Study of Thermal Properties of Irradiation-induced Stainless Steels Used in the Development of Nuclear Reactors

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Poster for the 2011 University Scholars Day at the University of North Texas discussing a study of thermal properties of irradiation-induced stainless steels used in the development of nuclear reactors.

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1 p.

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Londono, Mauricio & Choi, Tae-Youl April 14, 2011.

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This poster is part of the collection entitled: UNT Undergraduate Student Works and was provided by the UNT Honors College to the UNT Digital Library, a digital repository hosted by the UNT Libraries. It has been viewed 125 times. More information about this poster can be viewed below.

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  • Choi, Tae-Youl University of North Texas; Faculty Mentor; choi@egw.unt.edu

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UNT Honors College

The UNT Honors College is dedicated to enriching the undergraduate academic experience for talented, motivated, and well-prepared students. The college offers its members many benefits, including challenging classes, training in research methods and skills, eligibility to live in Rawlins Hall or Honors Hall, and a supportive social and academic environment.

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  • Main Title: Study of Thermal Properties of Irradiation-induced Stainless Steels Used in the Development of Nuclear Reactors
  • Series Title: University Scholars Day

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Description

Poster for the 2011 University Scholars Day at the University of North Texas discussing a study of thermal properties of irradiation-induced stainless steels used in the development of nuclear reactors.

Physical Description

1 p.

Notes

Abstract: In the development of nuclear power reactors, the use of metals able to withstand high temperatures and induced radiation is paramount. Molecular decomposition, embrittlement and swelling at the grain level of such materials are a consequence of intense neutron bombardment. Materials such as stainless steel T91 and oxide dispersed steel (ODS) are widely used in nuclear reactors. Mechanical and thermal properties at the grain level of these materials under irradiation have not been sufficiently demonstrated, for which the understanding and modeling of such parameters may lead to better maintenance of nuclear power plants, further development of newer materials and alloys, and material failure prediction. The purpose of this research is to further investigate the conduction of stainless steels at the grain level when subjected to intense radiation and high temperatures for efficient heat exchanger design and prediction of material failure.

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  • Eighth Annual University Scholars Day, 2011, Denton, Texas, United States

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UNT Undergraduate Student Works

This collection presents scholarly and artistic content created by undergraduate students. All materials have been previously accepted by a professional organization or approved by a faculty mentor. Most classroom assignments are not eligible for inclusion. The collection includes, but is not limited to Honors College theses, thesis supplemental files, professional presentations, articles, and posters. Some items in this collection are restricted to use by the UNT community.

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  • April 14, 2011

Added to The UNT Digital Library

  • June 18, 2012, 9:19 a.m.

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  • March 11, 2020, 10:26 a.m.

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Londono, Mauricio & Choi, Tae-Youl. Study of Thermal Properties of Irradiation-induced Stainless Steels Used in the Development of Nuclear Reactors, poster, April 14, 2011; (https://digital.library.unt.edu/ark:/67531/metadc86727/: accessed May 14, 2025), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Honors College.

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