J. P. Abriata and J. C. Bolcich, The Nb-Zr (Niobium-Zirconium) system. Bulletin of Alloy Phase Diagrams, pp.1-34, 1982.

J. P. Abriata, J. Garcés, and R. A. Versaci, The O-Zr (Oxygen-Zirconium) system. Bulletin of Alloy Phase Diagrams, pp.2-116, 1986.

I. Aitchison and B. Cox, Interpretation of Fractographs of SCC in Hexagonal Metals, CORROSION, vol.28, issue.3, pp.1-83, 1972.
DOI : 10.5006/0010-9312-28.3.83

I. Part, Influence of microstructure on the hydride embrittlement in Zircaloy-4 at 20°C and 350°C

L. Baker and L. C. Just, Studies of metal-water reactions at high temperatures : III. Experimental and theorical studies of zirconium-water reaction, 1962.

L. Barrow, A. T. Barrow, J. Almer, and M. R. Daymond, The Zr20Nb???H phase diagram and the characterisation of hydrides in ??-Zr, Journal of Nuclear Materials, vol.442, issue.1-3, pp.1-3, 2013.
DOI : 10.1016/j.jnucmat.2013.08.031

G. Bertolino, G. Meyer, P. Ipiña, and J. , Effects of hydrogen content and temperature on fracture toughness of Zircaloy-4, Journal of Nuclear Materials, vol.320, issue.3, pp.3-272279, 2003.
DOI : 10.1016/S0022-3115(03)00193-4

B. Ammar and Y. , traitements thermomécaniques des colonies de lamelles parallèles du Zircaloy-4 trempé-?, Thèse de Doctorat, École Nationale Supérieure des Mines de Saint, 2012.

M. Billone, Y. Yan, T. Burtseva, and R. Daum, Cladding embrittlement during postulated loss-of-coolant accidents, Report, pp.6967-6974, 2008.
DOI : 10.2172/946677

P. Boisot and G. Béranger, Variations des paramètres cristallins de la solution solide alpha zirconium-oxygène en fonction de la teneur en oxygène, C.R. Acad. Sc. Paris -Série C, vol.269, p.587590, 1969.

S. Boutin and S. Graff, A New LOCA safety demonstration in France, TopFuel 2015, pp.427-436, 2015.

J. Brachet, D. Hamon, J. Béchade, P. Forget, C. Toffolon-masclet et al., Quantification of the chemical elements partitioning within pre-hydrided Zircaloy-4 after high temperature steam oxidation as a function of the final cooling scenario (LOCA conditions) and consequences on the (local) materials hardening. IAEA technical meeting on fuel behaviour and modelling under severe transient and LOCA conditions, pp.18-21, 2011.

J. Brachet, D. Hamon, and C. Raepsaet, Capability of EPMA and µ-ERDA to quantify the micro-chemical partitioning within nuclear fuel cladding materials after a LOCA transient, pp.29-30, 2012.

J. Brachet, L. Portier, T. Forgeron, J. Hivroz, D. Hamon et al., Influence of hydrogen content on the alpha/bêta transformation temperatures and on the thermal-mechanical behavior of Zy-4, M4(ZrSnFeV) and M5?(ZrNbO) alloys during the first phase of LOCA transient, Zirconium in Nuclear Industry: 13th International Symposium, ASTM STP 1423, pp.673-701, 2002.

J. Brachet, C. Toffolon-masclet, D. Hamon, T. Guilbert, G. Trego et al., Oxygen, Hydrogen and Main Alloying Chemical Elements Partitioning Upon Alpha??????Beta Phase Transformation in Zirconium Alloys, Solid State Phenomena, vol.172, issue.174, pp.172-174, 2011.
DOI : 10.4028/www.scientific.net/SSP.172-174.753

J. Brachet, V. Vandenberghe-maillot, L. Portier, D. Gilbon, A. Lesbros et al., Hydrogen content, preoxidation, and cooling scenario effects on postquench microstructure and mechanical properties of Zircaloy-4 and M5 ® alloys in LOCA conditions, Journal of ASTM International, vol.5, p.5, 2008.

