. and Shestakov, V. P. and Longhurst, Glen Reed},
abstractNote = {The present work is an attempt to obtain data concerning the influence of neutron and ? irradiation upon hydrogen retention in V-4Cr-4Ti vanadium alloy. The experiments on in-pile loading of vanadium alloy specimens at the neutron flux density 1014 n/cm2s, hydrogen pressure of 80 Pa, and temperatures of 563, 613, and 773 K were carried out using the IVG.1M reactor of the Kazakhstan National Nuclear Center. A preliminary set of loading/degassing experiments with non-irradiated material has been carried out to obtain data on hydrogen interaction with vanadium alloy. The, data presented in this work are related both to non-irradiated and irradiated samples.},
doi = {10.1016/S0920-3796(00)00305-7},
journal = {},
issn = {0920-3796},
number = ,
volume = 51-52,
place = {United States},
year = {1999},
month = {9}
}

Conference:
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