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Hydrogen permeation in iron-chromium-aluminum (FeCrAl) alloys and the effects of microstructure and surface oxide

Journal Article · · Journal of Nuclear Materials
 [1];  [2];  [2];  [2];  [3];  [3];  [4]
  1. Idaho National Laboratory (INL), Idaho Falls, ID (United States); Purdue Univ., West Lafayette, IN (United States)
  2. Idaho National Laboratory (INL), Idaho Falls, ID (United States)
  3. Missouri Univ. of Science and Technology, Rolla, MO (United States)
  4. Idaho National Laboratory (INL), Idaho Falls, ID (United States); Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Iron–chromium–aluminum (FeCrAl) class alloys are candidates for use as cladding for accident-tolerant fuels and moderators. In this context, hydrogen isotope permeation in FeCrAl alloys is an important material property. Here, in the present work, the apparent permeability, effective diffusivity, and apparent solubility of hydrogen in the FeCrAl alloys C26M and Kanthal D (KD) were measured with gas-driven hydrogen permeation. Permeation measurements were conducted at temperatures of 400 to 700 °C and at gas-driven pressures from 1 to 100 kPa. In particular, the effect of grain size on hydrogen transport was studied with KD samples with three different microstructures: nanocrystalline (NC), ultra-fine grained (UFG), and coarse-grained (CG). The UFG and NC specimens had higher apparent activation energies (73.4 kJ mol-1 and 65.2 kJ mol-1, respectively) for hydrogen permeability than the CG sample (46.9 kJ mol-1). An aluminum oxide layer formed on the primary- and secondary-side surfaces of all samples subjected to permeation experiments which demonstrated the propensity of FeCrAl alloys to form these innate oxide permeation barriers.

Research Organization:
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Sponsoring Organization:
USDOE Laboratory Directed Research and Development (LDRD) Program; USDOE Office of Nuclear Energy (NE), Nuclear Energy Enabling Technologies (NEET); USDOE Office of Nuclear Energy (NE)
Grant/Contract Number:
AC05-00OR22725; AC07-05ID14517; NE0008524
OSTI ID:
2479023
Alternate ID(s):
OSTI ID: 2447008
Journal Information:
Journal of Nuclear Materials, Vol. 603; ISSN 0022-3115
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English

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