1-12 of 12
Keywords: reactor/nuclear
Close
Save search
Follow your search
Access your saved searches in your account
Would you like to receive an alert when new items match your search?
Close Modal
Sort by
Proceedings Papers

Guidance on the Suitability of Design Codes and Assessment Procedures for Deploying High Temperature Advanced Modular Reactors in the UK

Marc Chevalier, Peter James, Nick Underwood
Proc. ASME. PVP2022, Volume 1: Codes and Standards, V001T01A076, July 17–22, 2022
Paper No: PVP2022-84897
https://doi.org/10.1115/PVP2022-84897
... to be used congruently to provide a solution on a timescale consistent with the UKs ambition for AMR deployment. elevated temperature analysis and design structural integrity safety and reliability reactor/nuclear creep probability/probabilistic Proceedings of the ASME 2022 Pressure Vessels...
View Paper titled, Guidance on the Suitability of Design Codes and Assessment Procedures for Deploying High Temperature Advanced Modular Reactors in the UK
Open the PDF for Guidance on the Suitability of Design Codes and Assessment Procedures for Deploying High Temperature Advanced Modular Reactors in the UK in another window
Topics: Design, High temperature
Proceedings Papers

Fatigue Benchmark Comparison Effort Between Code_Aster and CNNC/NPIC Software – Part 3

Yin Liu, Hai Xie, Zichen Kong, Xuejiao Shao, Stephan Courtin, Sam Cuvilliez, Furui Xiong
Proc. ASME. PVP2022, Volume 1: Codes and Standards, V001T01A009, July 17–22, 2022
Paper No: PVP2022-78364
https://doi.org/10.1115/PVP2022-78364
... stepping. fatigue finite and boundary element methods piping components reactor/nuclear thermomechanical Proceedings of the ASME 2022 Pressure Vessels & Piping Conference PVP2022 July 17-22, 2022, Las Vegas, Nevada, USA PVP2022-78364 FATIGUE BENCHMARK COMPARISON EFFORT BETWEEN CODE_ASTER...
View Paper titled, Fatigue Benchmark Comparison Effort Between Code_Aster and CNNC/NPIC Software – Part 3
Open the PDF for Fatigue Benchmark Comparison Effort Between Code_Aster and CNNC/NPIC Software – Part 3 in another window
Topics: Computer software, Fatigue
Proceedings Papers

Use of HDPE Piping in Buried Nuclear Class 3 Systems Categorized as Low Safety Significant

J. E. (Jim) O’Sullivan
Proc. ASME. PVP2022, Volume 1: Codes and Standards, V001T01A078, July 17–22, 2022
Paper No: PVP2022-84425
https://doi.org/10.1115/PVP2022-84425
... provisions for material procurement, design, fabrication, installation, and testing of technically superior HDPE piping as a cost-competitive permanent replacement for degraded buried safety related Class 3 carbon steel piping. reactor/nuclear nonmetals polymers safety/risk/reliability repair...
View Paper titled, Use of HDPE Piping in Buried Nuclear Class 3 Systems Categorized as Low Safety Significant
Open the PDF for Use of HDPE Piping in Buried Nuclear Class 3 Systems Categorized as Low Safety Significant in another window
Topics: Pipes, Risk, Safety
Proceedings Papers

Probabilistic Fracture Mechanics Codes for Piping International Benchmark – Part 1: Deterministic Comparisons

Matthew Homiack
Proc. ASME. PVP2022, Volume 2: Computer Technology and Bolted Joints; Design and Analysis, V002T03A054, July 17–22, 2022
Paper No: PVP2022-84724
https://doi.org/10.1115/PVP2022-84724
... of the PFM codes, which will be presented in a subsequent paper. corrosion fracture numerical and computational piping components probability/probabilistic reactor/nuclear Proceedings of the ASME 2022 Pressure Vessels & Piping Conference PVP2022 July 17-22, 2022, Las Vegas, Nevada, USA PVP2022...
View Paper titled, Probabilistic Fracture Mechanics Codes for Piping International Benchmark – Part 1: Deterministic Comparisons
Open the PDF for Probabilistic Fracture Mechanics Codes for Piping International Benchmark – Part 1: Deterministic Comparisons in another window
Topics: Fracture (Materials), Fracture (Process), Fracture mechanics, Pipes, Leakage, Leak-before-break, Stress, Water, Alloys, Corrosion
Proceedings Papers

BRUTE: Evaluation of Mechanical Properties of True Reactor Pressure Vessel Material From Barsebäck 2

