A new fuel loading design for the Advanced Neutron Source

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Description

A new fuel loading design has been developed for the Advanced Neutron Source Reactor. In this reactor the combination of a small core volume and high power results in a very high power density. Using a direct optimization procedure the thermal-hydraulic margins for oxide temperature drop, centerline temperature and incipient boiling (and thus critical heat flux) were maximized to increase the limiting thermal power from 298 MW to 346 MW compared to the previous fuel grading, while maintaining the desired peak reflector thermal flux.

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11 p.

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Gehin, J. C.; Renier, J. P. & Worley, B. A. June 1, 1994.

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Description

A new fuel loading design has been developed for the Advanced Neutron Source Reactor. In this reactor the combination of a small core volume and high power results in a very high power density. Using a direct optimization procedure the thermal-hydraulic margins for oxide temperature drop, centerline temperature and incipient boiling (and thus critical heat flux) were maximized to increase the limiting thermal power from 298 MW to 346 MW compared to the previous fuel grading, while maintaining the desired peak reflector thermal flux.

Physical Description

11 p.

Notes

INIS; OSTI as DE94012323; Paper copy available at OSTI: phone, 865-576-8401, or email, reports@adonis.osti.gov

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  • American Nuclear Society (ANS) topical meeting,Knoxville, TN (United States),11-15 Apr 1994

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Office of Scientific & Technical Information Technical Reports

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  • June 1, 1994

Added to The UNT Digital Library

  • Nov. 3, 2018, 11:47 a.m.

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  • Nov. 14, 2018, 4:14 p.m.

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Gehin, J. C.; Renier, J. P. & Worley, B. A. A new fuel loading design for the Advanced Neutron Source, report, June 1, 1994; Tennessee. (https://digital.library.unt.edu/ark:/67531/metadc1314641/: accessed July 29, 2021), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.

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