... 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...

... 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...

... reactor/nuclear nonmetals polymers safety/risk/reliability repair probability/probabilistic Abstract Code Case N-755 and ASME Section III Appendix XXVI were developed by ASME for providing deterministic rules for new construction of Class 3 buried piping using High Density...

... 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...

...-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...

... dynamic analysis finite and boundary element methods numerical and computational reactor/nuclear structural integrity Abstract Packages used to transport spent nuclear fuel (SNF) are required by the U.S. Code of Federal Regulations 10 CFR 71.71 to demonstrate satisfactory performance...

... 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...

... fatigue based on a mechanically short cracks. Total Life Prediction approach that would be adequately, but not excessively, conservative. Such an approach necessitates the Keywords: Fatigue, Testing, Corrosion, Metals, development of analytical methods for the various stages of Reactor/Nuclear, Structural...

... analysis 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...

... reactor/nuclear structural integrity Proceedings of the ASME 2021 Pressure Vessels & Piping Conference PVP2021 July 13-15, 2021, Virtual, Online PVP2021-61617 SPENT NUCLEAR FUEL MECHANICAL LOADS IN THE GENERAL PACKAGE DROP SCENARIO Nicholas Klymyshyn1, Casey Spitz, Pavlo Ivanusa, Kevin Kadooka, James...

... mechanical loads 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...

... 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. Keywords: Fatigue, Testing, Corrosion, Metals, Reactor/Nuclear, Structural Integrity NOMENCLATURE C(T) Compact Tensile DCPD Direct...