Pentti Arffman, Jari Lydman, Noora Hytönen, Zaiqing Que, Sebastian Lindqvist
Proc. ASME. PVP2022, Volume 4A: Materials and Fabrication, V04AT06A034, July 17–22, 2022
Paper No: PVP2022-83819
https://doi.org/10.1115/PVP2022-83819
...-based transition temperature, possibly due to the inhomogeneity of the materials. The results show that the safety of the materials can be assessed reliably, provided that contemporary methods, equipment and analyses are used. ageing fracture reactor/nuclear pressure vessel weld structural...
View Paper titled, BRUTE: Evaluation of Mechanical Properties of True Reactor Pressure Vessel Material From Barsebäck 2
Open the PDF for BRUTE: Evaluation of Mechanical Properties of True Reactor Pressure Vessel Material From Barsebäck 2 in another window
Topics: Fracture (Materials), Fracture (Process), Mechanical properties, Reactor vessels
Proceedings Papers

Large-Scale Parametric Modeling of Spent Nuclear Fuel Dynamics in the 30 cm Package Drop Scenario

Kevin Kadooka, James Fitzpatrick, Nicholas Klymyshyn
Proc. ASME. PVP2022, Volume 5: Operations, Applications, and Components; Seismic Engineering; ASME Nondestructive Evaluation, Diagnosis and Prognosis (NDPD) Division, V005T07A030, July 17–22, 2022
Paper No: PVP2022-84747
https://doi.org/10.1115/PVP2022-84747
... and modeling strategy the Spent Fuel and Waste Science and Technology program is using to close the external loads knowledge gap. dynamic analysis finite and boundary element methods numerical and computational reactor/nuclear structural integrity Proceedings of the ASME 2022 Pressure Vessels...
View Paper titled, Large-Scale Parametric Modeling of Spent Nuclear Fuel Dynamics in the 30 cm Package Drop Scenario
Open the PDF for Large-Scale Parametric Modeling of Spent Nuclear Fuel Dynamics in the 30 cm Package Drop Scenario in another window
Topics: Dynamics (Mechanics), Modeling, Spent nuclear fuels, Fuels, Manufacturing, Simulation, Stress, Boiling water reactors, Cladding systems (Building), Fuel rods
Proceedings Papers

An Estimate of Spent Nuclear Fuel Mechanical Loads in the General 30 cm Package Drop Scenario

Nicholas Klymyshyn, Kevin Kadooka, Casey Spitz, James Fitzpatrick
Proc. ASME. PVP2022, Volume 5: Operations, Applications, and Components; Seismic Engineering; ASME Nondestructive Evaluation, Diagnosis and Prognosis (NDPD) Division, V005T07A028, July 17–22, 2022
Paper No: PVP2022-84353
https://doi.org/10.1115/PVP2022-84353
... program can consider the knowledge gap closed. dynamic analysis finite and boundary element methods numerical and computational reactor/nuclear structural integrity Proceedings of the ASME 2022 Pressure Vessels & Piping Conference PVP2022 July 17-22, 2022, Las Vegas, Nevada, USA PVP2022-84353...
View Paper titled, An Estimate of Spent Nuclear Fuel Mechanical Loads in the General 30 cm Package Drop Scenario
Open the PDF for An Estimate of Spent Nuclear Fuel Mechanical Loads in the General 30 cm Package Drop Scenario in another window
Topics: Spent nuclear fuels, Stress, Fuels, Manufacturing, Damage, Modeling, Boiling water reactors, Boundary element methods, Collaboration, Design
Proceedings Papers

Transient Thermal Modeling of the High Burnup Demonstration Research Project Cask Using STAR-CCM+ and COBRA-SFS

D. J. Richmond, J. A. Fort, S. R. Suffield
Proc. ASME. PVP2021, Volume 5: Operations, Applications, and Components; Seismic Engineering; Non-Destructive Examination, V005T07A031, July 13–15, 2021
Paper No: PVP2021-62082
https://doi.org/10.1115/PVP2021-62082
... and design elevated temperature reactor/nuclear verification/validation/qualification Proceedings of the ASME 2021 Pressure Vessels & Piping Conference PVP2021 July 13-15, 2021, Virtual, Online PVP2021-62082 TRANSIENT THERMAL MODELING OF THE HIGH BURNUP DEMONSTRATION RESEARCH PROJECT CASK USING STAR...
View Paper titled, Transient Thermal Modeling of the High Burnup Demonstration Research Project Cask Using STAR-CCM+ and COBRA-SFS
Open the PDF for Transient Thermal Modeling of the High Burnup Demonstration Research Project Cask Using STAR-CCM+ and COBRA-SFS in another window
Topics: Computational fluid dynamics, Design, Modeling, Temperature, Transients (Dynamics), Drying, Steady state, Fuels, Spent nuclear fuels, Storage
Proceedings Papers

