Creep of the N-1 alloy within the region of polymorphic transformation

Pirogov, E. N.; Алымов, М. И.; Artyukhina, L. L.

doi:10.1007/bf01125022

Cited by 5 publications

(3 citation statements)

References 2 publications

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“…Pirogov et al [30] also investigated the creep behavior of Zr-1Nb in a temperature regime of 607-877°C. The a/a + b-phase boundary as per Zr-Nb phase diagram occurs at $600°C, and thus, the microstructure would transform into a two-phase microstructure with significant b-Zr phase present across the temperature ranges.…”

Section: Creep Characteristics Of Zr-1nb Alloymentioning

confidence: 97%

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Creep behavior of niobium-modified zirconium alloys

Charit

Murty

2008

Journal of Nuclear Materials

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Section: Creep Characteristics Of Zr-1nb Alloymentioning

confidence: 97%

“…Alymov and coworkers [26,[28][29][30]] generated a vast amount of high temperature deformation data in a wide range of conditions. The work was carried out in the single phase regime of the alloy at a temperature range of 377-597°C and a stress range of 10-150 MPa (2 · 10 À4 -4 · 10 À3 E) [26].…”

Section: Creep Characteristics Of Zr-1nb Alloymentioning

confidence: 99%

Creep behavior of niobium-modified zirconium alloys

Charit

Murty

2008

Journal of Nuclear Materials

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“…The strain rate in the two-phase coexistence ð þ Þ region follows a separate mechanism than in the single-phase region. 22,23) For computational convenience, some authors have suggested ad hoc correlations in the mixed-phase region for Zircaloy-4 4,5) or have considered homogenisation according to 11,24) …”

Section: Governing Equationsmentioning

confidence: 99%

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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