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Keywords: fission reactor theory
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Journal Articles

CFD Tool for Assessment of the Reactor Pressure Vessel Integrity in Pressure Thermal Shock Conditions: Influence of Turbulence Model and Mesh Refinement on the Vessel Thermal Loading During PTS Transient

A. Martin, S. Benhamadouche, G. Bezdikian, F. Beaud, F. Lestang
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. June 2011, 133(3): 031302.
https://doi.org/10.1115/1.3027494
Published Online: April 7, 2011
.... 16 12 2005 28 02 2008 07 04 2011 07 04 2011 computational fluid dynamics cracks fission reactor coolants fission reactor cooling fission reactor fuel claddings fission reactor theory fracture mechanics heat transfer nuclear engineering computing pressure vessels...
View Article titled, CFD Tool for Assessment of the Reactor Pressure Vessel Integrity in Pressure Thermal Shock Conditions: Influence of Turbulence Model and Mesh Refinement on the Vessel Thermal Loading During PTS Transient
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Topics: Boundary-value problems, Computational fluid dynamics, Fluids, Geometry, Nozzles, Safety, Temperature, Thermal shock, Transients (Dynamics), Turbulence
Journal Articles

Quantitative Estimation of the Growth of Environmentally Assisted Cracks at Flaws in Light Water Reactor Components

H. Xue, Y. Sato, T. Shoji
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. February 2009, 131(1): 011404.
https://doi.org/10.1115/1.3027458
Published Online: November 26, 2008
.... , 2007 , “ Development of a Stress Corrosion Crack Test Methodology Using Tube-Shaped Specimen ,” J. Test. Eval. 0090-3973 10.1520/JTE100628 , 35 ( 3 ), pp. 254 – 258 . cracks elasticity finite element analysis fission reactor materials fission reactor theory nuclear power stations...
View Article titled, Quantitative Estimation of the Growth of Environmentally Assisted Cracks at Flaws in Light Water Reactor Components
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Topics: Fracture (Materials), Light water reactors, Stress
Journal Articles

Temperature Distribution and Thermal Stress Analysis of Ball-Tank Subjected to Solar Radiation

Vishnu Verma, A. K. Ghosh, H. S. Kushwaha
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. May 2005, 127(2): 119–122.
https://doi.org/10.1115/1.1858920
Published Online: May 27, 2005
...; revision received September 22, 2004. Review conducted by: K. K. Yoon. 02 September 2003 22 September 2004 27 05 2005 thermal stresses stress analysis solar radiation fission research reactors finite element analysis fission reactor theory fission reactor materials fission...
View Article titled, Temperature Distribution and Thermal Stress Analysis of Ball-Tank Subjected to Solar Radiation
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Topics: Solar radiation, Temperature, Temperature distribution, Thermal stresses
Journal Articles

Optimum Global Failure Prediction Model of Steam Generator Tube With Two Parallel Axial Through-Wall Cracks

Seong-In Moon, Young-Jin Kim, Jin-Ho Lee, Myung-Ho Song, Youn-Won Park
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. May 2005, 127(2): 123–128.
https://doi.org/10.1115/1.1858921
Published Online: May 27, 2005
.... Review conducted by: K. K. Yoon. 15 September 2003 22 September 2004 27 05 2005 finite element analysis failure (mechanical) cracks fission reactor materials fission reactor theory plastic deformation nuclear reactor maintenance Steam Generator Tube Plastic Collapse...
View Article titled, Optimum Global Failure Prediction Model of Steam Generator Tube With Two Parallel Axial Through-Wall Cracks
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Topics: Failure, Fracture (Materials), Stress, Collapse, Boilers, Plates (structures)
Journal Articles

Optimization of Loads in Piping Systems by the Realistic Calculation Method Applying Fluid-Structure-Interaction (FSI) and Dynamic Friction

Tilman Diesselhorst, Ulrich Neumann
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Article
J. Pressure Vessel Technol. February 2005, 127(1): 1–6.
https://doi.org/10.1115/1.1845449
Published Online: March 15, 2005
... Division December 4, 2003; revision received September 8, 2004. Review conducted: W. L. Cheng. 04 December 2003 08 September 2004 15 03 2005 nuclear power stations fission reactor cooling fission reactor theory fission reactor design pipes valves nuclear engineering...
View Article titled, Optimization of Loads in Piping Systems by the Realistic Calculation Method Applying Fluid-Structure-Interaction (FSI) and Dynamic Friction
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Topics: Fluid structure interaction, Fluids, Optimization, Pipes, Piping systems, Pressure, Stress, Surges, Valves, Sliding friction
Journal Articles

The Effect of Reduced Design Margin on the Fire Survivability of ASME Code Propane Tanks

A. M. Birk
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Article
J. Pressure Vessel Technol. February 2005, 127(1): 55–60.
https://doi.org/10.1115/1.1845476
Published Online: March 15, 2005
.... Associate Editor: M. D. Rana. 26 February 2004 30 August 2004 15 03 2005 pressure vessels nuclear engineering computing fission reactor design fission reactor materials fission reactor theory fires fission reactor safety fracture steel tanks (containers) Pressure...
View Article titled, The Effect of Reduced Design Margin on the Fire Survivability of ASME Code Propane Tanks
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Topics: ASME Standards, Design, Fire, Failure, Steel
Journal Articles

Information Fusion Technique for Evaluating Radiation Embrittlement of Reactor Pressure Vessel Steels

J. A. Wang, S. Konduri, N. S. V. Rao
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Article
J. Pressure Vessel Technol. February 2005, 127(1): 98–104.
https://doi.org/10.1115/1.1858926
Published Online: March 15, 2005
... Fusion , 1 , no. 1 , pp. 35 – 44 . 25 July 2004 08 September 2004 23 November 2004 15 03 2005 fission reactor materials pressure vessels steel embrittlement radiation effects fission reactor theory fission reactor safety copper nickel phosphorus...
View Article titled, Information Fusion Technique for Evaluating Radiation Embrittlement of Reactor Pressure Vessel Steels
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Topics: Boiling water reactors, Embrittlement, Uncertainty, Radiation (Physics), Steel