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1
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30644468473
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Influence of long service exposures on the thermal-mechanical behavior of Zy-4 and M5™ alloys in LOCA conditions
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paper ID JAI12468
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Portier, L., Bredel, T., Brachet, J.-C., Maillot, V., Mardon, J.-P., and Lesbros, A., "Influence of Long Service Exposures on the Thermal-Mechanical Behavior of Zy-4 and M5™ Alloys in LOCA Conditions," J. ASTM Int., Vol.2, No.2, 2005, paper ID JAI12468 (www.astm.org).
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(2005)
J. ASTM Int.
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, Issue.2
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Portier, L.1
Bredel, T.2
Brachet, J.-C.3
Maillot, V.4
Mardon, J.-P.5
Lesbros, A.6
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2
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76649141996
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Overview of CEA analytical studies on the cladding behavior during and after prototypical LOCA transients
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Brachet, J.-C., Maillot, V., Portier, L., Forgeron, T., Gilbon, D., Mardon, J.-P., Lesbros, A., and Waeckel, N., "Overview of CEA Analytical Studies on the Cladding Behavior During and After Prototypical LOCA Transients," Proceedings of the OECD Ad-Hoc LOCA Meeting, Paris-Issy-lesMoulineaux, 27-28 of June 2006.
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(2006)
Proceedings of the OECD Ad-Hoc LOCA Meeting, Paris-Issy-lesMoulineaux 27-28 of June
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Brachet, J.-C.1
Maillot, V.2
Portier, L.3
Forgeron, T.4
Gilbon, D.5
Mardon, J.-P.6
Lesbros, A.7
Waeckel, N.8
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3
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69549096484
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Influence of hydrogen simulating BU effects on the metallurgical and thermal-mechanical behavior of M5™ and zircaloy-4 alloys under LOCA conditions
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Beijing (Pékin), China, May ICONE1350457.
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Mardon, J.-P., Brachet, J.-C., Portier, L., Maillot, V., Forgeron, T., Lesbros, A., and Waeckel, N., "Influence of Hydrogen Simulating BU Effects on the Metallurgical and Thermal-Mechanical Behavior of M5™ and Zircaloy-4 Alloys Under LOCA Conditions," Proceedings of the 13th International Conference on Nuclear Engineering, Beijing (Pékin), China, May 16-20, 2005, ICONE1350457.
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(2005)
Proceedings of the 13th International Conference on Nuclear Engineering
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Mardon, J.-P.1
Brachet, J.-C.2
Portier, L.3
Maillot, V.4
Forgeron, T.5
Lesbros, A.6
Waeckel, N.7
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4
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0040109968
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Optimization of BWR behavior of stress-relieved zircaloy-4 cladding tubes by upgrading the manufacturing and inspection process
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ASTM International, West Conshohocken, PA
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Mardon, J. P., Charquet, D., and Sevenat, J., "Optimization of BWR Behavior of Stress-Relieved Zircaloy-4 Cladding Tubes by Upgrading the Manufacturing and Inspection Process," Zirconium in the Nuclear Industry; 10th International Symposium, ASTM STP 1245, ASTM International, West Conshohocken, PA, pp. 329-348.
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Zirconium in the Nuclear Industry; 10th International Symposium, ASTM STP 1245
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Mardon, J.P.1
Charquet, D.2
Sevenat, J.3
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5
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0343254679
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Update on the development of advanced Zr alloys for PWR fuel rods claddings
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Portland, March 2-6
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Mardon, J. P., Garner, G., Beslu, P., Charquet, D., and Sevenat, J., "Update on the Development of Advanced Zr Alloys for PWR Fuel Rods Claddings," ANS International Topical Meeting on LWR Fuel Performance, Portland, March 2-6, 1997, pp. 405-412.
