Creep deformation of an unirradiated zircaloy nuclear fuel cladding tube under dry storage conditions

Mayuzumi, Masami; Onchi, Takeo

doi:10.1016/0022-3115(90)90384-y

Cited by 27 publications

(8 citation statements)

References 4 publications

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“…7 and 9 are adequate only when the stress level is very high (so-called power-law breakdown). The previous models contained unrealistic steady-state creep rates and should be modified into a power-law function as (10) In this study, Eqs. 2, 6, and 10 were used for the modeling.…”

Section: Modeling and Discussionmentioning

confidence: 99%

“…Mayuzumi and Onchi [10][11][12] utilized the mechanical equation (Eq. 2) in order to estimate the creep behavior of…”

Section: Previous Models (For Non Irradi-ated Zirconium Alloys)mentioning

confidence: 99%

“…In addition, the model can estimate the long-time creep behavior that would be difficult with a real test, and the behavior under varying creep conditions such as temperature rising or decreasing, stress increase or reduction, etc. Actually, the model estimation of creep has been used in many systems, such as Alloy 617 [15], stainless steel [16], as well as zirconium [9][10][11][12][13].…”

Section: Primary Creep Strain (ε P )mentioning

confidence: 99%

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Modeling of thermal creep behavior in Zr-1.1Nb-0.05Cu alloys

2011

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The power-law dependency is suitable for describing the thermal creep behavior of modern zirconium alloys. In contrast to the previous phenomenological and empirical models, mechanistic approaches with power-law relations were made to explain the creep rates of the Zr-1.1Nb-0.05Cu alloy. For the modeling, the experimental stress and temperature parameters were varied according to the operating conditions of nuclear power plants. It was observed that the creep was controlled by the dislocation glide and climb mechanism. The proposed model explained the experimental data well, and was able to estimate the creep rates for elongated times.

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Section: Modeling and Discussionmentioning

confidence: 99%

“…Mayuzumi and Onchi [10][11][12] utilized the mechanical equation (Eq. 2) in order to estimate the creep behavior of…”

Section: Previous Models (For Non Irradi-ated Zirconium Alloys)mentioning

confidence: 99%

Section: Primary Creep Strain (ε P )mentioning

confidence: 99%

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Modeling of thermal creep behavior in Zr-1.1Nb-0.05Cu alloys

2011

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“…The time hardening relation of Eq. 6, along with variants where the (Àrt) term inside the exponential argument is given in terms of minimum strain rate 11 and raised to a power, 12 have similar applicability to creep in Sn-3.8Ag-0.7Cu and other Pb-free solder alloys under isothermal constant-load creep deformation. In Eq.…”

Section: Introductionmentioning

confidence: 95%

Primary Creep in Sn-3.8Ag-0.7Cu Solder, Part II: Constitutive Creep Model Development and Finite Element Analysis

Shirley

Spelt

2009

Journal of Elec Materi

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A constitutive creep model is presented for Sn-3.8Ag-0.7Cu that incorporates both transient and steady-state creep to provide agreement for both creep and stress relaxation data with a single set of eight coefficients. The model utilizes both temperature-compensated time and strain rate to normalize minimum strain rate and saturated transient creep strain, thereby establishing equivalence between decreased temperature and increased strain rate. The apparent activation energy of steady-state creep, 83.6 kJ/mol, was indicative of both dislocation core and bulk lattice diffusion. A saturation threshold was defined that distinguishes whether transient or steady-state creep is dominant under either static or variable loading.

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“…6 Moreover, any change (or transition) in the deformation mechanism would lead to large uncertainties. 20 However, "no experimental evidence has been found of the validity of utilizing rupture data of the unirradiated cladding for predicting rupture behavior of the spent fuel." 22 Peehs et al 2 and Mayuzumi and Onchi 5,22 prefer to evaluate the spentfuel integrity by predicting the accumulated creep strain with a criterion for a specified strain limit.…”

Section: Larson-miller Parametermentioning

confidence: 99%

The internal pressurization creep of Zr alloys for spent-fuel dry storage feasibility

Murty

2000

JOM

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A short review of creep results on is presented with the express purpose of applying the results to dry-storage feasibility. Data reveal inconsistencies with regard to the underlying creep mechanism at intermediate and high stresses. A lack of relevant results is noted on transitional creep mechanisms as stresses and temperatures are lowered, along with the dangers involved in blind extrapolation of short-term creep results to conditions encountered during dry storage that could lead to nonconservative estimates of creep rates, creep strains, and lifetimes due to the dominance of viscous creep mechanisms at these conditions. The plausible influence of alloying elements, such as niobium and vanadium, on the underlying creep mechanism(s) is enumerated. Further research is warranted on the characterization of creep mechanisms in Zircaloys in terms of not only the mechanical data, but also the microstructural investigations.

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Creep deformation of an unirradiated zircaloy nuclear fuel cladding tube under dry storage conditions

Cited by 27 publications

References 4 publications

Modeling of thermal creep behavior in Zr-1.1Nb-0.05Cu alloys

Modeling of thermal creep behavior in Zr-1.1Nb-0.05Cu alloys

Primary Creep in Sn-3.8Ag-0.7Cu Solder, Part II: Constitutive Creep Model Development and Finite Element Analysis

The internal pressurization creep of Zr alloys for spent-fuel dry storage feasibility

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