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Keywords: pressurized thermal shockClose
Maksym Zarazovskii, Vladislav Pištora, Dana Lauerova, Florian Obermeier, Diego Fernando Mora Mendez, Yaroslav Dubyk, Tobias Bolinder, Carlos Cueto-Felgueroso Garcia, Szabolcs Szávai, Judit Dudra, Oriol Costa Garrido, Christophe Blain, Markku Puustinen, Jinya Katsuyama, B. Richard Bass, Paul T. Williams, Oleksii Shugailo
Proc. ASME. PVP2022, Volume 1: Codes and Standards, V001T01A083, July 17–22, 2022
Paper No: PVP2022-83699
... Abstract The APAL (Advanced Pressurized Thermal Shock (PTS) Analysis for Long-Term Operation (LTO)) project was launched in October 2020 for four years with funding from the European Union’s HORIZON 2020 program. Within APAL, an extensive literature review was performed and experience...
Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A016, August 3, 2020
Paper No: PVP2020-21736
... with some of the modern ones. * Contact author: email@example.com Keywords: reactor pressure vessel, pressurized thermal shock, resistance against brittle fracture, one-dimensional heat transfer, ventilation system, transient analysis, structural analysis, warm pre-stressing, cladding integrity...
Proc. ASME. PVP2019, Volume 1: Codes and Standards, V001T01A059, July 14–19, 2019
Paper No: PVP2019-93967
... Abstract For reactor pressure vessels (RPVs) of pressurized water reactors, temperature of the coolant water in the emergency core cooling system (ECCS) may influence the structural integrity of the RPV during pressurized thermal shock (PTS) events. By focusing on a mitigation measure to raise...
Proc. ASME. PVP2019, Volume 3: Design and Analysis, V003T03A101, July 14–19, 2019
Paper No: PVP2019-94076
... several integrated numerical codes and methods were performed for a reference pressurized water reactor (PWR) RPV subjected to pressurized thermal shock (PTS) loads. System analyses were performed with the numerical codes RELAP5 and TRACE, whereas for structural and fracture mechanics calculations...
Proc. ASME. PVP2013, Volume 7: Operations, Applications and Components, V007T07A031, July 14–18, 2013
Paper No: PVP2013-97569
... Both probabilistic and deterministic methods are used in structural integrity assessment of reactor pressure vessels (RPV) under pressurized thermal shock (PTS) conditions. The deterministic assessment is normally performed using flaw assessment procedures based on linear elastic or elastic...
Proc. ASME. PVP2013, Volume 1B: Codes and Standards, V01BT01A058, July 14–18, 2013
Paper No: PVP2013-98161
... The integrity of a reactor pressure vessel (RPV) related to pressurized thermal shocks (PTSs) has been extensively studied. This paper introduces the method of using fracture mechanics for the integrity analysis of a RPV subjected to PTS transients. A 3-D finite element (FE) model is used...
Proc. ASME. PVP2011, Volume 7: Operations, Applications, and Components, 49-56, July 17–21, 2011
Paper No: PVP2011-57784
... Hypothetical Small Break Loss Of Coolant Accident is identified as one of the most severe transients leading to a potential huge Pressurized Thermal Shock on the Reactor Pressure Vessel (RPV). This may result in two-phase flow configurations in the cold legs, according to the operating...
Proc. ASME. PVP2007, Volume 3: Design and Analysis, 335-341, July 22–26, 2007
Paper No: PVP2007-26549
... 21 08 2009 During a pressurized thermal shock (PTS) event, the overlay cladding on the inner surface of reactor pressure vessel (RPV) is subjected to high tensile stress compared to base metal because of the difference in thermal expansion coefficients between cladding and base metal...
Proc. ASME. PVP2008, Volume 3: Design and Analysis, 421-427, July 27–31, 2008
Paper No: PVP2008-61809
... 24 07 2009 The nuclear power plants lifetime is strongly dependent of the guarantee of the reactor pressure vessel (RPV) integrity. Therefore, the RPV integrity has to be demonstrated under the most severe configuration, namely the Pressurized Thermal Shock induced by the Loss...
Proc. ASME. PVP2005, Volume 3: Design and Analysis, 281-292, July 17–21, 2005
Paper No: PVP2005-71371
... 04 08 2008 Under a transient loading like pressurized thermal shock (PTS), the stress discontinuity near the interface between cladding and base metal of a reactor pressure vessel (RPV) is caused by the difference in their thermal expansion coefficients. So the stress intensity factor...
Proc. ASME. PVP2006-ICPVT-11, Volume 3: Design and Analysis, 825-832, July 23–27, 2006
Paper No: PVP2006-ICPVT-11-93368
... such as pressurized thermal shock (PTS). Some functions of PASCAL have been improved such as the Monte Carlo method, the probability of crack detection (POD) by inspection and the graphical user interface (GUI). Using the improved PASCAL, case studies on some parameters for some typical PTS transients have been...