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Title: Safety Analysis of the Mo-99 Production Upgrade to the University of Missouri Research Reactor (MURR) with Highly-Enriched and Low-Enriched Uranium Fuel

Abstract

The University of Missouri has been working in conjunction with Argonne National Laboratory (ANL) in the National Nuclear Security Administration (NNSA) Material Management and Minimization (M3) Reactor Conversion Program to support conversion of the University of Missouri- Columbia Research Reactor (MURR®) from highly enriched uranium (HEU) to low-enriched uranium (LEU) fuel. MURR is one of five U.S. High Performance Research Reactors (USHPRR) plus a critical facility that plans to convert to the use of LEU fuel. The purpose of this report is to document the safety margins for both HEU and LEU cores with the Mo-99 production upgrade proposed, designated as the 2017-RBM-99 device in this report. In addition to the 2017-RBM-99 device, the neutronics models also include descriptions of the experimental facilities and experiment loading that are currently typical for MURR and which are different from the experiments that were modeled in the analysis performed for the PSAR. Lastly, there have been changes to the LEU fuel element design with regard to the coolant channel thickness tolerances for the innermost and outermost coolant channels based on feedback from the fuel fabricator. This design change did not change the nominal dimensions of the coolant channels/fuel plates or fuel loading ofmore » the fuel plates in the element. Thus, for the purpose of the neutronics analysis for the 2017-RBM-99 upgrade, which is based on nominal dimensions and fuel loadings, the components of the LEU element are modeled the same as in the PSAR analysis. However, the design tolerance changes were incorporated in the calculations of the steady-state safety margins for both HEU and LEU. While the use of fewer significant figures has simplified fabrication, yet there were no negative impacts, including on safety margins, since the end channels were not limiting locations.« less

Authors:
 [1];  [1];  [1];  [1];  [1];  [2];  [2];  [2];  [2]
  1. Argonne National Lab. (ANL), Argonne, IL (United States). Nuclear Science and Engineering Div.
  2. Univ. of Missouri, Columbia, MO (United States). Research Reactor
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 - Office of Material Management and Minimization (M3)
OSTI Identifier:
1569033
Report Number(s):
ANL/RTR/TM-18/16
154020; TRN: US2000035
DOE Contract Number:  
AC02-06CH11357
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS

Citation Formats

Stillman, J. A., Feldman, E. E., Pham, S., Yoon, D. S., Wilson, E. H., Cowherd, W. M., Foyto, L. P., Kutikkad, K., and Peters, N. J.. Safety Analysis of the Mo-99 Production Upgrade to the University of Missouri Research Reactor (MURR) with Highly-Enriched and Low-Enriched Uranium Fuel. United States: N. p., 2019. Web. doi:10.2172/1569033.
Stillman, J. A., Feldman, E. E., Pham, S., Yoon, D. S., Wilson, E. H., Cowherd, W. M., Foyto, L. P., Kutikkad, K., & Peters, N. J.. Safety Analysis of the Mo-99 Production Upgrade to the University of Missouri Research Reactor (MURR) with Highly-Enriched and Low-Enriched Uranium Fuel. United States. https://doi.org/10.2172/1569033
Stillman, J. A., Feldman, E. E., Pham, S., Yoon, D. S., Wilson, E. H., Cowherd, W. M., Foyto, L. P., Kutikkad, K., and Peters, N. J.. 2019. "Safety Analysis of the Mo-99 Production Upgrade to the University of Missouri Research Reactor (MURR) with Highly-Enriched and Low-Enriched Uranium Fuel". United States. https://doi.org/10.2172/1569033. https://www.osti.gov/servlets/purl/1569033.
@article{osti_1569033,
title = {Safety Analysis of the Mo-99 Production Upgrade to the University of Missouri Research Reactor (MURR) with Highly-Enriched and Low-Enriched Uranium Fuel},
author = {Stillman, J. A. and Feldman, E. E. and Pham, S. and Yoon, D. S. and Wilson, E. H. and Cowherd, W. M. and Foyto, L. P. and Kutikkad, K. and Peters, N. J.},
abstractNote = {The University of Missouri has been working in conjunction with Argonne National Laboratory (ANL) in the National Nuclear Security Administration (NNSA) Material Management and Minimization (M3) Reactor Conversion Program to support conversion of the University of Missouri- Columbia Research Reactor (MURR®) from highly enriched uranium (HEU) to low-enriched uranium (LEU) fuel. MURR is one of five U.S. High Performance Research Reactors (USHPRR) plus a critical facility that plans to convert to the use of LEU fuel. The purpose of this report is to document the safety margins for both HEU and LEU cores with the Mo-99 production upgrade proposed, designated as the 2017-RBM-99 device in this report. In addition to the 2017-RBM-99 device, the neutronics models also include descriptions of the experimental facilities and experiment loading that are currently typical for MURR and which are different from the experiments that were modeled in the analysis performed for the PSAR. Lastly, there have been changes to the LEU fuel element design with regard to the coolant channel thickness tolerances for the innermost and outermost coolant channels based on feedback from the fuel fabricator. This design change did not change the nominal dimensions of the coolant channels/fuel plates or fuel loading of the fuel plates in the element. Thus, for the purpose of the neutronics analysis for the 2017-RBM-99 upgrade, which is based on nominal dimensions and fuel loadings, the components of the LEU element are modeled the same as in the PSAR analysis. However, the design tolerance changes were incorporated in the calculations of the steady-state safety margins for both HEU and LEU. While the use of fewer significant figures has simplified fabrication, yet there were no negative impacts, including on safety margins, since the end channels were not limiting locations.},
doi = {10.2172/1569033},
url = {https://www.osti.gov/biblio/1569033}, journal = {},
number = ,
volume = ,
place = {United States},
year = {2019},
month = {10}
}