Spent Nuclear Fuel Mechanical Loads in the General Package Drop Scenario

Nicholas Klymyshyn, Casey Spitz, Pavlo Ivanusa, Kevin Kadooka, James Fitzpatrick
Proc. ASME. PVP2021, Volume 5: Operations, Applications, and Components; Seismic Engineering; Non-Destructive Examination, V005T07A026, July 13–15, 2021
Paper No: PVP2021-61617
https://doi.org/10.1115/PVP2021-61617
... progress toward developing the general solution to the problem of spent nuclear fuel mechanical loads in the 30 cm package drop scenario, and it describes the next steps in closing the knowledge gap. dynamic analysis finite and boundary element methods numerical and computational reactor/nuclear...
View Paper titled, Spent Nuclear Fuel Mechanical Loads in the General Package Drop Scenario
Open the PDF for Spent Nuclear Fuel Mechanical Loads in the General Package Drop Scenario in another window
Topics: Spent nuclear fuels, Stress, Damage, Manufacturing, Boundary element methods, Design, Dynamic analysis, Finite element analysis, Finite element model, Fuels
Proceedings Papers

Structural Dynamics Modeling of Spent Nuclear Fuel During Hypothetical Package Drop Events

Kevin Kadooka, James Fitzpatrick, Nicholas Klymyshyn
Proc. ASME. PVP2021, Volume 5: Operations, Applications, and Components; Seismic Engineering; Non-Destructive Examination, V005T07A025, July 13–15, 2021
Paper No: PVP2021-61610
https://doi.org/10.1115/PVP2021-61610
... to the point of consistency with the package design requirements. dynamic analysis finite and boundary element methods numerical and computational reactor/nuclear structural integrity Proceedings of the ASME 2021 Pressure Vessels & Piping Conference PVP2021 July 13-15, 2021, Virtual, Online...
View Paper titled, Structural Dynamics Modeling of Spent Nuclear Fuel During Hypothetical Package Drop Events
Open the PDF for Structural Dynamics Modeling of Spent Nuclear Fuel During Hypothetical Package Drop Events in another window
Topics: Modeling, Spent nuclear fuels, Structural dynamics, Fuels, Shock (Mechanics), Transportation systems, Boundary element methods, Buckling, Cladding systems (Building), Design
Proceedings Papers

Negative R Fatigue Short Crack Growth Rate Testing on Austenitic Stainless Steels

Adam Griffiths, Peter Gill, Ben Coult, Jack Beswick, Norman Platts, Jonathan Mann, Chris Currie, Joe Airey
Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A013, July 13–15, 2021
Paper No: PVP2021-62909
https://doi.org/10.1115/PVP2021-62909
... reference curves and results from material specific in-house testing to assist the understanding of the behaviour of mechanically short cracks. fatigue testing corrosion metals reactor/nuclear structural integrity Proceedings of the ASME 2021 Pressure Vessels & Piping Conference PVP2021 July...
View Paper titled, Negative R Fatigue Short Crack Growth Rate Testing on Austenitic Stainless Steels
Open the PDF for Negative R Fatigue Short Crack Growth Rate Testing on Austenitic Stainless Steels in another window
Topics: Fatigue, Fracture (Materials), Stainless steel, Testing, Grain size, Heat, Nucleation (Physics), Stress, Analytical methods, ASME Standards
Proceedings Papers

Results From Environmentally-Assisted Short Crack Fatigue Testing on Austenitic Stainless Steels

Ben Coult, Adam Griffiths, Jack Beswick, Peter Gill, Norman Platts, Jean Smith, Gary Stevens
Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A016, August 3, 2020
Paper No: PVP2020-21406
https://doi.org/10.1115/PVP2020-21406
... mm. Crack growth rates have been compared to those predicted in ASME, Code Case N-809 and results from material specific in-house testing to assist the understanding of the behaviour of mechanically short cracks. fatigue testing corrosion metals reactor/nuclear structural integrity...
View Paper titled, Results From Environmentally-Assisted Short Crack Fatigue Testing on Austenitic Stainless Steels
Open the PDF for Results From Environmentally-Assisted Short Crack Fatigue Testing on Austenitic Stainless Steels in another window
Topics: Fatigue testing, Fracture (Materials), Stainless steel, Testing, Fatigue, Nucleation (Physics), Stress, Analytical methods, ASME Standards, Bridges (Structures)