Hydrogen Release from Irradiated Vanadium Alloy V-4Cr-4Ti
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.
- Research Organization:
- Idaho National Lab. (INL), Idaho Falls, ID (United States)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- DE-AC07-99ID-13727
- OSTI ID:
- 924524
- Report Number(s):
- INEEL/CON-99-00078; TRN: US200809%%365
- 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
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