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Title: Radiation tolerance of FeCrAl alloys for light water reactor fuel cladding applications.

Abstract

Abstract not provided.

Authors:
Publication Date:
Research Org.:
Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
Sponsoring Org.:
USDOE National Nuclear Security Administration (NNSA)
OSTI Identifier:
1510568
Report Number(s):
SAND2018-4555PE
662603
DOE Contract Number:  
AC04-94AL85000
Resource Type:
Conference
Resource Relation:
Conference: Proposed for presentation at the Invited Seminar at Oregon State University in Corvallis, OR.
Country of Publication:
United States
Language:
English

Citation Formats

Briggs, Samuel. Radiation tolerance of FeCrAl alloys for light water reactor fuel cladding applications.. United States: N. p., 2018. Web.
Briggs, Samuel. Radiation tolerance of FeCrAl alloys for light water reactor fuel cladding applications.. United States.
Briggs, Samuel. Sun . "Radiation tolerance of FeCrAl alloys for light water reactor fuel cladding applications.". United States. https://www.osti.gov/servlets/purl/1510568.
@article{osti_1510568,
title = {Radiation tolerance of FeCrAl alloys for light water reactor fuel cladding applications.},
author = {Briggs, Samuel},
abstractNote = {Abstract not provided.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2018},
month = {4}
}

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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