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Title: U-Mo Monolithic Fuel for Nuclear Research and Test Reactors

Abstract

The metallic fuel selected to replace the current HEU fuels in the research and test reactors is the LEU-10 weight % Mo alloy in the form of a thin sheet or foil encapsulated in AA6061 aluminum alloy with a zirconium interlayer. In order to effectively lead this pursuit, new developments in processing and fabrication of the fuel elements have been initiated, along with a better understanding of material behavior before and after irradiation as a result of these new developments. This editorial note gives an introduction about research and test reactors, need for HEU to LEU conversion, fuel requirements, high uranium density monolithic fuel development and an overview of the four articles published in the December 2017 issue of JOM under a special topic titled “U-Mo Monolithic Fuel for Nuclear Research and Test Reactors”.

Authors:
Publication Date:
Research Org.:
Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1415697
Report Number(s):
PNNL-SA-129341
Journal ID: ISSN 1047-4838; DN2006000
DOE Contract Number:  
AC05-76RL01830
Resource Type:
Journal Article
Journal Name:
JOM. Journal of the Minerals, Metals & Materials Society
Additional Journal Information:
Journal Volume: 69; Journal Issue: 12; Journal ID: ISSN 1047-4838
Publisher:
Springer
Country of Publication:
United States
Language:
English
Subject:
U-Mo; research and test reactors; LEU fuel development

Citation Formats

Prabhakaran, Ramprashad. U-Mo Monolithic Fuel for Nuclear Research and Test Reactors. United States: N. p., 2017. Web. doi:10.1007/s11837-017-2612-3.
Prabhakaran, Ramprashad. U-Mo Monolithic Fuel for Nuclear Research and Test Reactors. United States. doi:10.1007/s11837-017-2612-3.
Prabhakaran, Ramprashad. Thu . "U-Mo Monolithic Fuel for Nuclear Research and Test Reactors". United States. doi:10.1007/s11837-017-2612-3.
@article{osti_1415697,
title = {U-Mo Monolithic Fuel for Nuclear Research and Test Reactors},
author = {Prabhakaran, Ramprashad},
abstractNote = {The metallic fuel selected to replace the current HEU fuels in the research and test reactors is the LEU-10 weight % Mo alloy in the form of a thin sheet or foil encapsulated in AA6061 aluminum alloy with a zirconium interlayer. In order to effectively lead this pursuit, new developments in processing and fabrication of the fuel elements have been initiated, along with a better understanding of material behavior before and after irradiation as a result of these new developments. This editorial note gives an introduction about research and test reactors, need for HEU to LEU conversion, fuel requirements, high uranium density monolithic fuel development and an overview of the four articles published in the December 2017 issue of JOM under a special topic titled “U-Mo Monolithic Fuel for Nuclear Research and Test Reactors”.},
doi = {10.1007/s11837-017-2612-3},
journal = {JOM. Journal of the Minerals, Metals & Materials Society},
issn = {1047-4838},
number = 12,
volume = 69,
place = {United States},
year = {2017},
month = {11}
}

Works referenced in this record:

History of fast reactor fuel development
journal, September 1993


Development of very-high-density low-enriched-uranium fuels
journal, December 1997


Low-temperature irradiation behavior of uranium–molybdenum alloy dispersion fuel
journal, August 2002