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Microstructural Characterization of Reactor Pressure Vessel Steels
Metals, 2023 Ion irradiation is a promising tool to emulate neutron-irradiation effects on reactor pressure vessel (RPV) steels, especially in the situation of limited availability of suitable neutron-irradiated material.
Libang Lai +4 more
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Study on the influences of RPV deformation on CHF under IVR conditions
Frontiers in Energy Research, 2023 After the reactor core melt, the thermal impact of high temperature molten mixture to the lower head of reactor pressure vessel (RPV) will cause the shape change of cooling channel constituted by reactor pressure vessel outer surface and other supporting
Shuang Wen +13 more
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Conducting local cutout from the surface of the VVER-1000 reactor vessel
Trudy Odesskogo Politehničeskogo Universiteta, 2019 Integrity of the reactor pressure vessel is a critical element in demonstrating the capability of nuclear power plant for operation to at least 80 years.
Олексій Геннадійович Руденко +3 more
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Spinodal decomposition and radiation damage of a FeCuMnNi high-entropy alloy
Nuclear Materials and Energy, 2023 The precipitation of Cu-rich phases during the irradiation process will reduce radiation resistance in Fe-Cu-Mn-Ni reactor pressure vessel steels. Therefore, high-entropy alloys with excellent radiation resistance are expected to replace reactor pressure
Qingwei Guo +5 more
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Nuclear Engineering and Technology, 2022 This paper presents a numerical investigation of two-phase natural circulation flows established when external reactor vessel cooling is applied to a severe accident of the APR1400 reactor for the in-vessel retention of the core melt.
Min Seop Song +3 more
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Test of Critical Heat Flux on Outer Surface of CAP1400 Pressurized Reactor Vessel
Shanghai Jiaotong Daxue xuebao, 2022 A full height sliced test facility is established based on the modeling process. The heating test section is manufactured by adopting the explosive welding technology, and the surface of carbon steel can simulate the actual surface characteristic of a ...
SHI Guobao, ZHENG Mingguang, ZHANG Kun, KUANG Bo, LIU Pengfei
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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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Non-hardening embrittlement mechanism of pressure vessel steel Ni-Cr-Mo-V welds during thermal aging
Advances in Mechanical Engineering, 2020 The mechanical performance of reactor pressure vessel materials is an important factor in the safety and economics of the operation of a nuclear power plant.
Guojun Wei +4 more
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Validation of the Serpent 2 Monte Carlo code for reactor dosimetry applications [PDF]
EPJ Web of Conferences, 2023 The verification and validation (V&V) of the Serpent 2 Monte Carlo code for 3-D reactor dosimetry applications is being carried out at VTT. Two code-to-code computational benchmark cases were calculated by MCNP and Serpent 2. The computational efficiency
Dorval Eric
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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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