Results 11 to 20 of about 1,270 (244)
Science and Technology of Nuclear Installations, 2021 The safety-risk pressurized thermal shock (PTS) have on a reactor pressure vessel (RPV) is one of the most important studies for the lifetime ageing management of a reactor.
M. Annor-Nyarko, Hong Xia
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Mechanical Engineering Journal, 2020 Probabilistic fracture mechanics (PFM) is considered a promising methodology in assessing the integrity of structural components in nuclear power plants because it can rationally represent the influence parameters in their probabilistic distributions ...
Kai LU +8 more
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DEVELOPMENT OF THE ALTERNATE PRESSURIZED THERMAL SHOCK RULE (10 CFR 50.61a) IN THE UNITED STATES
Nuclear Engineering and Technology, 2013 In the early 1980s, attention focused on the possibility that pressurized thermal shock (PTS) events could challenge the integrity of a nuclear reactor pressure vessel (RPV) because operational experience suggested that overcooling events, while not ...
MARK KIRK
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Two-Phase Flow Simulations for PTS Investigation by Means of Neptune_CFD Code
Science and Technology of Nuclear Installations, 2009 Two-dimensional axisymmetric simulations of pressurized thermal shock (PTS) phenomena through Neptune_CFD module are presented aiming at two-phase models validation against experimental data. Because of PTS complexity, only some thermal-hydraulic aspects
Maria Cristina Galassi +3 more
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Normalizing treatment influence on the forged steel SAE 8620 fracture properties
Materials Research, 2005 In a PWR nuclear power plant, the reactor pressure vessel (RPV) contains the fuel assemblies and reactor vessels internals and keeps the coolant at high temperature and high pressure during normal operation.
Paulo de Tarso Vida Gomes +3 more
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Nihon Kikai Gakkai ronbunshu, 2020 The Japan Electric Association code, JEAC 4206-2016 specifies a procedure for assessment of a reactor pressure vessel integrity against pressurized thermal shock (PTS) events which postulates a semi-elliptical flaw (10 mm in depth x 60 mm in length ...
Takatoshi HIROTA +2 more
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Science and Technology of Nuclear Installations, 2022 The damage induced pressurized thermal shock (PTS) may pose to a reactor pressure vessel (RPV) is a critical safety requirement assessed as part of the ageing management programme of pressurized water reactors (PWRs).
M. Annor-Nyarko +2 more
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Pressurized Thermal Shock Experiments with Thick Vessels [PDF]
, 1988 A 148-mm-thick pressure vessel containing a long axial flaw was subjected to a combined loading of internal pressure and thermal shock. The experiment was performed to investigate the effects of loading sequence on initiation of brittle fracture and the behavior of a crack propagating into ductile regions.
RH Bryan +3 more
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Metals, 2020 P91 steel is a typical steel used in the manufacture of boilers in ultra-supercritical power plants and heat exchangers in nuclear power plants. For the long-term serviced P91 steel pressurized structures, the main failure mode is the welded joint ...
Kai Yang, Yingjie Zhang, Jianping Zhao
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CFD study of the PTS experiment in ROCOM test facility
Nuclear Engineering and Technology, 2020 With the aging of nuclear reactors, embrittlement of the reactor pressure vessel (RPV) steel, as a consequence of routine operations, is highly probable.
Zoran Čarija +3 more
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