... Abstract Cases of stress corrosion cracking (SCC) in Ni-base alloy weld metals welded to the low alloy steel (LAS) in reactor pressure vessel (RPV) components have led to discussions on the possibility of SCC propagating into the RPV. In the previous study, the fracture mode of dissimilar metal...

... with defining the state-of-the-art of the Warm Pre-Stress (WPS) effect, which has an impact on the reactor pressure vessel (RPV) brittle fracture margin in both deterministic and probabilistic terms, was collected. To gather the worldwide experience of the WPS approaches and models, a comprehensive...

... Abstract The H2020 FRACTESUS project is aimed at the validation of miniaturized compact tension (MCT) specimen. More specifically the usage of the MCT with the Master Curve (MC) oriented fracture toughness testing of reactor pressure vessel (RPV) materials in hot cell conditions...

... Abstract As nuclear power plants age and their lifetimes are being extended, the possibility and need to perform repairs of safety critical and hard to replace components is ever increasing. For example, defects in the reactor pressure vessel caused by exposure to high temperature, pressure...

... Abstract Cases of stress corrosion cracking (SCC) in Ni-base alloy weld metals welded to low alloy steel (LAS) of reactor pressure vessel (RPV) components have led to discussions on the possibility of SCC propagating into the RPV. However, the fracture behavior and the assessment methodology...

... Abstract Residual stress is one of the most important influence factors in the structural integrity assessment of the nuclear components. However, at the present, there are few examples of residual stress measurements for thick butt-welded plates such as the reactor pressure vessels (RPVs...

... 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...

.... A proposed method using robotized gas metal arc welding-cold metal transfer to repair a “worst-case” scenario, linear crack like defect beneath the cladding, which extended into the reactor pressure vessel steel, was evaluated on laboratory scale in previous works (PVP2020-21233, PVP2020-21236...

... 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...

... 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 REGRESSION...

... 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 programs...

... 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, reactor...

... 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. It is well...

... 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 to material...

... 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 of Pressure-Temperature...

... Abstract During the 2012 outage at Doel 3 and Tihange 2 Nuclear Power Plants, a large number of quasi-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...

... 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...

... 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...

... 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...

... Pressure Vessel, Fracture Mechanics ABSTRACT 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...