Results 11 to 20 of about 662,342 (249)
Evaluation of heat-flux distribution at the inner and outer reactor vessel walls under the in-vessel retention through external reactor vessel cooling condition [PDF]
Nuclear Engineering and Technology, 2015 Background: A numerical simulation was carried out to investigate the difference between internal and external heat-flux distributions at the reactor vessel wall under in-vessel retention through external reactor vessel cooling (IVR-ERVC). Methods: Total
Sang Mo An, Hwan Yeol Kim, Jaehoon Jung
exaly +4 more sources
Reactor Vessel Water Level Estimation During Severe Accidents Using Cascaded Fuzzy Neural Networks
Nuclear Engineering and Technology, 2016 Global concern and interest in the safety of nuclear power plants have increased considerably since the Fukushima accident. In the event of a severe accident, the reactor vessel water level cannot be measured.
Man Gyun Na, Kwae Hwan Yoo
exaly +3 more sources
Nuclear Engineering and Technology, 2014 Safety-related parameters are very important for confirming the status of a nuclear power plant. In particular, the reactor vessel water level has a direct impact on the safety fortress by confirming reactor core cooling.
Man Gyun Na
exaly +3 more sources
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
doaj +2 more sources
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.
core +4 more sources
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
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
doaj +1 more source
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
core +2 more sources
Nuclear Engineering and Technology, 2021 Existing elastic analysis methods cannot be adhered to in order to assess the structural integrity of a reactor vessel and internals for a beyond design basis earthquake.
Sang-Jeong Lee +5 more
doaj +1 more source
Nuclear Engineering and Technology, 2023 In the late in-vessel phase of a nuclear reactor severe accident, the internal heat transfer and crust evolution during the debris bed melting process have important effects on the thermal load distribution along the vessel wall, and further affect the ...
Chao Lv +4 more
doaj +1 more source