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Title: Permeation of hydrogen in hastelloy C-276 alloy at high temperature

Abstract

Tritium is generated by the interaction of neutrons with the lithium and beryllium in the molten salt reactors (MSRs), which use FLiBe as one of solvents of fluoride fuel. Tritium as by-product in the MSRs is an important safety issue because it could easily diffuse into environment through high temperature heat exchangers. The experimental technique of gas driven permeation has been used to investigate the transport parameter of hydrogen in Hastelloy C-276 which is considered as one of the candidate for structure materials. The measurements were carried out at the temperature range of 400-800 Celsius degrees with hydrogen loading pressures ranging from 5*10{sup 3} to 4*10{sup 4} Pa. The H diffusive transport parameters for Hastelloy C-276 follow an Arrhenius law in this temperature range. Regarding diffusivity and Sieverts' constant, Hastelloy C-276 has lower values compared with Ni201 alloy. The possible reason may be the trapping effects, which were formed by the alloying elements of Mo and Cr in the matrix. At the same time, the thin oxidation layer formed by the high Cr content could lead to a slower dissociation process of H{sub 2} at the surface. (authors)

Authors:
; ;  [1];  [2]
  1. Shanghai Institute of Applied Physics, Jiading District, Shanghai (China)
  2. Nuclear and Radiation Safety Center, Haidian District, Beijing (China)
Publication Date:
OSTI Identifier:
22429796
Resource Type:
Journal Article
Journal Name:
Fusion Science and Technology
Additional Journal Information:
Journal Volume: 67; Journal Issue: 3; Conference: TRITIUM 2013: 10. International Conference on Tritium Science and Technology, Nice Acropolis (France), 21-25 Oct 2013; Other Information: Country of input: France; 16 refs.; Journal ID: ISSN 1536-1055
Country of Publication:
United States
Language:
English
Subject:
37 INORGANIC, ORGANIC, PHYSICAL AND ANALYTICAL CHEMISTRY; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 36 MATERIALS SCIENCE; BERYLLIUM; FLIBE; FLUORIDES; HASTELLOYS; HEAT EXCHANGERS; HYDROGEN; LITHIUM; MOLTEN SALT REACTORS; NEUTRONS; PRESSURE RANGE KILO PA; SOLVENTS; TEMPERATURE RANGE 0400-1000 K; TRITIUM

Citation Formats

Zhang, D., Liu, W., Qian, Y., and Que, J. Permeation of hydrogen in hastelloy C-276 alloy at high temperature. United States: N. p., 2015. Web. doi:10.13182/FST14-T109.
Zhang, D., Liu, W., Qian, Y., & Que, J. Permeation of hydrogen in hastelloy C-276 alloy at high temperature. United States. https://doi.org/10.13182/FST14-T109
Zhang, D., Liu, W., Qian, Y., and Que, J. Sun . "Permeation of hydrogen in hastelloy C-276 alloy at high temperature". United States. https://doi.org/10.13182/FST14-T109.
@article{osti_22429796,
title = {Permeation of hydrogen in hastelloy C-276 alloy at high temperature},
author = {Zhang, D. and Liu, W. and Qian, Y. and Que, J.},
abstractNote = {Tritium is generated by the interaction of neutrons with the lithium and beryllium in the molten salt reactors (MSRs), which use FLiBe as one of solvents of fluoride fuel. Tritium as by-product in the MSRs is an important safety issue because it could easily diffuse into environment through high temperature heat exchangers. The experimental technique of gas driven permeation has been used to investigate the transport parameter of hydrogen in Hastelloy C-276 which is considered as one of the candidate for structure materials. The measurements were carried out at the temperature range of 400-800 Celsius degrees with hydrogen loading pressures ranging from 5*10{sup 3} to 4*10{sup 4} Pa. The H diffusive transport parameters for Hastelloy C-276 follow an Arrhenius law in this temperature range. Regarding diffusivity and Sieverts' constant, Hastelloy C-276 has lower values compared with Ni201 alloy. The possible reason may be the trapping effects, which were formed by the alloying elements of Mo and Cr in the matrix. At the same time, the thin oxidation layer formed by the high Cr content could lead to a slower dissociation process of H{sub 2} at the surface. (authors)},
doi = {10.13182/FST14-T109},
url = {https://www.osti.gov/biblio/22429796}, journal = {Fusion Science and Technology},
issn = {1536-1055},
number = 3,
volume = 67,
place = {United States},
year = {2015},
month = {3}
}