The advanced neutron source three-element-core fuel grading

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The proposed Advanced Neutron Source (ANS) pre-conceptual design consists of a two-element 330 MW{sub f} nuclear reactor fueled with highly-enriched uranium and is cooled, moderated, and reflected with heavy water. Recently, the ANS design has been changed to a three-element configuration in order to permit a reduction of the enrichment, if required, while maintaining or improving the thermal-hydraulic margins. The core consists of three annular fuel elements composed of involute-shaped fuel plates. Each fuel plate has a thickness of 1.27 mm and consists of a fuel meat region Of U{sub 3}Si{sub 2}-Al (50% enriched in one case that was proposed) ... continued below

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8 p.

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Gehin, J.C. December 31, 1995.

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Description

The proposed Advanced Neutron Source (ANS) pre-conceptual design consists of a two-element 330 MW{sub f} nuclear reactor fueled with highly-enriched uranium and is cooled, moderated, and reflected with heavy water. Recently, the ANS design has been changed to a three-element configuration in order to permit a reduction of the enrichment, if required, while maintaining or improving the thermal-hydraulic margins. The core consists of three annular fuel elements composed of involute-shaped fuel plates. Each fuel plate has a thickness of 1.27 mm and consists of a fuel meat region Of U{sub 3}Si{sub 2}-Al (50% enriched in one case that was proposed) and an aluminum filler region between aluminum cladding. The individual plates are separated by a 1.27 mm coolant channel. The three element core has a fuel loading of 31 kg of {sup 235}U which is sufficient for a 17-day fuel cycle. The goal in obtaining a new fuel grading is to maximize important temperature margins. The limits imposed axe: (1) Limit the temperature drop over the cladding oxide layer to less than 119{degrees}C to avoid oxide spallation. (2) Limit the fuel centerline temperature to less than 400{degrees}C to avoid fuel damage. (3) Limit the cladding wall temperature to less than the coolant. incipient-boiling temperature to avoid coolant boiling. Other thermal hydraulic conditions, such as critical heat flux, are also considered.

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8 p.

Notes

INIS; OSTI as DE96003780

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  • Winter meeting of the American Nuclear Society (ANS), San Francisco, CA (United States), 29 Oct - 1 Nov 1995

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  • Other: DE96003780
  • Report No.: CONF-951006--27
  • Grant Number: AC05-84OR21400
  • DOI: 10.2172/205866 | External Link
  • Office of Scientific & Technical Information Report Number: 193910
  • Archival Resource Key: ark:/67531/metadc672264

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  • December 31, 1995

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  • June 29, 2015, 9:42 p.m.

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  • Jan. 21, 2016, 1:53 p.m.

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Gehin, J.C. The advanced neutron source three-element-core fuel grading, article, December 31, 1995; Tennessee. (digital.library.unt.edu/ark:/67531/metadc672264/: accessed August 20, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.