L. R. Bunnell, J. L. Bates, and G. B. Mellinger, Some high-temperature properties of Zircaloy-oxygen alloys, Journal of Nuclear Materials, vol.116, issue.2-3, pp.2-219, 1983.
DOI : 10.1016/0022-3115(83)90106-X

W. G. Burgers, On the process of transition of the cubic-body-centered modification into the hexagonal-close-packed modification of zirconium, Physica, vol.1, issue.7-12, pp.7-12, 1934.
DOI : 10.1016/S0031-8914(34)80244-3

A. Cabrera, Modélisation du comportement mécanique 'post-trempe', après oxydation à haute température des gaines de combustible des réacteurs à eau pressurisée, Thèse de Doctorat, 2012.

A. Cabrera and N. Waeckel, A strength based approach to define LOCA limits, TopFuel 2015, pp.407-416, 2015.

O. Canet, M. Latroche, F. Bourée-vigneron, and A. Percheron-guégan, Structural study of Zr(Cr1?????Fe??)2D?? (0.4 ????? ??? 0.75; 2 <?? < 3) by means of neutron powder diffraction, Journal of Alloys and Compounds, vol.210, issue.1-2, pp.1-129134, 1994.
DOI : 10.1016/0925-8388(94)90127-9

G. J. Carpenter, The dilatational misfit of zirconium hydrides precipitated in zirconium, Journal of Nuclear Materials, vol.48, issue.3, p.264266, 1973.
DOI : 10.1016/0022-3115(73)90022-6

C. Chauvy, P. Barberis, and F. Montheillet, Microstructure transformation during warm working of ??-treated lamellar Zircaloy-4 within the upper ??-range, Materials Science and Engineering: A, vol.431, issue.1-2, pp.1-2, 2006.
DOI : 10.1016/j.msea.2006.05.031
URL : https://hal.archives-ouvertes.fr/hal-00292933

Y. Chen, X. Wan, F. Li, Q. Wang, and Y. Liu, The behavior of hydrogen in high temperature titanium alloy Ti-60, Materials Science and Engineering: A, vol.466, issue.1-2, pp.1-2, 2007.
DOI : 10.1016/j.msea.2007.02.081

R. Chosson, Étude expérimentale et modélisation du comportement en fluage sous pression interne d'une gaine en alliage de zirconium oxydée en atmosphère vapeur, Thèse de Doctorat, 2014.

H. M. Chung and T. F. Kassner, Embrittlement criteria for Zircaloy fuel cladding applicable to accident situations in light-water reactors : summary report, pp.1344-79, 1980.

J. Goldak, L. Lloyd, and C. Barrett, Lattice parameters thermal expansions and Grüneisen coefficients of zirconium 4.2 to 1130 K, Physical Review, vol.144, pp.2-478, 1966.

D. Gosset, L. Saux, and M. , In-situ X-ray diffraction analysis of zirconia layer formed on zirconium alloys oxidized at high temperature, Journal of Nuclear Materials, vol.458, pp.245-252, 2015.
DOI : 10.1016/j.jnucmat.2014.12.067

D. Gosset, L. Saux, M. Simeone, D. Gilbon, and D. , New insights in structural characterization of zirconium alloys oxidation at high temperature, Journal of Nuclear Materials, vol.429, issue.1-3, pp.1-3, 1924.
DOI : 10.1016/j.jnucmat.2012.05.003

C. Grandjean and G. Hache, A state-of-the-art review of past programmes devoted to fuel behaviour under loss-of-coolant accident conditions. Part 3. Cladding oxidation. Resistance to quench and post-quench loads, 2008.

M. Grange, J. Besson, and E. Andrieu, Anisotropic behavior and rupture of hydrided ZIRCALOY-4 sheets, Metallurgical and Materials Transactions A, vol.19, issue.8, pp.3-679690, 1998.
DOI : 10.1007/BF02674025

M. Große and C. Goulet, First results of neutron radiography and tomography of QUENCH-L0 cladding tubes, Quench Workshop 2010. KIT, Allemagne, pp.16-18, 2010.

M. Große, J. Stuckert, M. Steinbrück, and A. Kaestner, Secondary hydriding during LOCA ??? Results from the QUENCH-L0 test, Journal of Nuclear Materials, vol.420, issue.1-3, pp.1-3, 2012.
DOI : 10.1016/j.jnucmat.2011.11.045

M. Große, M. Van-den-berg, C. Goulet, E. Lehmann, and B. Schillinger, In-situ neutron radiography investigations of hydrogen diffusion and absorption in zirconium alloys. Proceeding of the Ninth World Conference on Neutron Radiography ( " The Big-5 on Neutron Radiography, Nuclear Instruments and Methods in Physics Research Section A Accelerators, Spectrometers, Detectors and Associated Equipment, pp.1-253, 2011.