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Mardon, J.P.1
Garner, G.2
Beslu, P.3
Charquet, D.4
Sevenat, J.5
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6
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0033892352
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Influence of composition and fabrication process on out-of-pile and in-pile properties of M5 alloy
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G. P. Sabol and G. D. Moan, Eds., ASTM International, West Conshohocken, PA
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Mardon, J. P., Charquet, D., and Sevenat, J., "Influence of Composition and Fabrication Process on Out-of-Pile and In-Pile Properties of M5 Alloy," Zirconium in the Nuclear Industry: 12th International Symposium, ASTM STP 1354, G. P. Sabol and G. D. Moan, Eds., ASTM International, West Conshohocken, PA, 2000, pp. 505-524.
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Zirconium in the Nuclear Industry: 12th International Symposium, ASTM STP 1354
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Mardon, J.P.1
Charquet, D.2
Sevenat, J.3
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7
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70449761114
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The corrosion of the alloy M5™: An overview
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Buenos Aires, Argentina, October
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Thomazet, J., Dalmais, A., Bossis, P., Godlewski, J., Blat, M., and Miquet, A., "The Corrosion of the Alloy M5™: An Overview," IAEA Technical Committee Meeting on Behavior of High Corrosion Resistance Zr-based Alloys, Buenos Aires, Argentina, October 24-28, 2005.
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(2005)
IAEA Technical Committee Meeting on Behavior of High Corrosion Resistance Zr-based Alloys
, pp. 24-28
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Thomazet, J.1
Dalmais, A.2
Bossis, P.3
Godlewski, J.4
Blat, M.5
Miquet, A.6
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8
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76649109533
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Mechanical behavior at room temperature and metallurgical study of low-tin zircaloy-4 and M5TM (ZrNbO) alloys after oxidation at 1000°C and quenching
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Sept. 10-14, IAEA, Halden, Norway.
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Brachet, J.-C., Pelchat, J., Hamon, D., Maury, R., Jacques, P., and Mardon, J.-P., "Mechanical Behavior at Room Temperature and Metallurgical Study of Low-Tin Zircaloy-4 and M5TM (ZrNbO) Alloys After Oxidation at 1000°C and Quenching," Proceedings of TCM on "Fuel Behavior Under Transient and LOCA Conditions," Sept. 10-14, 2001, IAEA, Halden, Norway.
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(2001)
Proceedings of TCM on "Fuel Behavior under Transient and LOCA Conditions
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Brachet, J.-C.1
Pelchat, J.2
Hamon, D.3
Maury, R.4
Jacques, P.5
Mardon, J.-P.6
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9
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33744933196
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Comparison of the high burn-up corrosion of M5TM and low tin zircaloy-4 alloys
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P. Rudling and B. Kammenzind, Ed., ASTM International, West Conshohocken, PA
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Bossis, P., Pêcheur, D., Hanifl, K., Thomazet, J., and Blat, M., "Comparison of the High Burn-up Corrosion of M5TM and Low Tin Zircaloy-4 Alloys," Zirconium in the Nuclear Industry: 14th International Symposium, ASTM STP 1467, P. Rudling and B. Kammenzind, Ed., ASTM International, West Conshohocken, PA, 2006, pp. 494-525.
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(2006)
Zirconium in the Nuclear Industry: 14th International Symposium, ASTM STP 1467
, pp. 494-525
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Bossis, P.1
Pêcheur, D.2
Hanifl, K.3
Thomazet, J.4
Blat, M.5
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10
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76649133256
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Investigations of the microstructure and mechanical properties of prior-beta structure as a function of the oxygen content up to ~ 0.9 wt %," this conference, to be published
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June
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Stern, A., et al, "Investigations of the Microstructure and Mechanical Properties of Prior-Beta Structure as a Function of the Oxygen Content up to ~ 0.9 wt %," This conference, to be published in J. ASTM Int., June 2007.
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J. ASTM Int.
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Stern, A.1
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11
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0018530224
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Pseudo binary zircaloy-oxygen diagram
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Chung, H. M. and Kassner, T. F., "Pseudo Binary Zircaloy-oxygen Diagram," J. Nucl. Mater., Vol.84, 1979, p. 327.
