HYDRIDE FORMATION KINETICS ON GASEOUS HYDRIDING OF ZIRCALOY-4 USING AVRAMI EQUATION

Authors

  • Hadi Suwarno Pusat Teknologi Bahan Bakar Nuklir (PTBBN) - BATAN
  • Rohmad Sigit Pusat Teknologi Bahan Bakar Nuklir (PTBBN) - BATAN

DOI:

https://doi.org/10.17146/jsmi.2017.18.2.4167

Keywords:

Zircaloy-4, Kinetics, Hydriding, Hydride phase, AVRAMI

Abstract

HYDRIDE FORMATION KINETICS ON GASEOUS HYDRIDING OF ZIRCALOY-4 USING AVRAMI EQUATION. Zirconium alloys are mainly material for fuel cladding. Mechanical properties degradation of zircaloy-4 as nuclear fuel cladding is inevitable due to its interaction with hydrogen during normal reactor operation or transient condition. Kinetics analyses of Zircaloy-4 cladding materials at operating temperatures of 500, 550 and 600 oC under hydrogen atmosphere by using Avrami’s method to simulate brittle hydride phase formation and physical observation of the cladding after hydriding have been performed in order to observe the cladding to hydrogen interaction. Kinetic analyses showed that hydriding reaction rate follows the second order with activation energy of 35 kJ/mol. The formation of ε-ZrH phase, an indication of the physical degradation of the tubes, consumed time of 180 minutes at a temperature of 500 oC, 150 minutes at 550 oC, and 100 minutes at 600 oC, respectively. Degradation mechanical properties could be seen visually on the higher hydriding temperature. The cladding materials showed that the tube swelling occurs at a temperature of 550 oC and the tube degraded into pieces occurs at 600 oC. The value of mechanical degradation will be determined by mechanical testing in the next research.

Downloads

Download data is not yet available.

References

. H.H. Hsu and L.W. Tsay. “Effect of Hydride Orientation on Fracture Toughness of Zircloy-4 Cladding.” Journal of Nuclear Materials, vol. 408,

pp. 67-72, Jan. 2011.

. Udagawa Y, Yamaguchi M, Abe H, Sekimura N, Fuketa T. “Ab Initio Study on Plane Defects in Zirconium hydrogen Solid Solution and Zirconium Hydride.”Acta Materialia, vol. 58, no. 11, pp. 3927- 3938,2010.

. Steinbrück, Martin. “Hydrogen Absorption by Zirconium Alloys at High Temperatures.” Journal of NuclearMaterials, vol. 334, no. 1, pp. 58-64, 2004.

. H.H. Hsu and L.W. Tsay. “Fracture Properties of Hydrided Zircaloy-4 Cladding in Recrystallization and Stress-relief Anneal Conditions.” Journal of Nuclear Materials, vol. 422, pp. 116-123, 2012.

. Z. Wang, U. Garbe, H. Li, et al. “Hydride Precipitation and Its Influence on Mechanical Properties of Notched and Unnotched Zircaloy-4

Plates.” Journal of Nuclear Materials, vol. 436, no. 1-3, pp. 84-92, May 2013.

. T. Kubo, Y. Kobayashi, H. Uchikoshi. “Measurements of Delayed Hydride Cracking propagation rate in the radial direction of

Zircaloy-2 Cladding Tubes.” Journal of Nuclear Materials, vol. 427, no. 1-3, pp. 18-29, 2012.

. R. Sigit, H. Suwarno, B. Soegijono.

“Characterization of Zircaloy-4 After Gaseous Hydriding at Temperature Range of 350-600oC.” Atom Indonesia, vol. 42, no. 3, pp. 137-43, 2016.

. Daum, R.S., Y.S. Chu, and A.T. Motta. “Identification and Quantification of Hydride Phases in Zircaloy-4 Cladding Using Synchrotron

X-Ray Diffraction.” Journal of Nuclear Materials, vol. 392, no. 3, pp. 453-463, 2009.

. Suwarno, H. “Development of TRIGA Fuel Fabrication by Powder Technique.” Atom Indonesia, vol. 40, no. 3, pp. 113-120, 2014.

. M. Songolzadeh, M. Soleimani, and M.T. Ravanchi. “Using modified Avrami Kinetic and Two Component Isotherm Equation for Modeling of CO2 /N2 Adsorption Over a 13X Zeolite Bed.”

Journal of National Gas Science Engineering, vol. 27, no. 2, pp. 831-841, 2015.

