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Title: Manufacturing Experience for Oxide Dispersion Strengthened Alloys

Abstract

This report documents the results of the development and the manufacturing experience gained at the Pacific Northwest National Laboratories (PNNL) while working with the oxide dispersion strengthened (ODS) materials MA 956, 14YWT, and 9YWT. The Fuel Cycle Research and Development program of the Office of Nuclear Energy has implemented a program to develop a Uranium-Molybdenum metal fuel for light water reactors. ODS materials have the potential to provide improved performance for the U-Mo concept.

Authors:
 [1];  [1];  [1];  [1];  [1];  [1];  [1];  [1]
  1. Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
Publication Date:
Research Org.:
Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1406829
Report Number(s):
PNNL-25817
AF5810000
DOE Contract Number:  
AC05-76RL01830
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE

Citation Formats

Bennett, Wendy D., Doherty, Ann L., Henager, Charles H., Lavender, Curt A., Montgomery, Robert O., Omberg, Ronald P., Smith, Mark T., and Webster, Ryan A. Manufacturing Experience for Oxide Dispersion Strengthened Alloys. United States: N. p., 2016. Web. doi:10.2172/1406829.
Bennett, Wendy D., Doherty, Ann L., Henager, Charles H., Lavender, Curt A., Montgomery, Robert O., Omberg, Ronald P., Smith, Mark T., & Webster, Ryan A. Manufacturing Experience for Oxide Dispersion Strengthened Alloys. United States. doi:10.2172/1406829.
Bennett, Wendy D., Doherty, Ann L., Henager, Charles H., Lavender, Curt A., Montgomery, Robert O., Omberg, Ronald P., Smith, Mark T., and Webster, Ryan A. Thu . "Manufacturing Experience for Oxide Dispersion Strengthened Alloys". United States. doi:10.2172/1406829. https://www.osti.gov/servlets/purl/1406829.
@article{osti_1406829,
title = {Manufacturing Experience for Oxide Dispersion Strengthened Alloys},
author = {Bennett, Wendy D. and Doherty, Ann L. and Henager, Charles H. and Lavender, Curt A. and Montgomery, Robert O. and Omberg, Ronald P. and Smith, Mark T. and Webster, Ryan A.},
abstractNote = {This report documents the results of the development and the manufacturing experience gained at the Pacific Northwest National Laboratories (PNNL) while working with the oxide dispersion strengthened (ODS) materials MA 956, 14YWT, and 9YWT. The Fuel Cycle Research and Development program of the Office of Nuclear Energy has implemented a program to develop a Uranium-Molybdenum metal fuel for light water reactors. ODS materials have the potential to provide improved performance for the U-Mo concept.},
doi = {10.2172/1406829},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Thu Sep 22 00:00:00 EDT 2016},
month = {Thu Sep 22 00:00:00 EDT 2016}
}

Technical Report:

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