Irradiation Creep Behavior of Zr-Base Alloys

Soniak, A.; L'Hullier, N.; Mardon, J.P.; Rebeyrolle, V.; Bouffioux, P.; Bernaudat, Ch.

doi:10.1520/stp11419s

Cited by 21 publications

(24 citation statements)

References 10 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…It has been found that the Zircaloy RXA model adequately describes the creep behavior of M5 Soniak et al, 2002). The Zircaloy SRA model is used for ZIRLO with a reduction factor of 0.8.…”

Section: Model Development and Comparisonsmentioning

confidence: 99%

See 1 more Smart Citation

Material Property Correlations: Comparisons between FRAPCON-3.4, FRAPTRAN 1.4, and MATPRO

Luscher¹,

Geelhood²

2010

View full text Add to dashboard Cite

The U.S. Nuclear Regulatory Commission uses the computer codes FRAPCON-3 and FRAPTRAN to model steady-state and transient fuel behavior, respectively, in regulatory analysis. In this document, material property correlations for oxide fuels and cladding materials are presented and discussed. Comparisons are made between the material property correlations used in the most recent versions of the codes, Comparisons are also made with MATPRO, which is a compilation of material property correlations with an extensive history of use with various fuel performance and severe accident codes. In addition to model-to-model comparisons, model-to-data comparisons and source codes for the FRAPCON-3.4 and FRAPTRAN 1.4 correlations are provided.iii iv ForewordThe U.S. Nuclear Regulatory Commission uses the computer codes FRAPCON and FRAPTRAN to model steady-state and transient fuel behavior, respectively, in regulatory analysis. To effectively model fuel behavior, material property correlations must be used for a wide range of operating conditions (e.g., temperature and burnup). In this sense, a "material property" is a physical characteristic of the material whose quantitative value is necessary in the analysis process.The consolidated resource for "material properties" cited most often in the literature is MATPRO (as documented in Volume 4 of NUREG/CR-6150). MATPRO is a compilation of fuel and cladding material property correlations with an extensive history of use with fuel performance and severe accident codes. However, consistency among the material property correlations in FRAPCON-3, FRAPTRAN, and MATPRO has never been complete, as the material property correlations in the fuel performance codes have evolved to accommodate recent fuel design changes.

show abstract

“…It has been found that the Zircaloy RXA model adequately describes the creep behavior of M5 Soniak et al, 2002). The Zircaloy SRA model is used for ZIRLO with a reduction factor of 0.8.…”

Section: Model Development and Comparisonsmentioning

confidence: 99%

“…Creep data was obtained from irradiated SRA and RXA tube from Franklin (1983), Soniak et al (2002), and . The relative standard error for the predictions is 14.5 percent for SRA and 21.6 percent for RXA cladding.…”

Section: Model Development and Comparisonsmentioning

confidence: 99%

Material Property Correlations: Comparisons between FRAPCON-3.4, FRAPTRAN 1.4, and MATPRO

Luscher¹,

Geelhood²

2010

View full text Add to dashboard Cite

show abstract

“…To account for the material behaviour on the whole loading range, two different sets of material parameters are used for creep at low stress level (base irradiation) and creep at high stress level (ramp test). In this study, the anisotropic behaviour of the cladding is not taken into account, although the coefficients of Hill's criterion have already been identified from tests performed under various loading conditions (Soniak et al, 2002). This approximation has been made in order to be consistent with former simulations performed with the 3D model of the TOUTATIS application.…”

