Neutron characterization of UN/U-Si accident tolerant fuel prior to irradiation

Adrian S. Losko; Sven C. Vogel; Mark A.M. Bourke; Stewart L. Voit; Anton S. Tremsin; Kenneth J. McClellan; Andrew T. Nelson

Neutron characterization of UN/U-Si accident tolerant fuel prior to irradiation

Adrian S. Losko, Sven C. Vogel, Mark A.M. Bourke, Stewart L. Voit, Anton S. Tremsin, Kenneth J. McClellan, Andrew T. Nelson

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

Abstract

Neutron imaging and tomographic reconstructions provide non-destructive three-dimensional characterization of nuclear fuel pellets that are typically about a cubic centimeter in volume with energy-resolved neutron imaging at a pulsed neutron source offering unique characterization not possible at a reactor source. Recent measurements at the Los Alamos Neutrons Science Center (LANSCE) studied a series of uranium nitride/uranium silicide ceramic composite pellets. This paper provides examples of spatially resolved measurements of cracks, isotopic enrichment and density with a (current) spatial resolution of approximately 75 microns. Phase and texture measurements were also performed but are not discussed in this paper. The UN/U-Si systems are under consideration as candidate systems for accident tolerant fuel. The examples are taken from measurements on a total of nine pellets of differing UN/U-Si formulations (two enrichment levels), U₃Si₅ reference formulations (two enrichment levels) and pellets with known flaws. The ₂₃₅U enrichments ranged from 0.2 to 8.8 wt.%. Pellets of the same composition are scheduled for irradiation in the Advanced Test Reactor this year.

Original language	English
Title of host publication	Top Fuel 2016
Subtitle of host publication	LWR Fuels with Enhanced Safety and Performance
Publisher	American Nuclear Society
Pages	1525-1533
Number of pages	9
ISBN (Electronic)	9780894487309
State	Published - 2016
Externally published	Yes
Event	Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance - Boise, United States Duration: Sep 11 2016 → Sep 15 2016

Publication series

Name	Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance

Conference

Conference	Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance
Country/Territory	United States
City	Boise
Period	09/11/16 → 09/15/16

Funding

This work is funded by the Fuel Cycle R&D program of the Office of Nuclear Energy. The neutron measurements were performed at the Los Alamos Neutron Science Center accelerator, which is stewarded by the National Nuclear Security Administration at Los Alamos National Laboratory operated by Los Alamos National Security LLC. The authors wish to thank Kelly Knickerbocker, Charles Kelsey, Melvin Borrego and Jason Gochanour for support.

Keywords

Characterization
Cracks
Isotopic enrichment
Neutrons
Tomography

Cite this

Losko, A. S., Vogel, S. C., Bourke, M. A. M., Voit, S. L., Tremsin, A. S., McClellan, K. J., & Nelson, A. T. (2016). Neutron characterization of UN/U-Si accident tolerant fuel prior to irradiation. In Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance (pp. 1525-1533). (Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance). American Nuclear Society.

@inproceedings{4495dfc2ce3b4da1afe6288b5f6aa416,

title = "Neutron characterization of UN/U-Si accident tolerant fuel prior to irradiation",

abstract = "Neutron imaging and tomographic reconstructions provide non-destructive three-dimensional characterization of nuclear fuel pellets that are typically about a cubic centimeter in volume with energy-resolved neutron imaging at a pulsed neutron source offering unique characterization not possible at a reactor source. Recent measurements at the Los Alamos Neutrons Science Center (LANSCE) studied a series of uranium nitride/uranium silicide ceramic composite pellets. This paper provides examples of spatially resolved measurements of cracks, isotopic enrichment and density with a (current) spatial resolution of approximately 75 microns. Phase and texture measurements were also performed but are not discussed in this paper. The UN/U-Si systems are under consideration as candidate systems for accident tolerant fuel. The examples are taken from measurements on a total of nine pellets of differing UN/U-Si formulations (two enrichment levels), U3Si5 reference formulations (two enrichment levels) and pellets with known flaws. The 235U enrichments ranged from 0.2 to 8.8 wt.\%. Pellets of the same composition are scheduled for irradiation in the Advanced Test Reactor this year.",

keywords = "Characterization, Cracks, Isotopic enrichment, Neutrons, Tomography",

author = "Losko, \{Adrian S.\} and Vogel, \{Sven C.\} and Bourke, \{Mark A.M.\} and Voit, \{Stewart L.\} and Tremsin, \{Anton S.\} and McClellan, \{Kenneth J.\} and Nelson, \{Andrew T.\}",

year = "2016",

language = "English",

series = "Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance",

publisher = "American Nuclear Society",

pages = "1525--1533",

booktitle = "Top Fuel 2016",

note = "Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance ; Conference date: 11-09-2016 Through 15-09-2016",

