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Title: Steam Oxidation Evaluation of Fe-Cr Alloys for Accident Tolerant Nuclear Fuel Cladding

Authors:
 [1];  [1]
  1. ORNL
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Nuclear Science User Facility (NSUF)
Sponsoring Org.:
Work for Others (WFO)
OSTI Identifier:
1351754
DOE Contract Number:  
AC05-00OR22725
Resource Type:
Conference
Resource Relation:
Journal Volume: 87; Journal Issue: 3-4; Conference: HTCPM9, Les Embiez, France, 20160515, 20160520
Country of Publication:
United States
Language:
English
Subject:
FeCr alloys; steam oxidation; kinetics; STEM

Citation Formats

Pint, Bruce A, and Unocic, Kinga A. Steam Oxidation Evaluation of Fe-Cr Alloys for Accident Tolerant Nuclear Fuel Cladding. United States: N. p., 2017. Web. doi:10.1007/s11085-017-9754-0.
Pint, Bruce A, & Unocic, Kinga A. Steam Oxidation Evaluation of Fe-Cr Alloys for Accident Tolerant Nuclear Fuel Cladding. United States. doi:10.1007/s11085-017-9754-0.
Pint, Bruce A, and Unocic, Kinga A. Sun . "Steam Oxidation Evaluation of Fe-Cr Alloys for Accident Tolerant Nuclear Fuel Cladding". United States. doi:10.1007/s11085-017-9754-0. https://www.osti.gov/servlets/purl/1351754.
@article{osti_1351754,
title = {Steam Oxidation Evaluation of Fe-Cr Alloys for Accident Tolerant Nuclear Fuel Cladding},
author = {Pint, Bruce A and Unocic, Kinga A},
abstractNote = {},
doi = {10.1007/s11085-017-9754-0},
journal = {},
number = 3-4,
volume = 87,
place = {United States},
year = {Sun Jan 01 00:00:00 EST 2017},
month = {Sun Jan 01 00:00:00 EST 2017}
}

Conference:
Other availability
Please see Document Availability for additional information on obtaining the full-text document. Library patrons may search WorldCat to identify libraries that hold this conference proceeding.

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