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Chung, H.M.1
Kassner, T.F.2
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12
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8844231312
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The effect of oxygen on the equilibrium beta/alpha + beta transformation temperature of zirconium-niobium alloys
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Hunt, E. L. and Niessen, P., "The Effect of Oxygen on the Equilibrium Beta/Alpha + Beta Transformation Temperature of Zirconium-Niobium Alloys," J. Nucl. Mater., Vol.325, 1970, pp. 134-136.
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14
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76649137529
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Characterization of zirconium hydrides and phase field approach to a mesoscopic-scale modeling of their precipitation
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This conference, to be published in June
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Zhao, Z., Blat-Yrieix, M., et al., "Characterization of Zirconium Hydrides and Phase Field Approach to a Mesoscopic-Scale Modeling of Their Precipitation," This conference, to be published in J. ASTM Int. June 2007.
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J. ASTM Int.
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Zhao, Z.1
Blat-Yrieix, M.2
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15
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70449817336
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Results from LOCA studies at JAEA
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Paris-Issy-Les-Moulineaux, June 27-28
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Nagase, F., "Results from LOCA Studies at JAEA," Proceedings of OECD Ad-Hoc LOCA Meeting, Paris-Issy-Les-Moulineaux, June 27-28, 2006.
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Proceedings of OECD Ad-Hoc LOCA Meeting
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Nagase, F.1
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17
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0036134406
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The dissolution of oxide on α-Zr(1%Nb) and β-Zr(20%Nb) alloys
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DOI 10.1016/S0022-3115(01)00714-0, PII S0022311501007140
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[17] Zhang, C. and Norton, P. R., "The Dissolution of Oxide on Alpha-Zr(l%Nb) and Beta-Zr(20%Nb) Alloys," J. Nucl. Mater., Vol.300, 2002, pp. 7-14. (Pubitemid 34007007)
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Journal of Nuclear Materials
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Zhang, C.1
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33748317874
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Effect of cooling history on cladding ductility under LOCA conditions
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DOI 10.3327/jnst.43.844
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76649098252
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Experimental study of embrittlement of Zr-l%Nb VVER claddings under LOCA-relevant conditions
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March
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Yegorova, L., et al., "Experimental Study of Embrittlement of Zr-l%Nb VVER Claddings Under LOCA-Relevant Conditions," NUREG/IA-0211 Int. Agreement Report, March 2005.
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NUREG/IA-0211 Int. Agreement Report
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Proposed criterion for the oxygen embrittlement of zircaloy-4 fuel cladding
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[21] Sawatzky, A., "A Proposed Criterion for the Oxygen Embrittlement of Zircaloy-4 Fuel Cladding," Zirconium in the Nuclear Industry (4th Conference), ASTM STP 681, ASTM International, West Conshohocken, PA, 1979, pp. 479-496. (Pubitemid 10430953)
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8844262007
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Influence of hydrogen content on the α⇔- ßphase transformation temperatures and on the thermal-mechanical behavior of zircaloy-4, M4 (ZrSnFeV), and M5™ (ZrNbO) alloys during the first phase of LOCA transient
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ASTM STP 1423, June 10-14, Annecy, France
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Brachet, J.-C., Portier, L., et al., "Influence of Hydrogen Content on the α⇔- ßPhase Transformation Temperatures and on the Thermal-mechanical Behavior of Zircaloy-4, M4 (ZrSnFeV), and M5™ (ZrNbO) Alloys During the First Phase of LOCA transient," Zirconium in the Nuclear Industry: 13th International Symposium, ASTM STP 1423, June 10-14, 2001, Annecy, France, pp. 673-701.
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Brachet, J.-C.1
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76649107616
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NUREG/ANL report-to be published.
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Bilione, M., Yan, Y., and Burtseva, T., "Cladding Embrittlement During Postulated Loss-of-Coolant Accidents," NUREG/ANL report-to be published.
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Cladding Embrittlement during Postulated Loss-of-Coolant Accidents
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Billone, M.1
Yan, Y.2
Burtseva, T.3
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