M. He, Caractérisation du comportement à rupture des alliages de zirconium de la gaine du crayon combustible des centrales nucléaires dans la phase post-trempe d'un APRP, Thèse de Doctorat, 2012.

A. Hellouin-de-menibus, Formation de blisters d'hydrures et effet sur la rupture de gaines en Zircaloy-4 en conditions d'accident d'injection de réactivité, Thèse de doctorat, 2012.

A. Hellouin-de-menibus, Q. Auzoux, O. Dieye, P. Berger, S. Bosonnet et al., Formation and characterization of hydride blisters in Zircaloy-4 cladding tubes, Journal of Nuclear Materials, vol.449, issue.1-3, pp.1-3, 2014.
DOI : 10.1016/j.jnucmat.2014.03.006
URL : https://hal.archives-ouvertes.fr/hal-00980723

X. Hu, K. A. Terrani, and B. D. Wirth, Hydrogen desorption kinetics from zirconium hydride and zirconium metal in vacuum, Journal of Nuclear Materials, vol.448, issue.1-3, pp.87-95, 2014.
DOI : 10.1016/j.jnucmat.2014.01.028

D. Kaddour, Fluage isotherme et anisotherme dans les domaines monophasés (? et ?) et biphasés (? + ?) d'un alliage Zr-1 %NbO, Thèse de Doctorat, 2004.

S. Kass, The development of the Zircaloys. OSTI ID: 4749323, Report Number, 1962.

J. J. Kearns, Terminal solubility and partitioning of hydrogen in the alpha phase of zirconium, Zircaloy-2 and Zircaloy-4, Journal of Nuclear Materials, vol.22, issue.3, pp.292-303, 1967.
DOI : 10.1016/0022-3115(67)90047-5

J. H. Kim, M. H. Lee, B. K. Choi, and Y. H. Jeong, Effects of oxide and hydrogen on the circumferential mechanical properties of Zircaloy-4 cladding, Nuclear Engineering and Design, vol.236, issue.18, pp.18-18671873, 2006.
DOI : 10.1016/j.nucengdes.2006.02.010

E. H. Kisi and C. J. Howard, Cristal structures of zirconia phases and their interrelation, Key Engineering Materials, pp.153-154, 1998.

K. Komatsu, Y. Takada, M. Mizuta, and S. Takahashi, The effects of oxidation temperature and slow-cooldown on ductile-brittle behavior of Zircaloy fuel cladding, Specialist Meeting on the Behavior of Water Reactor Fuel Elements under Accident Conditions, pp.13-19, 1976.

L. Lanzani and M. Ruch, Comments on the stability of zirconium hydride phases in Zircaloy, Journal of Nuclear Materials, vol.324, issue.2-3, pp.2-3, 2004.
DOI : 10.1016/j.jnucmat.2003.09.013

N. A. Leech and A. Garlick, The influence of environment on the formation of fluting microstructures during fracture of Zircaloy, Journal of Nuclear Materials, vol.125, issue.1, pp.19-24, 1984.
DOI : 10.1016/0022-3115(84)90511-7

L. Saux and M. , Comportement et rupture de gaines en Zircaloy?4 détendu vierges, hydrurées ou irradiées en situation accidentelle de type RIA, Thèse de Doctorat, 2008.

L. Saux, M. Besson, J. Carassou, S. Poussard, C. Averty et al., A model to describe the anisotropic viscoplastic mechanical behavior of fresh and irradiated Zircaloy-4 fuel claddings under RIA loading conditions, Journal of Nuclear Materials, vol.378, pp.1-60, 2008.
URL : https://hal.archives-ouvertes.fr/hal-00311854

L. Saux, M. Besson, J. Carassou, S. Poussard, C. Averty et al., Behavior and failure of uniformly hydrided Zircaloy-4 fuel claddings between 25 °C and 480 °C under various stress states, including RIA loading conditions, Engineering Failure Analysis, vol.17, pp.3-683700, 2010.
URL : https://hal.archives-ouvertes.fr/hal-00461500

L. Saux, M. Vandenberghe, V. Crébier, P. Brachet, J. Gilbon et al., Influence of steam pressure on the high temperature oxidation and post-cooling mechanical properties of Zircaloy-4 and M5? Cladding (LOCA Conditions), Zirconium in the Nuclear Industry : 17th International Symposium, ASTM STP 1543, pp.1002-1053, 2014.

