Seguir
Patrick Raynaud
Patrick Raynaud
Nuclear Regulatory Commission
Dirección de correo verificada de nrc.gov
Título
Citado por
Citado por
Año
Crack growth in the through-thickness direction of hydrided thin-wall Zircaloy sheet
PA Raynaud, DA Koss, AT Motta
Journal of nuclear materials 420 (1-3), 69-82, 2012
722012
NUREG-2121: Fuel fragmentation, relocation, and dispersal during the loss-of-coolant accident
PAC Raynaud
US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 2012
64*2012
FRAPCON-4.0: A Computer Code for the Calculation of Steady-state
KJ Geelhood, WG Luscher, P Raynaud, I Porter
Thermal-Mechanical Behavior of Oxide Fuel Rods for High Burnup 1, 2015
612015
Fracture toughness of hydrided Zircaloy-4 sheet under through-thickness crack growth conditions
PA Raynaud, DA Koss, AT Motta, KS Chan
ASTM International, 2008
302008
Cladding stress during extended storage of high burnup spent nuclear fuel
PAC Raynaud, RE Einziger
Journal of Nuclear Materials 464, 304-312, 2015
262015
Report on fuel fragmentation, relocation and dispersal
H Sonnenburg, W Wiesenack, J Karlsson, J Noirot, V Garat, N Waeckel, ...
Nuclear Energy Agency Committee on Safety of Nuclear Installations, 2016
242016
Material Property Correlations: Comparisons between FRAPCON-3.4
WG Luscher, KJ Geelhood, I Porter
FRAPTRAN-1.5, and MATPRO, 2014
182014
Predictions of fuel dispersal during a LOCA
P Raynaud, I Porter
Proceedings of WRFPM 2014, 2014
172014
FRAPCON-4.0: A Computer Code for the Calculation of Steady-State, Thermal-Mechanical Behavior of Oxide Fuel Rods for High Burnup
KJ Geelhood, WG Luscher, PA Raynaud, IE Porter
Pacific Northwest National Laboratory Richland, Washington, 2015
132015
Fuel Fragmentation
P Raynaud
Relocation, and Dispersal during Lossof-Coolant Accidents, US NRC, NUREG-2121, 2012
102012
Cladding hydrogen based regulations in the United States
P Raynaud, A Bielen
2011 Water Reactor Fuel Performance Meeting, Chengdu, China, 2011
102011
Crack growth through the thickness of thin-sheet hydrided Zircaloy-4
PAC Raynaud
The Pennsylvania State University, 2009
102009
Material Property Correlations: Comparison Between FRACAON-3.5, FRAPCON-1.5, and MATPRO
KJ Geelhood, WG Lusher, PA Raynaud
NUREG/CR-7024, Rev. 1, 2014
82014
Core-wide estimates of fuel dispersal during a LOCA
P Raynaud
TopFuel 2013, 636-643, 2013
72013
Important Aspects of Probabilistic Fracture Mechanics Analyses
P Raynaud, M Kirk, M Benson, M Homiack
Technical Letter, United States Nuclear Regulatory Commission, Rockville, MD …, 2018
62018
Potential impacts of modeling full reactor cores using combined fuel performance and thermal hydraulics codes
I Porter, TW Knight, P Raynaud
Nuclear Technology 190 (2), 174-182, 2015
62015
Fuel Fragmentation, Relocation, and Dispersal During the Loss-of-Coolant Accident (NUREG-2121)
P Raynaud
United States Nuclear Regulatory Commission, 2012
62012
Fuel fragmentation, relocation and dispersal during the loss-of-coolant accident, 2012
PAC Raynaud
Report NUREG-2121, US Nuclear Regulatory Commission, Washington, DC, USA, 0
6
FRAPCON-4.0: A Computer Code for the Calculation of Steady-State, Thermal-Mechanical Behavior of Oxide Fuel Rods for High Burnup. Nuclear Regulatory Commission, Washington, DC …
K Geelhood, W Luscher, P Raynaud
Pacific Northwest Lab., Richland, WA (United States), 2015
52015
FRAPCON-4.0: A Computer Code of Steady-State, Thermal-Mechanical Behavior of Oxide Fuel Rods for High Burnup
KJ Geelhood, WG Luscher, P Raynaud, P IE
PNNL-19418 1, 2015
52015
El sistema no puede realizar la operación en estos momentos. Inténtalo de nuevo más tarde.
Artículos 1–20