Section: Claddingmentioning

confidence: 99%

A new phenomenological criterion for pellet–cladding interaction rupture

Michel

Sercombe

Thouvenin

2008

Nuclear Engineering and Design

View full text Add to dashboard Cite

This study is concerned with structural integrity assessment of Pressure Water Reactor's (PWR) fuel rods under pellet-cladding interaction (PCI) loading condition. An important experimental and research cooperative program between EDF, AREVA-NP and the Atomic Energy Commission CEA is achieved in order to get a better understanding of the mechanisms possibly leading to PCI failure, as well as to qualify a PCI resistant rod design. The objectives of this work are: first, to improve the understanding of the pellet mechanical properties impact on cladding local loading with 3D simulations results, and second, to propose a new phenomenological rupture criterion for a better assessment of the failure risk. In this study fuel behaviour modelling under nominal and transient loading conditions is achieved with a multi-dimensional simulation tool called ALCYONE, included in the new fuel software PLEIADES currently co-developed by the CEA and EDF. Cladding loading due to mechanical interaction during power transient stage is first analysed through pellet-cladding interfacial stresses computed in the 3D simulation. Then, a 2D model is proposed in order to establish a correlation between interfacial loading and stress concentration in the cladding. In order to assess the failure risk under PCI a phenomenological criterion based on the membrane circumferential stress in the cladding and shear stresses at pellet-cladding interface is proposed. To compute the shear loading at pellet-cladding interface a new parameter (called W rθ) is introduced. Based on 3D calculations of PCI, it is shown in this paper that pellet fracture properties can have a significant effect on PCI loading.

show abstract

“…The model for the anisotropic viscoplastic strain component has the form identified by Soniak [22] for stressrelieved Zircaloy-4. As shown in Eq.…”

Section: Materials Viscoplastic Behaviormentioning

confidence: 99%

“…This same material batch was used in studies performed by Magnusson [27] in I-SCC tests in iodine vapor using an expanding mandrel technique at an iodine partial pressure of 60 Pa, which corresponds to a saturated effect of the iodine partial pressure on I-SCC susceptibility [28]. They found an I-SCC threshold stress of approximately 300 MPa over the temperature range 320 Ce380 C. It should be noted that the hoop stress in the cladding during these expanding mandrel tests was evaluated by FE using a viscoplastic model for the cladding (Soniak [22]) similar to the one used in the current study.…”

Section: Comparison With Other Researchmentioning

confidence: 99%

Stress corrosion crack initiation of Zircaloy-4 cladding tubes in an iodine vapor environment during creep, relaxation, and constant strain rate tests

Jezequel

Auzoux

Boulch

et al. 2018

Journal of Nuclear Materials

View full text Add to dashboard Cite

OATAO is an open access repository that collects the work of Toulouse researchers and makes it freely available over the web where possible. This is an author-deposited version published in : http://oatao. The experimental results showed that the apparent threshold hoop stress for I-SCC was found to be independent of the test temperature. A model for the time-to-failure of a cladding tube was developed using finite element simulations of the viscoplastic mechanical behavior of the material and a modified Kachanov's damage growth model. The times-to-failure predicted by this model are consistent with the experimental data. a b s t r a c tDuring accidental power transient conditions with Pellet Cladding Interaction (PCI), the synergistic effect of the stress and strain imposed on the cladding by thermal expansion of the fuel, and corrosion by iodine released as a fission product, may lead to cladding failure by Stress Corrosion Cracking (SCC). In this study, internal pressure tests were conducted on unirradiated cold-worked stress-relieved Zircaloy-4 cladding tubes in an iodine vapor environment. The goal was to investigate the influence of loading type (constant pressure tests, constant circumferential strain rate tests, or constant circumferential strain tests) and test temperature (320, 350, or 380 C) on iodine-induced stress corrosion cracking (I-SCC). The experimental results obtained with different loading types were consistent with each other. The apparent threshold hoop stress for I-SCC was found to be independent of the test temperature. SEM micrographs of the tested samples showed many pits distributed over the inner surface, which tended to coalesce into large pits in which a microcrack could initiate. A model for the time-to-failure of a cladding tube was developed using finite element simulations of the viscoplastic mechanical behavior of the material and a modified Kachanov's damage growth model. The times-to-failure predicted by this model are consistent with the experimental data.

show abstract

Irradiation Creep Behavior of Zr-Base Alloys

Cited by 21 publications

References 10 publications

Material Property Correlations: Comparisons between FRAPCON-3.4, FRAPTRAN 1.4, and MATPRO

Material Property Correlations: Comparisons between FRAPCON-3.4, FRAPTRAN 1.4, and MATPRO

A new phenomenological criterion for pellet–cladding interaction rupture

Stress corrosion crack initiation of Zircaloy-4 cladding tubes in an iodine vapor environment during creep, relaxation, and constant strain rate tests

Contact Info

Product

Resources

About