S. Lynch, Hydrogen embrittlement phenomena and mechanisms, Corrosion Reviews, vol.85, issue.3-4, pp.3-4, 2012.
DOI : 10.1080/14786437408213555

J. P. Mardon, G. L. Garner, and P. B. Hoffmann, M5 ® a breakthrough in Zr Alloy, Proceedings of 2010 LWR Fuel Performance, pp.26-29, 2010.

X. Ma, C. Toffolon-masclet, T. Guilbert, D. Hamon, and J. Brachet, Oxidation kinetics and oxygen diffusion in low-tin Zircaloy-4 up to 1523K, Journal of Nuclear Materials, vol.377, issue.2, pp.359-369, 2008.
DOI : 10.1016/j.jnucmat.2008.03.012

M. Ma, W. Xiang, B. Tang, L. Liang, L. Wang et al., Non-isothermal and isothermal hydrogen desorption kinetics of zirconium hydride, Journal of Nuclear Materials, vol.467, p.349356, 2015.
DOI : 10.1016/j.jnucmat.2015.10.004

. Ministère-de-l-'écologie and . Du-développement-durable-et-de-l-'énergie, Schéma d'un assemblage de combustible nucléaire, 2014.

S. Min, M. Kim, and K. Kim, Cooling rate- and hydrogen content-dependent hydride reorientation and mechanical property degradation of Zr???Nb alloy claddings, Journal of Nuclear Materials, vol.441, issue.1-3, pp.1-3, 2013.
DOI : 10.1016/j.jnucmat.2013.06.006

S. Mishra, K. S. Sivaramakrihnan, and M. K. Asundi, Formation of the gamma phase by a peritectoid reaction in the zirconium-hydrogen system, Journal of Nuclear Materials, vol.45, issue.3, pp.3-235, 1972.
DOI : 10.1016/0022-3115(72)90170-5

K. E. Moore and W. A. Young, Phase studies of the Zr-H system at high hydrogen concentrations, Journal of Nuclear Materials, vol.27, issue.3, pp.3-316, 1968.
DOI : 10.1016/0022-3115(68)90090-1

F. Nagase and T. Fuketa, Behavior of Pre-hydrided Zircaloy-4 Cladding under Simulated LOCA Conditions, Journal of Nuclear Science and Technology, vol.19, issue.2, pp.2-209, 2005.
DOI : 10.1080/18811248.1982.9734128

B. Nath, G. W. Lorimer, and N. Ridley, Effect of hydrogen concentration and cooling rate on hydride precipitation in ?-zirconium, Journal of Nuclear Materials, vol.58, pp.2-153, 1975.

A. Padel and A. Groff, Variation du module de young du zirconium ?? en fonction de la temperature, Journal of Nuclear Materials, vol.59, issue.3, pp.3-325, 1976.
DOI : 10.1016/0022-3115(76)90066-0

A. Pshenichnikov, J. Stuckert, and W. M. , Hydrides and fracture of pure zirconium and Zircaloy-4 at temperatures typical for loss-of-coolant accident conditions, the 20th QUENCH Workshop, KIT, Allemagne, pp.11-2014, 2014.

A. Pshenichnikov, J. Stuckert, and M. Walter, Microstructure and mechanical properties of Zircaloy-4 cladding hydrogenated at temperatures typical for loss-of-coolant accident (LOCA) conditions, Nuclear Engineering and Design, vol.283, pp.33-39, 2015.
DOI : 10.1016/j.nucengdes.2014.06.022

A. Pshenichnikov, J. Stuckert, M. Walter, and D. Litvinov, Hydrides and fracture of pure zirconium and Zircaloy-4 hydrogenated at temperatures typical for loss-of-coolant accident conditions, Proceedings of the 23rd International Conference on Nuclear Engineering (ICONE-23), 2015.

