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An Overview of the Pressurized Thermal Shock Issue in the Context of the NURESIM Project [PDF]
Science and Technology of Nuclear Installations, 2009 Within the European Integrated Project NURESIM, the simulation of PTS is investigated. Some accident scenarios for Pressurized Water Reactors may cause Emergency Core Coolant injection into the cold leg leading to PTS situations. They imply the formation of temperature gradients in the thick vessel walls with consequent localized stresses and the ...
M. Ilvonen +14 more
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Integrated Software Environment for Pressurized Thermal Shock Analysis [PDF]
Science and Technology of Nuclear Installations, 2011 The present paper describes the main features and an application to a real Nuclear Power Plant (NPP) of an Integrated Software Environment (in the following referred to as “platform”) developed at University of Pisa (UNIPI) to perform Pressurized Thermal
Dino Araneo +6 more
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Application of the French Codes to the Pressurized Thermal Shocks Assessment
Nuclear Engineering and Technology, 2016 The integrity of a reactor pressure vessel (RPV) related to pressurized thermal shocks (PTSs) has been extensively studied. This paper introduces an integrity assessment of an RPV subjected to a PTS transient based on the French codes.
Mingya Chen +8 more
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Review of pressurized thermal shock studies of large scale reactor pressure vessels in Hungary [PDF]
Fracture and Structural Integrity, 2016 In Hungary, four nuclear power units were constructed more than 30 years ago; they are operating to this day. In every unit, VVER-440 V213-type light-water cooled, light-water moderated, pressurized water reactors are in operation.
Tamás Fekete
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Numerical Analysis Related to the ROCOM Pressurized Thermal Shock Benchmark
Fluids, 2022 The development, verification, and validation of Computational Fluid Dynamics (CFD) codes in reference to nuclear power plant (NPP) safety has been a focus of many research organizations over the last few decades.
Thomas Höhne, Sören Kliem
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Methodological developments in the field of structural integrity analyses of large scale reactor pressure vessels in Hungary [PDF]
Fracture and Structural Integrity, 2016 Buildings, structures and systems of large scale and high value (e.g. conventional and nuclear power plants, etc.) are designed for a certain, limited service lifetime.
Tamás Fekete
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Vessel failure sensitivities of an advanced reactor for SBLOCA
Nuclear Engineering and Technology, 2020 Plant-specific analyses of an advanced reactor have been performed to assure the structural integrity of the reactor pressure vessel during transient conditions, which are expected to initiate pressurized thermal shock (PTS) events.
Myung Jo Jhung +3 more
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Verification of probabilistic fracture mechanics analysis code PASCAL for reactor pressure vessel
Mechanical Engineering Journal, 2023 A probabilistic fracture mechanics (PFM) analysis code, PASCAL, has been developed by Japan Atomic Energy Agency for failure probability and failure frequency evaluation of reactor pressure vessels (RPVs) considering neutron irradiation embrittlement and
Kai LU +10 more
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Frontiers in Energy Research, 2022 When the large pressurized water reactor in-vessel retention (IVR) system is put into operation, the outer wall of the reactor pressure vessel (RPV) will experience severe temperature fluctuations and be subjected to high internal pressure loads at the ...
Dahuan Zhu +6 more
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Heliyon, 2023 In the research field of reactor pressure vessel (RPV) subjected to pressurized thermal shock (PTS), the traditional linear elastic analytical method generally ignores the plastic properties of cladding. In fact, the neutron irradiation in RPV is easy to
Xin Sun, Guozhong Chai, Xiangqing Li
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