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Title: Irradiation Demonstration Element Design Parameters for MURR LEU U-Mo Fuel Conversion

Abstract

This report contains the results of reactor design and performance calculations for conversion of the University of Missouri Research Reactor (MURR) from the use of highly-enriched uranium (HEU) fuel to the use of low-enriched uranium (LEU) fuel. The analyses were performed by staff members of the U.S. Department of Energy National Nuclear Security Administration (NNSA)Office of Material Management and Minimization(M3)Reactor Conversion Program at the Argonne National Laboratory and the MURR Facility.

Authors:
 [1];  [1];  [2];  [2];  [2];  [2]
  1. Argonne National Lab. (ANL), Argonne, IL (United States)
  2. Univ. of Missouri, Columbia, MO (United States)
Publication Date:
Research Org.:
Argonne National Lab. (ANL), Argonne, IL (United States)
Sponsoring Org.:
USDOE National Nuclear Security Administration (NNSA), Office of Defense Nuclear Nonproliferation (NA-20). Office of Material Management and Minimization (NA-23)
OSTI Identifier:
1484001
Report Number(s):
ANL/RTR/TM-18/4
148746; TRN: US1902692
DOE Contract Number:  
AC02-06CH11357
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS

Citation Formats

Stillman, J., Wilson, E., Foyto, L., Kutikkad, K., McKibben, J. C., and Peters, N. Irradiation Demonstration Element Design Parameters for MURR LEU U-Mo Fuel Conversion. United States: N. p., 2018. Web. doi:10.2172/1484001.
Stillman, J., Wilson, E., Foyto, L., Kutikkad, K., McKibben, J. C., & Peters, N. Irradiation Demonstration Element Design Parameters for MURR LEU U-Mo Fuel Conversion. United States. doi:10.2172/1484001.
Stillman, J., Wilson, E., Foyto, L., Kutikkad, K., McKibben, J. C., and Peters, N. Mon . "Irradiation Demonstration Element Design Parameters for MURR LEU U-Mo Fuel Conversion". United States. doi:10.2172/1484001. https://www.osti.gov/servlets/purl/1484001.
@article{osti_1484001,
title = {Irradiation Demonstration Element Design Parameters for MURR LEU U-Mo Fuel Conversion},
author = {Stillman, J. and Wilson, E. and Foyto, L. and Kutikkad, K. and McKibben, J. C. and Peters, N.},
abstractNote = {This report contains the results of reactor design and performance calculations for conversion of the University of Missouri Research Reactor (MURR) from the use of highly-enriched uranium (HEU) fuel to the use of low-enriched uranium (LEU) fuel. The analyses were performed by staff members of the U.S. Department of Energy National Nuclear Security Administration (NNSA)Office of Material Management and Minimization(M3)Reactor Conversion Program at the Argonne National Laboratory and the MURR Facility.},
doi = {10.2172/1484001},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2018},
month = {1}
}

Technical Report:

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