M. P. Puls, The effect of hydrogen and hydrides on the integrity of zirconium alloy components, pp.978-979, 2012.
DOI : 10.1007/978-1-4471-4195-2

C. Raepsaet, . Bossis-ph, D. Hamon, J. L. Béchade, and J. C. Brachet, Quantification and local distribution of hydrogen within Zircaloy-4 PWR nuclear fuel cladding tubes at the nuclear microprobe of the Pierre S??e Laboratory from ??-ERDA, Proceedings of the 9th European Conference on Accelerators in Applied Research and Technology, pp.10-2424, 2008.
DOI : 10.1016/j.nimb.2008.03.041

J. T. Roberts, R. L. Jones, D. Cubicciotti, A. K. Miller, H. F. Wahcob et al., A stress corrosion cracking model for pellet-cladding interaction failures in lightwater reactor fuel rods, Zirconium in the Nuclear Industry, ASTM STP 681, p.285, 1979.

J. H. Root and R. W. Fong, Neutron diffraction study of the precipitation and dissolution of hydrides in Zr-2.5Nb pressure tube material, Journal of Nuclear Materials, vol.232, issue.1, pp.1-75, 1996.
DOI : 10.1016/0022-3115(96)00379-0

J. H. Root, W. M. Small, D. Khatamian, and O. T. Woo, Kinetics of the ?? to ?? zirconium hydride transformation in Zr-2.5Nb, Acta Materialia, vol.51, issue.7, pp.7-2041, 2003.
DOI : 10.1016/S1359-6454(03)00004-1

K. Sakamoto, H. Shiabata, K. Une, A. Ouchi, M. Aomi et al., Hydrogen absorption/desorption behavior through oxide layer of fuel claddings under accidental conditions, Water Reactor Fuel Performance Meeting/ Top Fuel / LWR Fuel Performance Meeting, 2014.

A. Sawatzky, A Proposed Criterion for the Oxygen Embrittlement of Zircaloy-4 Fuel Cladding, Zirconium in the Nuclear Industry (4th Conference), ASTM STP 681, pp.479-496, 1979.
DOI : 10.1520/STP36697S

S. S. Sidhu, N. S. Satya-murthy, F. P. Campos, and D. D. Zauberis, Neutron and X-Ray Diffraction Studies of Nonstoichiometric Metal Hydrides, Advances in Chemistry Series, vol.39, pp.87-98, 1963.
DOI : 10.1021/ba-1964-0039.ch008

J. Spurrier and J. C. Scully, Fractographic Aspects of the Stress Corrosion Cracking of Titanium in a Methanol/HCl Mixture, CORROSION, vol.28, issue.12, pp.453-643, 1972.
DOI : 10.5006/0010-9312-28.12.453

M. Steinbrück, Hydrogen absorption by zirconium alloys at high temperatures, Journal of Nuclear Materials, vol.334, issue.1, pp.58-64, 2004.
DOI : 10.1016/j.jnucmat.2004.05.007

M. Steinbrück, N. Ver, and M. Große, Oxidation of Advanced Zirconium Cladding Alloys in Steam at Temperatures in the Range of 600???1200????C, Oxidation of Metals, vol.241, issue.3-4, pp.3-4, 2011.
DOI : 10.1016/j.nucengdes.2010.04.010

A. Stern, Comportement métallurgique et mécanique des matériaux de gainage du combustible REP oxydés à haute température, Thèse de Doctorat, 2007.

A. Stern, J. Brachet, V. Maillot, D. Hamon, F. Barcelo et al., Investigations of the microstructure and mechanical properties of prior-beta structure as a function of the oxygen content in two zirconium alloys, Journal of ASTM International, vol.5, p.4, 2008.

J. Stuckert, Mechanical properties of pre-Hydrogenated (600 ? 5000 wppm) cladding Segments, pp.16-18, 2010.

C. Toffolon, Étude métallurgique et calculs de diagrammes de phases des alliages base zirconium du système : Zr-Nb-Fe-(O,Sn) Thèse de doctorat, 2000.

M. T. Tran, Caractérisation des microstructures trempées et sélection des variants dans le Zircaloy-4, Thèse de Doctorat, 2015.

G. Trégo, Comportement en fluage à haute température dans le domaine biphasé (? + ?) de L'alliage M5 ®, Thèse de Doctorat École Nationale Supérieure des Mines de, 2011.

