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Proc. ASME. PVP2022, Volume 1: Codes and Standards, V001T01A051, July 17–22, 2022
Paper No: PVP2022-81135
... integrity of previous nuclear reactor designs has been calculated using deterministic methods, but this approach can lead to overly-conservative (or in some cases, optimistic) assessments. Probabilistic structural integrity analysis methods offer the potential to increase understanding of uncertainty...
Proc. ASME. PVP2022, Volume 1: Codes and Standards, V001T01A055, July 17–22, 2022
Paper No: PVP2022-84742
... nuclear Proceedings of the ASME 2022 Pressure Vessels & Piping Conference PVP2022 July 17-22, 2022, Las Vegas, Nevada, USA PVP2022-84742 PROBABILISTIC CONTROL ROD FAILURE ANALYSIS FOR A NOMINAL MOLTEN SALT REACTOR Henry Cathcart Frazer-Nash Consultancy Ltd. Warrington, UK James Finley Frazer-Nash...
Proc. ASME. PVP2022, Volume 2: Computer Technology and Bolted Joints; Design and Analysis, V002T02A014, July 17–22, 2022
Paper No: PVP2022-81911
... Abstract AFCEN is the publisher of the French Nuclear code RCC-M ® (Design and Construction Rules for Mechanical Components of PWR Nuclear Islands) . It has launched an action for the revision of the Annex Z V and F 7000, respectively concerning the design and the installation of the bolted...
Proc. ASME. PVP2020, Volume 3: Design and Analysis, V003T03A020, August 3, 2020
Paper No: PVP2020-21759
..., compartmentalized by discipline, fragmented into various segments, communicated through numerous layers, and finally, printed onto an undersized paper by the stakeholders and end-users. Large nuclear projects, such as refurbishments and decommissioning, suffer from spatial, interface, and interreference challenges...
Proc. ASME. PVP2020, Volume 2: Computer Technology and Bolted Joints, V002T02A008, August 3, 2020
Paper No: PVP2020-21527
.... The representation of the material stress-strain curve is another important aspect that may require additional guidance. plastic collapse load finite element analysis (FEA) twice elastic slope method (TESM) nuclear ASSESSMENT OF SECTION III APPENDIX XIII-3230 PLASTIC ANALYSIS Wolf Reinhardt Candu Energy...
Proc. ASME. PVP2019, Volume 2: Computer Technology and Bolted Joints, V002T02A026, July 14–19, 2019
Paper No: PVP2019-93557
... and the uncertainty of extreme percentiles of finite Monte Carlo samples. Keywords: Probabilistic, Nuclear, Structural Integrity NOMENCLATURE Input variable to probabilistic assessment Output from probabilistic assessment 0 Baseline assessment result Mean Standard deviation Kurtosis 1 Contact author...
Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 1, 275-281, July 18–22, 2010
Paper No: PVP2010-25187
... 14 01 2011 The objectives of this paper is to discuss technical harmonization of Nuclear Codes and Standards, based on French long experience in Codes and Standards used for design-fabrication and operation of nuclear components (mainly pressure retaining components). After a long...