Zobrazeno 1 - 10
of 18
pro vyhledávání: '"Daniel Sommerville"'
Autor:
Arslan Siddique, Francesco Banterle, Massimiliano Corsini, Paolo Cignoni, Daniel Sommerville, Chris Joffe
Publikováno v:
Sensors, Vol 23, Iss 14, p 6456 (2023)
We present MoReLab, a tool for user-assisted 3D reconstruction. This reconstruction requires an understanding of the shapes of the desired objects. Our experiments demonstrate that existing Structure from Motion (SfM) software packages fail to estima
Externí odkaz:
https://doaj.org/article/5a4965ee1b194cb0b0063e1cea0c1078
Publikováno v:
Volume 4: Fluid-Structure Interaction.
As part of the license basis of a nuclear boiling water reactor pressure vessel, a sudden loss of coolant accident (LOCA) event needs to be analyzed. One of the loads that results from this event is a sudden depressurization of the recirculation line
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::cdecaa2219bd3138e6cc7c814ca71efe
https://doi.org/10.1115/pvp2020-21633
https://doi.org/10.1115/pvp2020-21633
Autor:
Daniel Sommerville, Matthew Walter
Publikováno v:
Volume 3: Design and Analysis.
Cracking in boiling water reactor (BWR) core shroud welds has been identified in operating nuclear plants worldwide. The Boiling Water Reactor Vessel and Internals Project (BWRVIP) has published several reports providing inspection and evaluation (I&
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::072565b51c54d57b85eeb5f76905ebf6
https://doi.org/10.1115/pvp2016-63616
https://doi.org/10.1115/pvp2016-63616
Publikováno v:
Volume 3: Design and Analysis.
Cracking in boiling water reactor (BWR) core shroud welds has been identified in operating nuclear plants worldwide. The nuclear industry has taken extensive efforts to disposition and evaluate core shroud cracking, most notably within the BWR Vessel
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c11c6e9794d4e12fb045e2a507e8ecfe
https://doi.org/10.1115/pvp2016-63689
https://doi.org/10.1115/pvp2016-63689
Publikováno v:
Volume 4: Fluid-Structure Interaction.
There have been numerous industry communications over the past six years identifying issues pertaining to incorrectly calculated or erroneously omitted recirculation line break acoustic loads. Acoustic loads caused by a postulated recirculation line
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1a0e964efe73ef53f56c674d39536ec8
https://doi.org/10.1115/pvp2015-45769
https://doi.org/10.1115/pvp2015-45769
Publikováno v:
Volume 6B: Materials and Fabrication.
Two simplified models are developed and benchmarked for predicting through-wall axial and hoop weld residual stress (WRS) distributions in single V groove dissimilar metal welds (DMWs) joining cylindrical components such as piping or nozzles. The mod
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::0ca15579b31dd14bdf5d0c90cab4c1d8
https://doi.org/10.1115/pvp2014-28828
https://doi.org/10.1115/pvp2014-28828
Autor:
Gary L. Stevens, Hardayal S. Mehta, Joshua Kusnick, Mark Kirk, Michael L. Benson, Timothy J. Griesbach, Daniel Sommerville
Publikováno v:
Volume 1: Codes and Standards.
A previous PVP paper [1] identified suggested improvements to be made to ASME Code, Section XI, Nonmandatory Appendix G, “Fracture Toughness Criteria for Protection Against Failure” [2]. That paper also identified that the current version of Appe
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::00e5dc1647ccafc25386cfe6b8271571
https://doi.org/10.1115/pvp2014-28397
https://doi.org/10.1115/pvp2014-28397
Publikováno v:
Volume 2: Computer Technology and Bolted Joints.
As part of license renewal activities, many Boiling Water Reactor utilities must assess the integrity of bolted components within the reactor pressure vessel. Since inspection techniques capable of identifying cracking in the threaded regions of the
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a9e9db400ec3b67b8c2a8dc78d2dfefe
https://doi.org/10.1115/pvp2013-97727
https://doi.org/10.1115/pvp2013-97727
Autor:
Daniel Sommerville
Publikováno v:
Volume 4: Fluid-Structure Interaction.
Recent industry communications have identified issues pertaining to incorrectly calculated recirculation line break acoustic loads or structural evaluations that need to include, but have previously excluded, the recirculation line break acoustic loa
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5ede32a0eebddea8948d5d520a71d36b
https://doi.org/10.1115/pvp2013-97728
https://doi.org/10.1115/pvp2013-97728
Autor:
Nathan Palm, Shengjun Yin, Matthew Walter, Daniel Sommerville, Gary L. Stevens, Carol Heinecke
Publikováno v:
Volume 3: Design and Analysis.
In past years, the authors have undertaken various studies of nozzles in both boiling water reactors (BWRs) and pressurized water reactors (PWRs) located in the reactor pressure vessel (RPV) adjacent to the core beltline region. Those studies describ
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::18e1875794f4167134fd76cb5c2cfdd7
https://doi.org/10.1115/pvp2012-78119
https://doi.org/10.1115/pvp2012-78119