Extending the application range of a fuel performance code from normal operating to design basis accident conditions

Uffelen, P. Van; Csaba, Gyori; Arndt, Sebastian; Laar, J. van de; Hózer, Zoltán; Spykman, G

doi:10.1016/j.jnucmat.2008.08.043

Cited by 41 publications

(19 citation statements)

References 8 publications

(10 reference statements)

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“…Evaluation was performed for correlations based on E110 alloys Yegorova [2], Solyany [8], AEKI [9], and for Zircaloy based correlations Cathcart-Pawel [10] and Baker-Just [11] also. Very high degree of conservatism for all existing models in Baker-Just correlation is known to be always (too) conservative; therefore, the commentary to non-conservativism at low temperatures is appropriate.…”

Section: Comparison Of Experimental Data and Existing Modelsmentioning

confidence: 99%

Proposal of new oxidation kinetics for sponge base E110 cladding tubes material

Krejčí

Vrtílková

Gajdoš

et al. 2017

EPJ Nuclear Sci. Technol.

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Abstract. Study of high temperature steam oxidation kinetics during the high temperature oxidation was carried out on the sponge base E110 cladding tubes material in the temperature range 600-1300°C. The oxidation kinetics derived from the weight gain measurements showed a parabolic rate law for temperatures 1100°C and higher only. For lower temperatures in range 800-1050°C especially, the parabolic law leads to very conservative prediction. Therefore, the new oxidation kinetics, different from the parabolic law, was designed. The experimental database containing more than 800 data points was compared with the new developed UJP-correlation and available correlations for E110 and Zircaloy alloys. Statistical analysis for all tested correlations was provided.

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Section: Comparison Of Experimental Data and Existing Modelsmentioning

confidence: 99%

Proposal of new oxidation kinetics for sponge base E110 cladding tubes material

Krejčí

Vrtílková

Gajdoš

et al. 2017

EPJ Nuclear Sci. Technol.

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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%

“…IV). Other workers have recommended phase mixing rules for calculating the creep rate 11) and burst stress 12) in the two-phase coexistence ð þ Þ domain of Zr alloys. Hence, it is worthwhile to utilise the output of our phase transition model, that is, the fraction of the -phase as a function of time (temperature), to calculate the creep rate and the burst stress in the ð þ Þ domain, through Eqs.…”

Section: Parametric Studymentioning

confidence: 99%

“…More recent modelling efforts are the works of Forgeron et al 12) and Brachet et al 13) and the implementation of such models in a fuel performance code. 11) Although our general modelling approach is similar to that presented in Refs. 12) and 13), our basic equations for phase transformation kinetics, combined creep and oxidation equations, and mechanical equilibrium are different.…”

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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“…TRANSURANUS is a computer program for the thermal and mechanical analysis of fuel rods in nuclear reactors (see [7][8][9][10]). The TRANSURANUS code consists of a clearly defined mechanical-mathematical framework into which physical models can easily be incorporated.…”

Section: Transuranus Overviewmentioning

confidence: 99%

A Procedure to Address the Fuel Rod Failures During LB-LOCA Transient in Atucha-2 NPP

Adorni

Nevo

D'Auria

et al. 2010

18th International Conference on Nuclear Engineering: Volume 1

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Depending on the specific event scenario and on the purpose of the analysis, the availability of calculation methods that are not implemented in the standard system thermal hydraulic codes might be required. This may imply the use of a dedicated fuel rod thermomechanical computer code. This paper provides an outline of the methodology for the analysis of the 2A LB-LOCA accident in Atucha-2 NPP and describes the procedure adopted for the use of the fuel rod thermomechanical code. The methodology implies the application of best estimate thermalhydraulics, neutron physics, and fuel pin performance computer codes, with the objective to verify the compliance with the specific acceptance criteria. The fuel pin performance code is applied with the main objective to evaluate the extent of cladding failures during the transient. The procedure consists of a deterministic calculation by the fuel performance code of each individual fuel rod during its lifetime and in the subsequent LB-LOCA transient calculations. The boundary and initial conditions are provided by core physics and three-dimensional neutron kinetic coupled thermal-hydraulic system codes calculations. The procedure is completed by the sensitivity calculations and the application of the probabilistic method, which are outside the scope of the current paper.

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Extending the application range of a fuel performance code from normal operating to design basis accident conditions

Cited by 41 publications

References 8 publications

Proposal of new oxidation kinetics for sponge base E110 cladding tubes material

Proposal of new oxidation kinetics for sponge base E110 cladding tubes material

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

A Procedure to Address the Fuel Rod Failures During LB-LOCA Transient in Atucha-2 NPP

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