Hostname: page-component-78c5997874-fbnjt Total loading time: 0 Render date: 2024-11-11T05:22:45.921Z Has data issue: false hasContentIssue false

Nondestructive Evaluation on Hydrided LWR Fuel Cladding by Small Angle Incoherent Neutron Scattering of Hydrogen

Published online by Cambridge University Press:  09 January 2014

Y. Yan
Affiliation:
Oak Ridge National Laboratory, Oak Ridge, TN 37831, U.S.A.
S. Qian
Affiliation:
Oak Ridge National Laboratory, Oak Ridge, TN 37831, U.S.A.
K. Littrell
Affiliation:
Oak Ridge National Laboratory, Oak Ridge, TN 37831, U.S.A.
C. M. Parish
Affiliation:
Oak Ridge National Laboratory, Oak Ridge, TN 37831, U.S.A.
G. L. Bell
Affiliation:
Oak Ridge National Laboratory, Oak Ridge, TN 37831, U.S.A.
L. K. Plummer
Affiliation:
University of Oregon, Eugene, OR 97403, U.S.A.
Get access

Abstract

A non-destructive neutron scattering method was developed to precisely measure the uptake of total hydrogen in nuclear grade Zircaloy-4 cladding. The hydriding apparatus consists of a closed stainless steel vessel that contains Zircaloy-4 specimens and hydrogen gas. By controlling the initial hydrogen gas pressure in the vessel and the temperature profile, target hydrogen concentrations from tens of ppm to a few thousands of ppm have been successfully achieved. Following hydrogen charging, the hydrogen content of the hydrided specimens was measured using the vacuum hot extraction method (VHE), by which the samples with desired hydrogen concentration were selected for the neutron study. Small angle incoherent neutron scattering (SAINS) were performed in the High Flux Isotope Reactor (HFIR) at Oak Ridge National Laboratory (ORNL). Our study indicates that a very small amount (≈ 20 ppm) hydrogen in commercial Zircaloy-4 cladding can be measured very accurately in minutes for a wide range of hydrogen concentration by a nondestructive method. The hydrogen distribution in a tube sample was obtained by scaling the neutron scattering rate with a factor, which is determined by calibration process with direct chemical analysis method on the specimen. This scale factor can be used for future test with unknown hydrogen concentration, thus provide a nondestructive method for absolute hydrogen concentration determination.

Type
Articles
Copyright
Copyright © Materials Research Society 2014 

Access options

Get access to the full version of this content by using one of the access options below. (Log in options will check for institutional or personal access. Content may require purchase if you do not have access.)

References

REFERENCES

Chervallier, J. and Aucourier, M., Annu. Rev. Materi. Sci. 18, (1988) 219.CrossRefGoogle Scholar
Yan, Y., Burtseva, T., and Billone, M., “High-Temperature Steam-Oxidation Behavior of Zr-1Nb Cladding Alloy E110,” J. Nucl. Mater. 393, (2009) 433448.CrossRefGoogle Scholar
Brachet, J. C., Portier, L., Hivroz, J., Hamon, D., Guilbert, T., Bedel, T., Yvon, P., Mardon, J. P., and Jacques, P., “Influence of Hydrogen Content on the α/β Phase Transformation Temperature and on the Thermal-Mechanical Behavior of Zy-4, M4 (ZrSnFeV), and M5™ (ZrNbO) Alloys During the First Phase of LOCA Transient,” Zirconium in the Nuclear Industry, ASTM STP 1423, American Society for Testing and Materials (2002) 673–701.CrossRefGoogle Scholar
Billone, M., Yan, Y., Burtseva, T., and Daum, R., “Cladding Embrittlement During Postulated Loss-of-Coolant Accidents,” NUREG/CR-6967, ANL-07/04, July 2008.CrossRefGoogle Scholar
Yan, Y., Blackwell, A. S., Plummer, L. K., Radhakrishnan, B., Gorti, S. B., and Clarno, K. T., “Observation and Mechanism of Hydride in Zircaloy-4 and Local Radial Hydride Induced by High Pressure,” 2013 IHLRWM, Albuquerque, New Mexico, April 28 – May 2, 2013 Google Scholar
Garde, A. M., Comstok, R. J., Pan, G., Baranwal, R., Hallstadius, L., Cook, T., and Carrera, F., “Advanced Zirconium Alloy for PWR Application,” J. ASTM Intl. 7, No. 9 doi:10.1520/JAI103030.CrossRefGoogle Scholar
Chabretou, V., Hoffmann, P. B., Trapp-Pritsching, S., Garner, G., Barberis, P., Rebeyrolle, V., and Vermoyal, J. J., “Ultra Low Tin Quaternary Alloys PWR Performance-Impact of Tin Content on Corrosion Resistance, Irradiation Growth, and Mechanical Properties,” J. ASTM Intl. 8, No. 5, doi:10.1520/JAI103013.CrossRefGoogle Scholar
Yasuda, R., Nakada, M., Matsubayashi, M.. Harada, K., Hatakeyama, Y., and Amano, H., “Application of Hydrogen Analysis by Neutron Imaging Plate Method to Zircaloy Cladding Tubes,” J. Nucl. Mater. 320, (2003) 223230.CrossRefGoogle Scholar
Brosse, M., Lehmann, E., Vontobel, P., and Steibrueck, M., “Quantitative Determination of Absorbed Hydrogen in Oxidized Zircaloy by Means of Neutron Radiography,” Nucl. Instrum. Methods Phys. Res. A, 566, (2006) 739745.Google Scholar
Neutron radiography Handbook (Nuclear Science and Development), Von Der Hardt, P. and Rotter, H. (Eds), D. Reidel Publishing Company, Dorredcht, Holland, 1981 p. 58.CrossRefGoogle Scholar
Lehmann, E.H., Vontobel, P., and Kardjilov, N., Appl. Radiat. Isotopes 61, (2004) 503.CrossRefGoogle Scholar