Enhanced thermal conductivity UO2-BeO fuels fabrication methods and their thermal performance in light water reactors

Wenzhong Zhou; Rong Liu

doi:10.1115/ICONE22-30647

Enhanced thermal conductivity UO2-BeO fuels fabrication methods and their thermal performance in light water reactors

Wenzhong Zhou
, Rong Liu

Research output: Chapters, Conference Papers, Creative and Literary Works › RGC 32 - Refereed conference paper (with host publication) › peer-review

2 Citations (Scopus)

Abstract

An enhanced thermal conductivity UO₂-BeO composite nuclear fuel was studied. A methodology to generate ANSYS (an engineering simulation software) FEM (Finite Element Method) thermal models of enhanced thermal conductivity oxide nuclear fuels was developed. Two fabrication methods to produce high thermal conductivity UO₂-BeO oxide nuclear fuels were summarized. These two processing routes generated pellets with two different microstructures. The characteristics and microstructures of the fuel are determined for use in FEM thermal models, and the relevant thermal properties for UO₂-BeO fuels by two different fabrication methods were determined. The results showed significant increase in the fuel thermal conductivities. The reactor performance analysis showed that the decrease in centerline temperature was 250-350K for the UO₂-BeO composite fuel, and thus we can improve nuclear reactors' performance and safety, and highlevel radioactive waste generation.

Original language	English
Title of host publication	International Conference on Nuclear Engineering, Proceedings, ICONE
Publisher	American Society of Mechanical Engineers
Volume	1
ISBN (Print)	9780791845899
DOIs	https://doi.org/10.1115/ICONE22-30647
Publication status	Published - 2014
Event	2014 22nd International Conference on Nuclear Engineering, ICONE 2014 - Prague, Czech Republic Duration: 7 Jul 2014 → 11 Jul 2014

Publication series

Name
Volume	1

Conference

Conference	2014 22nd International Conference on Nuclear Engineering, ICONE 2014
Place	Czech Republic
City	Prague
Period	7/07/14 → 11/07/14

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SDG 12 Responsible Consumption and Production

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@inproceedings{576e435985d04560a5f3c84cc9dd69fd,

title = "Enhanced thermal conductivity UO2-BeO fuels fabrication methods and their thermal performance in light water reactors",

abstract = "An enhanced thermal conductivity UO2-BeO composite nuclear fuel was studied. A methodology to generate ANSYS (an engineering simulation software) FEM (Finite Element Method) thermal models of enhanced thermal conductivity oxide nuclear fuels was developed. Two fabrication methods to produce high thermal conductivity UO2-BeO oxide nuclear fuels were summarized. These two processing routes generated pellets with two different microstructures. The characteristics and microstructures of the fuel are determined for use in FEM thermal models, and the relevant thermal properties for UO2-BeO fuels by two different fabrication methods were determined. The results showed significant increase in the fuel thermal conductivities. The reactor performance analysis showed that the decrease in centerline temperature was 250-350K for the UO2-BeO composite fuel, and thus we can improve nuclear reactors' performance and safety, and highlevel radioactive waste generation.",

author = "Wenzhong Zhou and Rong Liu",

year = "2014",

doi = "10.1115/ICONE22-30647",

language = "English",

isbn = "9780791845899",

volume = "1",

publisher = "American Society of Mechanical Engineers",

booktitle = "International Conference on Nuclear Engineering, Proceedings, ICONE",

address = "United States",

note = "2014 22nd International Conference on Nuclear Engineering, ICONE 2014 ; Conference date: 07-07-2014 Through 11-07-2014",

}

Zhou, W & Liu, R 2014, Enhanced thermal conductivity UO2-BeO fuels fabrication methods and their thermal performance in light water reactors. in International Conference on Nuclear Engineering, Proceedings, ICONE. vol. 1, American Society of Mechanical Engineers, 2014 22nd International Conference on Nuclear Engineering, ICONE 2014, Prague, Czech Republic, 7/07/14. https://doi.org/10.1115/ICONE22-30647

Enhanced thermal conductivity UO2-BeO fuels fabrication methods and their thermal performance in light water reactors. / Zhou, Wenzhong; Liu, Rong.
International Conference on Nuclear Engineering, Proceedings, ICONE. Vol. 1 American Society of Mechanical Engineers, 2014.

Research output: Chapters, Conference Papers, Creative and Literary Works › RGC 32 - Refereed conference paper (with host publication) › peer-review

TY - GEN

T1 - Enhanced thermal conductivity UO2-BeO fuels fabrication methods and their thermal performance in light water reactors

AU - Zhou, Wenzhong

AU - Liu, Rong

PY - 2014

Y1 - 2014

N2 - An enhanced thermal conductivity UO2-BeO composite nuclear fuel was studied. A methodology to generate ANSYS (an engineering simulation software) FEM (Finite Element Method) thermal models of enhanced thermal conductivity oxide nuclear fuels was developed. Two fabrication methods to produce high thermal conductivity UO2-BeO oxide nuclear fuels were summarized. These two processing routes generated pellets with two different microstructures. The characteristics and microstructures of the fuel are determined for use in FEM thermal models, and the relevant thermal properties for UO2-BeO fuels by two different fabrication methods were determined. The results showed significant increase in the fuel thermal conductivities. The reactor performance analysis showed that the decrease in centerline temperature was 250-350K for the UO2-BeO composite fuel, and thus we can improve nuclear reactors' performance and safety, and highlevel radioactive waste generation.

AB - An enhanced thermal conductivity UO2-BeO composite nuclear fuel was studied. A methodology to generate ANSYS (an engineering simulation software) FEM (Finite Element Method) thermal models of enhanced thermal conductivity oxide nuclear fuels was developed. Two fabrication methods to produce high thermal conductivity UO2-BeO oxide nuclear fuels were summarized. These two processing routes generated pellets with two different microstructures. The characteristics and microstructures of the fuel are determined for use in FEM thermal models, and the relevant thermal properties for UO2-BeO fuels by two different fabrication methods were determined. The results showed significant increase in the fuel thermal conductivities. The reactor performance analysis showed that the decrease in centerline temperature was 250-350K for the UO2-BeO composite fuel, and thus we can improve nuclear reactors' performance and safety, and highlevel radioactive waste generation.

UR - https://www.scopus.com/pages/publications/84911954252

UR - https://www.scopus.com/record/pubmetrics.uri?eid=2-s2.0-84911954252&origin=recordpage

U2 - 10.1115/ICONE22-30647

DO - 10.1115/ICONE22-30647

M3 - RGC 32 - Refereed conference paper (with host publication)

SN - 9780791845899

VL - 1

BT - International Conference on Nuclear Engineering, Proceedings, ICONE

PB - American Society of Mechanical Engineers

T2 - 2014 22nd International Conference on Nuclear Engineering, ICONE 2014

Y2 - 7 July 2014 through 11 July 2014

ER -

Enhanced thermal conductivity UO2-BeO fuels fabrication methods and their thermal performance in light water reactors

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