Assessment of data and criteria for cladding burst in loss-of-coolant accidents
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[1] Kenji Yoshida,et al. Failure Correlation for Zircaloy-2 Fuel Cladding under High Temperature Transient Conditions , 1987 .
[2] Zoltán Hózer,et al. Ballooning Experiments with VVER Cladding , 2005 .
[3] A. Massih. High-temperature creep and superplasticity in zirconium alloys , 2013 .
[4] A. Massih,et al. Transformation kinetics of alloys under non-isothermal conditions , 2009, 0905.2276.
[5] A. Massih. An evaluation of high-temperature creep of zirconium alloys : data versus models , 2014 .
[6] John Paul Foster,et al. ZIRLO TM Cladding Improvement , 2008 .
[7] Hee M. Chung. FUEL BEHAVIOR UNDER LOSS-OF-COOLANT ACCIDENT SITUATIONS , 2005 .
[8] Fj Erbacher,et al. Zircaloy Fuel Cladding Behavior in a Loss-of-Coolant Accident: A Review , 1987 .
[9] A. Motta,et al. Zirconium Alloys in Nuclear Applications , 2006 .
[10] J. Schemel,et al. Effect of Beta Quenching on the Microstructure and Corrosion of Zircaloys , 1987 .
[11] Tero Manngård,et al. Evaluation of the Halden IFA-650 loss-of-coolant accident experiments 2, 3 and 4 , 2014 .
[12] F. J. Erbacher,et al. Cladding deformation and emergency core cooling of a pressurized water reactor in a LOCA. Summary description of the REBEKA program , 1990 .
[13] J. C. Brachet,et al. Experimental determination of creep properties of Zirconium alloys together with phase transformation , 2004 .
[14] F. J. Erbacher,et al. Experiments on ballooning in pressurized and transiently heated zircaloy-4 tubes , 1988 .
[15] S. H. Jury,et al. Zirconium metal-water oxidation kinetics. IV. Reaction rate studies. [BWR:PWR] , 1977 .
[16] J. van de Laar,et al. Extending the application range of a fuel performance code from normal operating to design basis accident conditions , 2007 .
[17] M. Mayuzumi,et al. Creep deformation and rupture properties of unirradiated Zircaloy-4 nuclear fuel cladding tube at temperatures of 727 to 857 K , 1990 .
[18] T. F. Kassner,et al. Pseudobinary zircaloy-oxygen phase diagram , 1979 .
[19] William F. Lyon,et al. Capabilities of the FALCON Steady State and Transient Fuel Performance Code , 2004 .
[20] A. Massih. Transformation kinetics of zirconium alloys under non-isothermal conditions , 2009 .
[21] G. Schanz,et al. Oxidation kinetics and related phenomena of zircaloy-4 fuel cladding exposed to high temperature steam and hydrogen-steam mixtures under PWR accident conditions , 1987 .
[22] M. Pathak,et al. Burst criterion for zircaloy-4 fuel cladding in an inert environment , 2013 .
[23] C. Bernaudat,et al. Experiment and Modeling of Advanced Fuel Rod Cladding Behavior Under LOCA Conditions: Alpha-Beta Phase Transformation Kinetics and EDGAR Methodology , 2000 .
[24] R. O. Meyer,et al. Cladding swelling and rupture models for LOCA analysis. Technical report , 1980 .
[25] Hermann Riedel,et al. Fracture at high temperatures , 1987 .
[26] Mohd. Kaleem Khan,et al. A review on the clad failure studies , 2011 .
[27] F. J. Erbacher,et al. Burst criterion of Zircaloy fuel claddings in a loss-of-coolant accident , 1982 .
[28] H. E. Rosinger. A model to predict the failure of zircaloy-4 fuel sheathing during postulated loca conditions , 1984 .
[29] C. Allibert,et al. Solid state phase equilibria of zircaloy-4 in the temperature range 750–1050°C , 1982 .
[30] L. Sepold,et al. LWR fuel rod behavior in the FR2 in-pile tests simulating the heatup phase of a LOCA. Final report , 1983 .
[31] Zoltán Hózer,et al. Experimental database of E110 claddings under accident conditionsAEKI-FRL-2007-123-01/01, NEA-1799 IFPE/AEKI-EDB-E110 , 2007 .
[32] F. J. Erbacher,et al. A review of zircaloy fuel cladding behavior in a loss-of-coolant accident , 1985 .
[33] A. Massih,et al. Thermodynamic evaluation of the Nb–O–Zr system , 2007 .
[34] F. J. Erbacher,et al. Studies on Zircaloy Fuel Clad Ballooning in a Loss-of-Coolant Accident—Results of Burst Tests with Indirectly Heated Fuel Rod Simulators , 1979 .
[35] G Hofmann,et al. Zirconium Cladding Deformation in a Steam Environment with Transient Heating , 1979 .
[36] Ali R Massih,et al. Review of experimental data for modelling LWR fuel cladding behaviour under loss of coolant accident conditions , 2007 .