Ultra Low Tin Quaternary Alloys PWR Performance—Impact of Tin Content on Corrosion Resistance, Irradiation Growth, and Mechanical Properties

Chabretou, V.; Hoffmann, P. B.; Trapp-Pritsching, S.; Garner, G.; Barbéris, Pierre; Rebeyrolle, V.; Vermoyal, J. J.

doi:10.1520/stp49382t

Cited by 4 publications

(6 citation statements)

References 9 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…The free growth results of the empty material test tubes are therefore given as illustrative as one contribution to fuel rod elongation. Growth breakaway has not been observed on M5 ® nor on quaternary alloy fuel rod elongations within the usual FA fluence irradiation range [4,9]. The general microstructure of Q12™ alloy after irradiation is similar to the microstructure of Zr1Nb0.3Sn0.1Fe, Zr1Nb0.3Sn0.2Fe and M5 ® alloys for similar irradiation fluences.…”

Section: Results Of Free-growth Testsmentioning

confidence: 63%

“…1a) r with sizes similar to the M5 ® as the grain size is not dependent on the alloy composition [4]. The highest iron content quaternary alloy (0.2%) contains some FCC (Zr,Nb)4Fe2 second phase particles (SPPs) [4]. Zy-4 shows the standard RXA Zy-4 microstructure with hexagonal Zr(Fe,Cr)2 Laves phases evenly dispersed throughout the matrix [7].…”

Section: Chemical Composition and Microstructure Before Irradiationmentioning

confidence: 97%

“…The grains are equiaxed (FIG. 1a) r with sizes similar to the M5 ® as the grain size is not dependent on the alloy composition [4]. The highest iron content quaternary alloy (0.2%) contains some FCC (Zr,Nb)4Fe2 second phase particles (SPPs) [4].…”

Section: Chemical Composition and Microstructure Before Irradiationmentioning

confidence: 97%

“…Quaternary alloys were manufactured in the similar way as M5 ® . Details of the processing route as well as an extensive out-of-pile characterization program (microstructure, texture, mechanical properties and creep and corrosion behavior) have all be given in previous publications and will not be discussed here [4,5]. All the materials are fully recrystallized.…”

Section: Chemical Composition and Microstructure Before Irradiationmentioning

confidence: 99%

“…The impact of iron is said beneficial for corrosion behavior. The behavior of this alloy was tested under irradiation in PWR and has shown, in comparison to M5 ® , improvement in irradiation creep strength [4,5,6].…”

Section: Introductionmentioning

confidence: 99%

See 4 more Smart Citations

Microstructural Evolution of Q12TM Alloy Irradiated in PWRs and Comparison with Other Zr Base Alloys

Doriot

Verhaeghe

Soniak-Defresne

et al. 2018

Zirconium in the Nuclear Industry: 18th International Symposium

View full text Add to dashboard Cite

Based on the M5 ® alloy metallurgy, the Q12™ alloy (Zr-1Nb-0.5Sn-0.1Fe) was developed by AREVA NP for structural components, with ultra-low Sn addition and slightly increased Fe content. The behavior of this alloy was tested under irradiation in PWR and has shown, in comparison to M5 ® , improvement in irradiation creep strength and similar free growth. The present paper provides results on dimensional stability and details the microstructural evolution of Q12™ alloy under neutron irradiation in PWR. The microstructural evolution under irradiation of Q12™ was studied for fast neutron fluences up to 13x10 25 n/m 2 (E>1 MeV) with Analytical Transmission Electron Microscopy observations, focused on radiation-enhanced needle-like particles, Laves Phases, and linear density of -component loops. These results are compared with other quaternary Zr-Nb-Sn-Fe alloys and with M5 ®. All these results allow a general discussion about microstructural evolution and behavior under irradiation of quaternary type alloys compared to M5 ® alloy. This study, in agreement with previous works on Zr1Nb and quaternary alloys, seems to show that increasing the iron content with the presence of niobium and tin will decrease the component loop linear density and delay the growth breakaway.

show abstract

Section: Results Of Free-growth Testsmentioning

confidence: 63%

Section: Chemical Composition and Microstructure Before Irradiationmentioning

confidence: 97%

Section: Chemical Composition and Microstructure Before Irradiationmentioning

confidence: 97%

Section: Chemical Composition and Microstructure Before Irradiationmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

See 3 more Smart Citations

Microstructural Evolution of Q12TM Alloy Irradiated in PWRs and Comparison with Other Zr Base Alloys

Doriot

Verhaeghe

Soniak-Defresne

et al. 2018

Zirconium in the Nuclear Industry: 18th International Symposium

View full text Add to dashboard Cite

show abstract

Current status of materials development of nuclear fuel cladding tubes for light water reactors

Duan

Yang

Satoh

et al. 2017

Nuclear Engineering and Design

273

View full text Add to dashboard Cite

Damage Build-Up in Zirconium Alloys During Mechanical Processing: Application to Cold Pilgering

Gaillac

Lemaignan

Barbéris

2012

Zirconium in the Nuclear Industry: 16th International Symposium

View full text Add to dashboard Cite

Cold pilgering of zirconium alloys containing high content of alloying elements may be a critical issue regarding surface defects or serious cracks. A better knowledge of damaging mechanisms during pilgering is a way for optimizing the cold forming routes of cladding tubes. Behavior of Zircaloy-4, M5™ (M5™ is a trademark of AREVA NP) and Zr-Nb-Sn-Fe alloys under damaging conditions were investigated for this purpose. Cold pilgering is a cyclic deformation process. Depending on its position inside the grooves of the rolls, material is strained alternately in compressive and tensile modes. Thus, materials were first tested under low cycle fatigue (LCF) deformation routes. LCF tests showed that the differences observed in the number of cycles to failure between alloys are mainly a function of the differences in fracture toughness. Fractography of the fatigue and toughness tests samples also showed that the final propagation of the crack is always ductile, meaning that toughness is the function of the ductile tearing damage mechanisms at the crack tip. Therefore, tensile tests of notched axisymmetric samples were used to study the ductile damage build-up mechanisms, by varying the stress triaxiality. A detailed analysis of the fractured samples was used to quantify a ductile damage accumulation parameter, function of the deformation and the stress triaxiality. Size and repartition of second phase particles, grain to grain misorientations, grain size, and texture were identified as the main metallurgical parameters having an effect in the ductile damage by nucleation, growth, and coalescence of voids. These experimental results, combined with the material mechanical history, provided by numerical modeling of the cold pilgering process, are now used to improve the forming routes of cladding tubes, both by a mechanical way (cold pilgering stress state) and a metallurgical one (microstructure of alloys used for tubes rolling).

show abstract

Ultra Low Tin Quaternary Alloys PWR Performance—Impact of Tin Content on Corrosion Resistance, Irradiation Growth, and Mechanical Properties

Cited by 4 publications

References 9 publications

Microstructural Evolution of Q12TM Alloy Irradiated in PWRs and Comparison with Other Zr Base Alloys

Microstructural Evolution of Q12TM Alloy Irradiated in PWRs and Comparison with Other Zr Base Alloys

Current status of materials development of nuclear fuel cladding tubes for light water reactors

Damage Build-Up in Zirconium Alloys During Mechanical Processing: Application to Cold Pilgering

Contact Info

Product

Resources

About