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Keywords: reactor pressure vessel
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Proceedings Papers

Proc. ASME. PVP2021, Volume 4: Materials and Fabrication, V004T06A047, July 13–15, 2021
Paper No: PVP2021-61467
... Proceedings of the ASME 2021 Pressure Vessels & Piping Conference PVP2021 July 13-15, 2021, Virtual, Online PVP2021-61467 STUDY ON FRACTURE BEHAVIOR AND ASSESSMENT FOR DISSIMILAR METAL WELD OF LOW ALLOY STEEL AND NI-BASE ALLOY WELD USING A BWR REACTOR PRESSURE VESSEL MATERIAL Takahiro Hayashi...
Proceedings Papers

Proc. ASME. PVP2021, Volume 4: Materials and Fabrication, V004T06A067, July 13–15, 2021
Paper No: PVP2021-61897
... Proceedings of the ASME 2021 Pressure Vessels & Piping Conference PVP2021 July 13-15, 2021, Virtual, Online PVP2021-61897 ASSESSMENT OF RESIDUAL STRESS FOR THICK BUTT-WELDED PLATE OF A REACTOR PRESSURE VESSEL STEEL Yoosung Ha1, Shigetaka Okano2, Hisashi Takamizawa1, Jinya Katsuyama1 and Masahito...
Proceedings Papers

Proc. ASME. PVP2021, Volume 4: Materials and Fabrication, V004T06A066, July 13–15, 2021
Paper No: PVP2021-61906
... toughness testing of the reactor pressure vessel steels under hot cell conditions. Validation of this method in an industrially-relevant environment will be an important step towards achieving its acceptance by the nuclear authorities, and finally, to induce its prospective usage by the nuclear power plant...
Proceedings Papers

Proc. ASME. PVP2021, Volume 4: Materials and Fabrication, V004T06A048, July 13–15, 2021
Paper No: PVP2021-61981
... environment (e.g. high temperature, high pressure, corrosion environment, neutron irradiation, etc Keywords: Alloy 52, cold metal transfer, gas metal arc Concerning repair welding, should a critical need for repair welding, reactor pressure vessel, repair welding arise, qualified and validated solutions must...
Proceedings Papers

Proc. ASME. PVP2020, Volume 3: Design and Analysis, V003T03A057, August 3, 2020
Paper No: PVP2020-21680
...Abstract Abstract In light water nuclear reactors, the reactor pressure vessel (RPV) plays the critical role of containing the reactor and coolant and is expected to maintain its integrity under a variety of conditions. The RPV is subjected to high neutron flux and temperature, which lead...
Proceedings Papers

Proc. ASME. PVP2020, Volume 8: Operations, Applications, and Components, V008T08A022, August 3, 2020
Paper No: PVP2020-21123
... size is an important factor to protect the reactor pressure vessel from brittle failure but is not explicitly documented in WRC175. However, according to the recent change of Appendix G, the ¼ thickness (¼T) flaw size is postulated in the surface of the nozzle inner corner for the evaluation...
Proceedings Papers

Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A016, August 3, 2020
Paper No: PVP2020-21736
...Abstract Abstract This paper presents a results of brittle fracture (BF) assessment of WWER-1000 reactor pressure vessel (RPV) subjected to pressurized thermal shook (PTS). Work is focused on the two factors affected on the BF safety margin. The first one is the definition of the heat transfer...
Proceedings Papers

Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A018, August 3, 2020
Paper No: PVP2020-21748
... in the modern regulatory method for radiation embrittlement assessment of the Ukrainian WWER-1000 RPVs. reactor pressure vessel radiation embrittlement fracture toughness critical temperature of brittleness surveillance programme weld metal statistical analysis chemical factor synergetic effect...
Proceedings Papers

Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A102, August 3, 2020
Paper No: PVP2020-21481
...Abstract Abstract In order to ensure continued safe operation of European nuclear reactors, it is necessary to solve specific issues that arise from irradiation induced reactor pressure vessel (RPV) embrittlement under long term operation. This requires an extension of the RPV surveillance...
Proceedings Papers

Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A076, August 3, 2020
Paper No: PVP2020-21445
... pressurized thermal shock (PTS) events. austenitic cladding fracture toughness reactor pressure vessel vessel integrity lifetime PROPERTIES OF CLADDING WITH RESPECT TO RPV INTEGRITY Milan Brumovský ÚJV e a.s. , 250 68 e , Czech Republic Keywords: austenitic cladding, fracture toughness...
Proceedings Papers

Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A064, August 3, 2020
Paper No: PVP2020-21430
...Abstract Abstract We have developed a probabilistic fracture mechanics (PFM) analysis code named PASCAL4 for evaluating the failure frequency of reactor pressure vessels (RPVs) through consideration of neutron irradiation embrittlement and transients such as pressurized thermal shock events...
Proceedings Papers

Proc. ASME. PVP2019, Volume 1: Codes and Standards, V001T01A001, July 14–19, 2019
Paper No: PVP2019-93211
...-laminar indications were detected in the lower and upper core shells of the reactor pressure vessels (RPVs). The observed indications could subsequently be attributed to hydrogen flaking induced during the component manufacturing process. As a consequence, both units remained core unloaded pending...
Proceedings Papers

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...
Proceedings Papers

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...
Proceedings Papers

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...
Proceedings Papers

Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 6, Parts A and B, 153-159, July 18–22, 2010
Paper No: PVP2010-25615
... 14 01 2011 The brittle failure assessment for five pressurized water reactor pressure vessels (RPV) of German nuclear power plants (NPP) has been revisited according to an advanced state of the art. Besides of recent innovation in fracture toughness curves and reference temperatures...
Proceedings Papers

Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 7, 211-220, July 18–22, 2010
Paper No: PVP2010-25646
... 14 01 2011 The Reactor Pressure Vessel (RPV) assessment and lifetime evaluation of the nuclear plants leads EDF and AREVA to use CFD tools for the demonstration of the Reactor Pressure Vessel (RPV) integrity. French PWR plants have been studied for a long time and so a large number...
Proceedings Papers

Proc. ASME. PVP2009, Volume 7: Operations, Applications and Components, 383-391, July 26–30, 2009
Paper No: PVP2009-77390
... Proceedings of PVP2009 2009 ASME Pressure Vessels and Piping Division Conference July 26-30, 2009, Prague, Czech Republic PVP2009-77390 CFD-Tools for Assessment of the Reactor Pressure Vessel Integrity in Pressure Thermal Shock Conditions. Thermal-hydraulic Methods and Main Industrial Results...
Proceedings Papers

Proc. ASME. PVP2009, Volume 6: Materials and Fabrication, Parts A and B, 613-620, July 26–30, 2009
Paper No: PVP2009-77035
... by the aid of the Master Curve concept in an appropriate way. An overview on the objectives, the experimental program, and the current status of the project is given. Finally first test results are presented and evaluated. CARINA reactor pressure vessel irradiation behavior fracture toughness crack...
Proceedings Papers

Proc. ASME. PVP2007, Volume 7: Operations, Applications and Components, 45-56, July 22–26, 2007
Paper No: PVP2007-26316
... 21 08 2009 Integrity evaluation methods for nuclear Reactor Pressure Vessels (RPVs) under Pressurised Thermal Shock (PTS) loading are applied by French Utility. They are based on the analysis of the behaviour of cracks under PTS loading conditions due to the emergency cooling during...