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J-C Brachet
Observed names:
Brachet, J.-C.,
Brachet, Jc.,
J. -C. Brachet,
J. C. Brachet,
J.C. Brachet,
JC Brachet
show all 6
Institutions:
Commissariat à l'Énergie Atomique et aux Énergies Alternatives,
Direction des Energies
Observed institutions:
Commissariat à l'Énergie Atomique et aux Énergies Alternatives,
CEA Paris-Saclay - Etablissement de Saclay,
Direction des Energies,
CEA Paris-Saclay
OpenAlex ID:
A5111624237
Experiment and Modeling of Advanced Fuel Rod Cladding Behavior Under LOCA Conditions: Alpha-Beta Phase Transformation Kinetics and EDGAR Methodology
2000
·
T Forgeron
, JC Brachet
, et al.
·
75
Influence of Long Service Exposures on the Thermal-Mechanical Behavior of Zy-4 and M5™ Alloys in LOCA Conditions
2005
·
L Portier
, T Bredel
, et al.
·
Journal of ASTM International
·
71
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
2002
·
J-C Brachet
, L Portier
, et al.
·
67
Experimental Study and Preliminary Thermodynamic Calculations of the Pseudo-Ternary Zr-Nb-Fe-(O,Sn) System
2002
·
C Toffolon
, J-C Brachet
, et al.
·
49
Study of Nb and Fe Precipitation in α-Phase Temperature Range (400 to 550°C) in Zr-Nb-(Fe-Sn) Alloys
2005
·
C Toffolon-Masclet
, P Barberis
, et al.
·
29
Behavior of chromium coated M5TM claddings under loca conditions
2017
·
Brachet, Jc.
, Dumerval, M.
, et al.
·
HAL
·
20
Study of Nb and Fe Precipitation in α-Phase Temperature Range (400 to 550°C) in Zr-Nb-(Fe-Sn) Alloys
2005
·
C Toffolon-Masclet
, P Barberis
, et al.
·
Journal of ASTM International
·
14
Hydrogen Content, Preoxidation, and Cooling Scenario Effects on Post-Quench Microstructure and Mechanical Properties of Zircaloy-4 and M5® Alloys in LOCA Conditions
2009
·
J. -C. Brachet
, V. Vandenberghe-Maillot
, et al.
·
13
Contribution of Thermodynamic Calculations to Metallurgical Studies of Multi-Component Zirconium Based Alloys
2009
·
C. Toffolon-Masclet
, J. C. Brachet
, et al.
·
12
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
2001
·
J-C Brachet
, X Averty
, et al.
·
12
Influence of Long Service Exposures on the Thermal-Mechanical Behavior of Zy-4 and M5™ Alloys in LOCA Conditions
2005
·
L Portier
, T Bredel
, et al.
·
11
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
2005
·
Y de Carlan
, X Averty
, et al.
·
Journal of ASTM International
·
10
Irradiation Effects on Base Metal and Welds of 9Cr-1Mo (EM10) Martensitic Steel
1996
·
A Alamo
, JL Séran
, et al.
·
4
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
2006
·
Y de Carlan
, X Averty
, et al.
·
1
Evolution des contraintes internes generees au sein d'un alliage de Zr oxyde a haute temperature puis refroidi
2017
·
Guillou, R.
, Le Saux, Matthieu
, et al.
·
HAL
Proceedings of the Start-up Meeting of the OECD-NEA Expert Group on Accident Tolerant Fuels for LWRs, 28-29 April 2014, OECD-NEA HQ
2014
·
Masaki Kurata
, Shannon Bragg-Sitton
, et al.
Creep behavior at high temperature of the oxygen stabilized zirconium alpha phase of fuel cladding tubes oxidized in loca conditions
2013
·
Chosson, Raphaël
, Vandenberghe, V.
, et al.
·
HAL
“Accident tolerant fuel” (Ex. : Gainage innovant plus robuste en conditions accidentelles) & Processus de qualification
2013
·
J.C. Brachet
, N. Waeckel
, et al.
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Works count:
18
Citation count:
388
H-index:
11
I10-index:
12
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