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Establishment of a Lead Loop Facility to Support Lead Cooled Fast Reactor Design

  • O. AnderogluEmail author
  • C. Cakez
  • S. Ghosh
  • K. Talaat
  • S. Lee
  • Y. Lee
  • K. A. Woloshun
  • S. J. Kim
  • S. A. Maloy
  • C. Unal
  • M. Ickes
  • P. Ferroni
Conference paper
  • 623 Downloads
Part of the The Minerals, Metals & Materials Series book series (MMMS)

Abstract

A new test loop made out of FeCrAl based oxide dispersion strengthened steel (ODS) MA956 is established at the University of New Mexico (UNM). The facility will support Versatile Test Reactor (VTR) program’s cartridge design out-of-pile to explore solutions for material compatibility issues of Lead Cooled Fast Reactors (LFRs). The loop is capable of operating up to 700 °C. While the flow rate in the MA956 pipe can reach up to 1 m/s, the specimen holders are designed to allow flow rates on the test specimens to reach 3 m/s. Numerical modeling is utilized to guide the experiments and assess the sensitivity to different design and operation parameters. In addition to the materials testing, a variety instrumentation needed for the operation of the reactors as well thermal hydraulics studies through a heat exchanger is also considered.

Notes

Acknowledgements

This work was supported by the Battel Energy Alliance LLC and the US Department of Energy (DOE-NEUP and VTR Programs) under the contract with the University of New Mexico (DE-NE0008789). The initial simulations were performed using computational resources provided by the University of New Mexico. Authors also acknowledges partial support by NRC faculty development grant (# NRC-HQ-60-17-G-0007).

References

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    Ballinger RG, Lim J (2004) An overview of corrosion issues for the design and operation of high-temperature lead- and lead-bismuth-cooled reactor systems. Nucl Technol 147(3):418–435CrossRefGoogle Scholar
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    Short MP, Ballinger RG, Hanninen HE (2013) Corrosion resistance of ally F91 and Fe-12Cr-2Si in LBE up to 715 °C. J Nuclear Mater 434:259–281Google Scholar
  3. 3.
    Sobolev V Database of thermophysical properties of liquid metal coolants for GEN-IV. Report, SCK-CEN-BLG-1069Google Scholar

Copyright information

© The Minerals, Metals & Materials Society 2020

Authors and Affiliations

  • O. Anderoglu
    • 1
    Email author
  • C. Cakez
    • 1
  • S. Ghosh
    • 1
  • K. Talaat
    • 1
  • S. Lee
    • 1
  • Y. Lee
    • 2
  • K. A. Woloshun
    • 3
  • S. J. Kim
    • 3
  • S. A. Maloy
    • 3
  • C. Unal
    • 3
  • M. Ickes
    • 4
  • P. Ferroni
    • 4
  1. 1.University of New MexicoAlbuquerqueUSA
  2. 2.Seoul National UniversitySeoulSouth Korea
  3. 3.Los Alamos National LaboratoryLos AlamosUSA
  4. 4.Westinghouse Electric CorporationPittsburghUSA

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