M. Tupin, C. Bisor, P. Bossis, J. Chêne, J. L. Bechade et al., Mechanism of corrosion of zirconium hydride and impact of precipitated hydrides on the Zircaloy-4 corrosion behaviour, Corrosion Science, vol.98, pp.478-93, 2015.
DOI : 10.1016/j.corsci.2015.05.058

I. Turque, Metallurgical evolution of a highly hydrided zirconium alloy upon cooling from high temperature, TMS 2015, 144th Annual Meeting & Exhibition, pp.15-19, 2015.

I. Turque, R. Chosson, L. Saux, M. Brachet, J. Vandenberghe et al., Mechanical behavior at high temperature of highly oxygen-or hydrogen-enriched ? and (prior-) ? phases of zirconium alloys, 18th International Symposium on Zirconium in the Nuclear Industry, ASTM STP 1597, pp.15-19, 2016.

Y. Udagawa, F. Nagase, and T. Fuketa, Effect of Cooling History on Cladding Ductility under LOCA Conditions, Journal of Nuclear Science and Technology, vol.41, issue.8, pp.8-844, 2006.
DOI : 10.3327/jnst.41.723

H. Uetsuka, T. Fuketa, and S. Kawasaki, Zircaloy-4 Cladding Embrittlement due to Inner Surface Oxidation under Simulated Loss-of-Coolant Condition, Journal of Nuclear Science and Technology, vol.8649, issue.3, pp.9-705, 1981.
DOI : 10.1016/0022-3115(75)90072-0

V. Vandenberghe, J. Brachet, L. Saux, M. Gilbon, D. Billone et al., Influence of the cooling scenario on the post-quench mechanical properties of pre-hydrided Zircaloy-4 fuel claddings after high temperature steam oxidation (LOCA conditions), Proceedings of 2010 LWR Fuel Performance/TopFuel/WRFPM, pp.26-29, 2010.

M. S. Veshchunov and V. E. Shestak, Models for hydrogen uptake and release kinetics by zirconium alloys at high temperatures, Nuclear Engineering and Design, vol.252, pp.96-107, 2012.
DOI : 10.1016/j.nucengdes.2012.07.011

S. C. Vogel, A Review of Neutron Scattering Applications to Nuclear Materials, ISRN Materials Science, vol.55, issue.1???3, 2013.
DOI : 10.1016/j.physb.2006.05.275

D. Wongsawaeng and S. Jaiyen, High-temperature absolute hydrogen desorption kinetics of zirconium hydride under clean and oxidized surface conditions, Journal of Nuclear Materials, vol.403, issue.1-3, pp.1-24, 2010.
DOI : 10.1016/j.jnucmat.2010.05.025

S. Yamanaka, K. Higuchi, and M. Miyake, Hydrogen solubility in zirconium alloys, Journal of Alloys and Compounds, vol.231, issue.1-2, pp.503-507, 1995.
DOI : 10.1016/0925-8388(95)01864-6

S. Yamanaka, D. Setoyama, H. Muta, M. Uno, M. Kuroda et al., Characteristics of zirconium hydrogen solid solution, Journal of Alloys and Compounds, vol.372, issue.1-2, pp.1-2, 2004.
DOI : 10.1016/j.jallcom.2003.09.140

S. Kobayashi, Analysis of the electronic structure of zirconium hydride, Proceedings of the International Symposium on Metal-Hydrogen Systems, Fundamentals and Applications (MH2000), pp.330-332, 2002.

O. T. Woo and K. Tangri, Transformation characteristics of rapidly heated and quenched zircaloy-4-oxygen alloys, Journal of Nuclear Materials, vol.79, issue.1, pp.1-83, 1979.
DOI : 10.1016/0022-3115(79)90435-5

Z. Zhao, Identification d'une nouvelle phase d'hydrure de zirconium et modélisation à l'échelle mésoscopique de sa précipitation, Thèse de Doctorat, 2008.

Z. Zhao, J. Morniroli, A. Legris, A. Ambard, Y. Khin et al., Identification and characterization of a new zirconium hydride, Journal of Microscopy, vol.11, issue.3, pp.3-410421, 2008.
DOI : 10.1007/BF02674025

E. Zuzek, J. P. Abriata, A. San-martin, and F. D. Manchester, The H-Zr (Hydrogen- Zirconium) system. Bulletin of Alloy Phase Diagrams, 1990.