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Title: Pre-Licensing Evaluation of Legacy SFR Metallic Fuel Data

Abstract

The US sodium cooled fast reactor (SFR) metallic fuel performance data that are of interest to advanced fast reactors applications, can be attributed mostly to the Integral Fast Reactor (IFR) program between 1984 and 1994. Metallic fuel data collected prior to the IFR program were associated with types of fuel that are not of interest to future advanced reactors deployment (e.g., previous U-Fissium alloy fuel). The IFR fuels data were collected from irradiation of U-Zr based fuel alloy, with and without Pu additions, and clad in different types of steels, including HT9, D9, and 316 stainless-steel. Different types of data were generated during the program, and were based on the requirements associated with the DOE Advanced Liquid Metal Cooled Reactor (ALMR) program.

Authors:
 [1];  [1]
  1. Argonne National Lab. (ANL), Argonne, IL (United States). Nuclear Engineering Division
Publication Date:
Research Org.:
Argonne National Lab. (ANL), Argonne, IL (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE), Nuclear Reactor Technologies (NE-7)
OSTI Identifier:
1418818
Report Number(s):
ANL-ART-76
136280
DOE Contract Number:  
AC02-06CH11357
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 22 GENERAL STUDIES OF NUCLEAR REACTORS

Citation Formats

Yacout, A. M., and Billone, M. C. Pre-Licensing Evaluation of Legacy SFR Metallic Fuel Data. United States: N. p., 2016. Web. doi:10.2172/1418818.
Yacout, A. M., & Billone, M. C. Pre-Licensing Evaluation of Legacy SFR Metallic Fuel Data. United States. doi:10.2172/1418818.
Yacout, A. M., and Billone, M. C. Fri . "Pre-Licensing Evaluation of Legacy SFR Metallic Fuel Data". United States. doi:10.2172/1418818. https://www.osti.gov/servlets/purl/1418818.
@article{osti_1418818,
title = {Pre-Licensing Evaluation of Legacy SFR Metallic Fuel Data},
author = {Yacout, A. M. and Billone, M. C.},
abstractNote = {The US sodium cooled fast reactor (SFR) metallic fuel performance data that are of interest to advanced fast reactors applications, can be attributed mostly to the Integral Fast Reactor (IFR) program between 1984 and 1994. Metallic fuel data collected prior to the IFR program were associated with types of fuel that are not of interest to future advanced reactors deployment (e.g., previous U-Fissium alloy fuel). The IFR fuels data were collected from irradiation of U-Zr based fuel alloy, with and without Pu additions, and clad in different types of steels, including HT9, D9, and 316 stainless-steel. Different types of data were generated during the program, and were based on the requirements associated with the DOE Advanced Liquid Metal Cooled Reactor (ALMR) program.},
doi = {10.2172/1418818},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2016},
month = {9}
}

Technical Report:

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