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발행년	- (예 : 2010-2015)

Post-Irradiation Tensile Behavior and Residual Activity of Several Ferritic/Martensitic and Austenitic Steels Irradiated in Osiris Reactor at 325°C up to 9 dpa

Academic Journal

de Carlan, Y; Averty, X; Brachet, J-C; Bertin, J; Rozenblum, F; Rabouille, O; Bougault, A

Effects of Radiation on Materials: 22nd Symposium, Jan 2006, Vol. 2006, No. 1475, pp. 67-85.

Full Text (ASTM) Find it@PNU

Post-Irradiation Tensile Behavior and Residual Activity of Several Ferritic/Martensitic and Austenitic Steels Irradiated in Osiris Reactor at 325°C up to 9 dpa

Academic Journal

de Carlan, Y; Averty, X; Brachet, J-C; Bertin, J-L; Rozenblum, F; Rabouille, O; Bougault, A

Journal of ASTM International, Sep 2005, Vol. 2, No. 8, pp. 1-19.

Full Text (ASTM) Scopus Find it@PNU

Study of Nb and Fe Precipitation in α-Phase Temperature Range (400 to 550°C) in Zr-Nb-(Fe-Sn) Alloys

Academic Journal

Toffolon-Masclet, C; Barberis, P; Brachet, J-C; Mardon, J-P; Legras, L

Journal of ASTM International, May 2005, Vol. 2, No. 5, pp. 1-18.

Full Text (ASTM) Scopus Find it@PNU

Influence of Long Service Exposures on the Thermal-Mechanical Behavior of Zy-4 and M5™ Alloys in LOCA Conditions

Academic Journal

Portier, L; Bredel, T; Brachet, J-C; Maillot, V; Mardon, J-P; Lesbros, A

Journal of ASTM International, Feb 2005, Vol. 2, No. 2, pp. 1-24.

Full Text (ASTM) Scopus Find it@PNU

Influence of Long Service Exposures on the Thermal-Mechanical Behavior of Zy-4 and M5™ Alloys in LOCA Conditions

Academic Journal

Portier, L; Bredel, T; Brachet, J-C; Maillot, V; Mardon, J-P; Lesbros, A

Zirconium in the Nuclear Industry: Fourteenth International Symposium, Jan 2005, Vol. 2005, No. 1467, pp. 896-920.

Full Text (ASTM) Find it@PNU

Study of Nb and Fe Precipitation in α-Phase Temperature Range (400 to 550°C) in Zr-Nb-(Fe-Sn) Alloys

Academic Journal

Toffolon-Masclet, C; Barberis, P; Brachet, J-C; Mardon, J-P; Legras, L

Zirconium in the Nuclear Industry: Fourteenth International Symposium, Jan 2005, Vol. 2005, No. 1467, pp. 81-101.

Full Text (ASTM) Find it@PNU

Influence of Hydrogen Content on the α/β Phase Transformation Temperatures and on the Thermal-Mechanical Behavior of Zy-4, M4 (ZrSnFeV), and M5™ (ZrNbO) Alloys During the First Phase of LOCA Transient

Academic Journal

Brachet, J-C; Portier, L; Forgeron, T; Hivroz, J; Hamon, D; Guilbert, T; Bredel, T; Yvon, P; Mardon, J-P; Jacques, P

Zirconium in the Nuclear Industry: Thirteenth International Symposium, Jan 2002, Vol. 2002, No. 1423, pp. 673-701.

Full Text (ASTM) Find it@PNU

Experimental Study and Preliminary Thermodynamic Calculations of the Pseudo-Ternary Zr-Nb-Fe-(O,Sn) System

Academic Journal

Toffolon, C; Brachet, J-C; Servant, C; Legras, L; Charquet, D; Barberis, P; Mardon, JP

Zirconium in the Nuclear Industry: Thirteenth International Symposium, Jan 2002, Vol. 2002, No. 1423, pp. 361-383.

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Behavior of Different Austenitic Stainless Steels, Conventional, Reduced Activation (RA) and ODS Chromium-Rich Ferritic-Martensitic Steels Under Neutron Irradiation at 325°C in PWR Environment

Academic Journal

Brachet, J-C; Averty, X; Lamagnère, P; Alamo, A; Rozenblum, F; Raquet, O; Bertin, J-L

Effects of Radiation on Materials: 20th International Symposium, Jan 2001, Vol. 2001, No. 1405, pp. 500-520.

Full Text (ASTM) Find it@PNU

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