}

Losko, AS, Vogel, SC, Bourke, MAM, Voit, SL, Tremsin, AS, McClellan, KJ & Nelson, AT 2016, Neutron characterization of UN/U-Si accident tolerant fuel prior to irradiation. in Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance. Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance, American Nuclear Society, pp. 1525-1533, Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance, Boise, United States, 09/11/16.

Neutron characterization of UN/U-Si accident tolerant fuel prior to irradiation. / Losko, Adrian S.; Vogel, Sven C.; Bourke, Mark A.M. et al.
Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance. American Nuclear Society, 2016. p. 1525-1533 (Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance).

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

TY - GEN

T1 - Neutron characterization of UN/U-Si accident tolerant fuel prior to irradiation

AU - Losko, Adrian S.

AU - Vogel, Sven C.

AU - Bourke, Mark A.M.

AU - Voit, Stewart L.

AU - Tremsin, Anton S.

AU - McClellan, Kenneth J.

AU - Nelson, Andrew T.

PY - 2016

Y1 - 2016

N2 - Neutron imaging and tomographic reconstructions provide non-destructive three-dimensional characterization of nuclear fuel pellets that are typically about a cubic centimeter in volume with energy-resolved neutron imaging at a pulsed neutron source offering unique characterization not possible at a reactor source. Recent measurements at the Los Alamos Neutrons Science Center (LANSCE) studied a series of uranium nitride/uranium silicide ceramic composite pellets. This paper provides examples of spatially resolved measurements of cracks, isotopic enrichment and density with a (current) spatial resolution of approximately 75 microns. Phase and texture measurements were also performed but are not discussed in this paper. The UN/U-Si systems are under consideration as candidate systems for accident tolerant fuel. The examples are taken from measurements on a total of nine pellets of differing UN/U-Si formulations (two enrichment levels), U3Si5 reference formulations (two enrichment levels) and pellets with known flaws. The 235U enrichments ranged from 0.2 to 8.8 wt.%. Pellets of the same composition are scheduled for irradiation in the Advanced Test Reactor this year.

AB - Neutron imaging and tomographic reconstructions provide non-destructive three-dimensional characterization of nuclear fuel pellets that are typically about a cubic centimeter in volume with energy-resolved neutron imaging at a pulsed neutron source offering unique characterization not possible at a reactor source. Recent measurements at the Los Alamos Neutrons Science Center (LANSCE) studied a series of uranium nitride/uranium silicide ceramic composite pellets. This paper provides examples of spatially resolved measurements of cracks, isotopic enrichment and density with a (current) spatial resolution of approximately 75 microns. Phase and texture measurements were also performed but are not discussed in this paper. The UN/U-Si systems are under consideration as candidate systems for accident tolerant fuel. The examples are taken from measurements on a total of nine pellets of differing UN/U-Si formulations (two enrichment levels), U3Si5 reference formulations (two enrichment levels) and pellets with known flaws. The 235U enrichments ranged from 0.2 to 8.8 wt.%. Pellets of the same composition are scheduled for irradiation in the Advanced Test Reactor this year.

KW - Characterization

KW - Cracks

KW - Isotopic enrichment

KW - Neutrons

KW - Tomography

UR - https://www.scopus.com/pages/publications/85019018966

M3 - Conference contribution

AN - SCOPUS:85019018966

T3 - Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance

SP - 1525

EP - 1533

BT - Top Fuel 2016

PB - American Nuclear Society

T2 - Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance

Y2 - 11 September 2016 through 15 September 2016

ER -

Neutron characterization of UN/U-Si accident tolerant fuel prior to irradiation

Abstract

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Keywords

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