. Parkison, A.J. “Hydride Production in Zircaloy-4 as a Function Time and Temperature.” Thesis, Texas A&M University, Texas, May, 2008.

. Sinha, I., and R. K. Mandal. “Avrami Exponent Under Transient and Heterogeneous Nucleation TransformationConditions.” Journal of NonCrystallineSolids, vol. 357, no. 3, pp. 919-925, 2011

. Blackmur, M S, J D Robson, M Preuss, O Zanellato, R J Cernik, S Shi, F Ribeiro,and J Andrieux. “Zirconium HydridePrecipitation Kinetics in Zircaloy-4Observed with Synchrotron X-RayDiffraction.” Journal Of Nuclear Materials, vol. 464, pp. 160-69, 2015.

. T.B. Massalski, H. Okamoto, P.R. Subramanian. “Binary Alloys Phase Diagrams. The American Society for Metals,” 2nd, Ed., vol. 3, Ohio, USA, 1990, pp. 2070.

. E. Torres, J. Desquines, M.C. Baietto, and A. Ambard, “Adsorption and Diffusion of Hydrogen in Zircaloy-4.” in Conference of Fontevraud 8:

“Contribution of Materials Investigations and Operating Experience to LWRs’ Safety, Performance and Reliability’, 14-18 September, 2014, pp. 351-360.

. H.H. Shen, X.T. Zu, B. Chen, C. Q. Huang, and K. Sun. “Direct Observation of Hydrogenation and dehydrogenation of a zirconium alloy.” Journal of Alloys and Compounds., vol. 659, pp. 23-30, 2016.

. J. Wei, P. Frankel, E. Polatidis, M. Blat et all. “The Effect of Sn on Autoclave Corrosion Performance and Corrosion Mechanism in Zr-Sn-Nb Alloys.”Acta Materialia, vol. 61, no. 11,pp. 4200-4214, 2013.

. H.H. Hsu, M.F. Chiang, Y.C. Chen. “The Influence of Hydride on Fracture Toughness of Recrystallized Zircaloy-4 Cladding.” Journal of Nuclear Material, vol. 447, pp. 56-62, 2014.

. P. Vizcaino,P.B. Bozzano,A.V. Flores,P.B. Bozzano, A.D. Banchik, R.A. Vercaci, and R.O. Rios. “Hydrogen Solubility and Microstructural

Changes in Zircaloy-4 due to Neutron Irradiation.” Journal of ASTM International, vol. 8, no. 1, pp. 128-148, 2011.

. K.V. Mani Krishna, D. Srivastava, G.K. Dey, V. Hiwarkar, I. Samadjar and S. Banerjee. “Role of Grain/Phase Boundary Nature on The Formation of Hydrides in Zr-25%NbAlloy.” Journal of Nuclear Materials, vol. 414, no. 2, pp. 270-275. 2011.

. I.S. Dupim, J.M.L. Moreira, S.L. Silve,C.C.G. eSilva, O.N. Jr, and R.G. Gomide. “Study on The Hydrogenation of Zircaloy-4.” Journal of Nuclear

Materials, vol. 427, no. 1-3, pp. 121-125, 2012.

. A.H. Menibus, Q. Auzoux, O. Dieye, P. Berger, S. Bosonnet, E. Foy V. McDonald, J. Besson and J. Crepin. “Formation and Characterization of

Hydride Blister in Zircaloy-4 Cladding Tubes”, Journal of Nuclear Materials, vol. 449, no. 1-3, pp. 132-147, 2014.

. A. Pshenichnikov, J. Stuckert, and M. Walter, M. “Microstructure and Mechanical Properties of Zircaloy-4 Cladding Hydrogenated at Temperatures Typical for Loss-of-CoolantAccident (LOCA) Conditions.” Nuclear Engineering Design, vol. 283, pp. 33-39, 2015.

. S. Sobieszczyk andS. Sobieszcky. “HydrogenEnhanced Degradation and Oxide Effects in Zirconium Alloys for Nuclear Applications.”

International Journal of Hydrogen Energy, vol. 36, no. 14, pp. 8619-8629, 2011.

Downloads

Published

31-01-2017

How to Cite

Hadi Suwarno, & Rohmad Sigit. (2017). HYDRIDE FORMATION KINETICS ON GASEOUS HYDRIDING OF ZIRCALOY-4 USING AVRAMI EQUATION. Jurnal Sains Materi Indonesia, 18(2), 68–73. https://doi.org/10.17146/jsmi.2017.18.2.4167