Transformation kinetics of zirconium alloys under non-isothermal conditions

Massih, Ali R

doi:10.1016/j.jnucmat.2008.11.033

Cited by 40 publications

(40 citation statements)

References 23 publications

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“…As discussed in our previous paper, 3) oxygen concentration affects the phase transition temperature in Zr alloys, and it is expected to have an impact on the kinetics of phase transition. Thus, strictly speaking, Eq.…”

Section: Discussionmentioning

confidence: 81%

“…For Zircaloy-4, we use T cent ¼ 1;159 K and T span ¼ 44 K. The expression for c is given in Ref. 3) for Zircaloy-4. The steady-state creep strain rate of Zr alloy cladding is expressed by a Norton law 4,5) d" dt ¼ A f ðxÞ expðÀQ=RTÞ…”

Section: Governing Equationsmentioning

confidence: 99%

“…The physical behaviour of cladding during the accident is governed by phase transformation, oxidation, creep deformation, and rupture of zirconium alloy within a time scale of about 120 s. The objective of this note is to delineate a unified generic computational method to account for these phenomena based on empirically attained material property data reported in the literature. We synthesise the previously described kinetics of zirconium alloy phase transformation 3) with the equations for cladding creep, oxidation, and burst 4,5) to calculate the rupture time/temperature during a transient.…”

Section: Introductionmentioning

confidence: 99%

“…A short survey of the literature on zirconium alloy phase transformation behaviour was presented in our previous paper. 3) Similar past modelling approaches comprise the works presented in Refs. 4) and 5), which however, did not include a phase transformation kinetics model.…”

Section: Introductionmentioning

confidence: 99%

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Modelling and Simulation of Reactor Fuel Cladding under Loss-of-Coolant Accident Conditions

Manngård

Massih

2011

J. Nucl. Sci. Technol.

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We present a unified model for calculation of zirconium alloy fuel cladding rupture during a postulated loss-of-coolant accident in light water reactors. The model treats the Zr alloy solid-to-solid phase transformation kinetics, cladding creep deformation, oxidation, and rupture as functions of temperature and time in an integrated fashion during the transient. The fuel cladding material considered here is Zircaloy-4, for which material property data (model parameters) are taken from the literature. We have modelled and simulated single-rod transient burst tests in which the rod internal pressure and the heating rate were kept constant during each test. The results are compared with experimental data on cladding rupture strain, temperature, and pressure. The agreement between computations and measurements in general is satisfactory. The effects of heating rate and rod internal pressure on the rupture strain are evaluated on the basis of systematic parameter variations of these quantities. In the -phase of Zr, the burst strain decreases with increasing heating rate, whereas in the two-phase coexistence ð þ Þ domain and -phase, the situation is more complex. Also, the mechanism for creep deformation in the ð þ Þ domain is not well understood; hence, its mechanistic constitutive relation is presently unknown.

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Section: Discussionmentioning

confidence: 81%

Section: Governing Equationsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Modelling and Simulation of Reactor Fuel Cladding under Loss-of-Coolant Accident Conditions

Manngård

Massih

2011

J. Nucl. Sci. Technol.

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“…During a postulated LOCA, fuel cladding will be subjected to a rapid increase in temperature (up to 750-1200°C) in steam environment, which not only induces a ? b transformations, but also leads to rapid oxidation of Zr and hydrogen uptake [8]. This will greatly deteriorate the performance of Zr alloys in service.…”

Section: Introductionmentioning

confidence: 99%