Results 11 to 20 of about 3,020,549 (269)
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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Model Materials for Reactor Pressure Vessel [PDF]
Acta Physica Polonica A, 2010 In this paper we report preliminary results from a study focused on investigation of the role of elements as Cr, Ni, Mn and Si in the radiation stability of reactor pressure vessel steels. Twelve model ferritic steels and eight model welds with basic composition derived from Russian VVER-1000 and Western PWR reactor pressure vessel materials were ...
J. Degmová, L. Debarberis, V. Kršjak
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Use of master curve technology for assessing shallow flaws in a reactor pressure vessel material
, 2022 Art. 031407, 11 S.In the NESC-IV project, an experimental/analytical program was performed to develop validated analysis methods for transferring fracture toughness data to shallow flaws in reactor pressure vessels subject to biaxial loading in the lower-
Wintle, J. +6 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
doaj +1 more source
Design by analysis of ductile failure and buckling in torispherical pressure vessel heads [PDF]
, 2008 Thin shell torispherical pressure vessel heads are known to exhibit complex elastic-plastic deformation and buckling behaviour under static pressure. In pressure vessel Design by Analysis, the designer is required to assess both of these behaviour modes ...
Camilleri, Duncan +2 more
core +4 more sources
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
doaj +1 more source
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
doaj +1 more source
Simulation of the influence of hydrophones used for the characterization of pressure field distribution in low frequency, high power ultrasonic reactor vessels [PDF]
, 2007 This paper describes the use of a finite element (FE) modeling approach to investigate the influence of different hydrophone designs in laboratory scale reactor vessels.
O'Leary, R.L., Harvey, G., Gachagan, A.
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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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