Results 11 to 20 of about 279 (157)
Calculation of vver-1000 core baffle temperature distribution for it's swelling assessment
Trudy Odesskogo Politehničeskogo Universiteta, 2020 This paper presents simplified CFD-model of VVER-1000 core baffle cooling to address swelling problems of the reactor internals. Swelling is the main limiting factor in the reactor core internals long term operation of VVER-1000 nuclear units.
Владислав Віталійович Філонов +3 more
doaj +5 more sources
Ex-core neutron exposure monitoring and reactor internals aging management at Ringhals [PDF]
EPJ Web of ConferencesThis paper discusses the management of plant aging at the Ringhals Units 3 and 4 nuclear power plants and provides a summary of its extensive database of reactor dosimetry comparisons.
Fischer Greg +3 more
doaj +1 more source
Nuclear Engineering and Technology, 2019 Nuclear power generates a large portion of the energy used today and plays an important role in energy development. To ensure safe nuclear power generation, it is essential to conduct an accurate analysis of reactor structural integrity.
Jong-beom Park +4 more
doaj +1 more source
Development of Austenitic Stainless Steel Cold-drawn Rods for Nuclear Power Plant Reactor Internals [PDF]
TeshugangAustenitic stainless steel for nuclear power plant reactor internals is extremely strict in terms of purity， grain size， corrosion resistance and mechanical properties， and stable quality materials are crucial to the safe operation of nuclear power ...
Tan Qingfeng, Jia Hongshuai, Wang Yu, Yan Zhandong, Yun Yongjia, Wang Yuhui, Zheng Jihui
doaj +3 more sources
Analysis of the flow distribution and mixing characteristics in the reactor pressure vessel
Nuclear Engineering and Technology, 2021 The analysis of the fluid flow characteristics in reactor pressure vessel is an important part of the hydraulic design of nuclear power plant, which is related to the structure design of reactor internals, the flow distribution at core inlet and the ...
L.L. Tong, L.Q. Hou, X.W. Cao
doaj +1 more source
Investigation of functionals of neutron flux influencing onto VVER-440 reactor pressure vessel [PDF]
Ядерна фізика та енергетика, 2008 The calculational procedure for determination of irradiation conditions of VVER-440 reactor internals is presented. Using the developed procedure, irradiation conditions of Rovno NPP Unit1&2 VVER-440 reactor internals – baffle, basket and barrel – are ...
S. M. Pugach +3 more
doaj
Nuclear Engineering and Technology, 2013 In accordance with the US Nuclear Regulatory Commission (US NRC), Regulatory Guide 1.20, the reactor vessel internals comprehensive vibration assessment program (RVI CVAP) has been developed for an Advanced Power Reactor 1400 (APR1400).
DO-YOUNG KO, KYU-HYUNG KIM
doaj +1 more source
Determination of irradiation conditions of WWER-1000 reactor internals [PDF]
Ядерна фізика та енергетика, 2006 The calculational procedure for determination of irradiation conditions of WWER-1000 reactor internals is presented. Using developed procedure, irradiation conditions of WWER-1000 reactor internals, first of all, baffle and barrel, are determined for a
S. M. Pugach +3 more
doaj
COMPARISON OF TWO TECHNIQUES FOR EVALUATING SPHERICAL INDENTATION DATA
Acta Polytechnica CTU Proceedings, 2020 Flow curves of 15Kh2MFA, Sv 08Kh19N10G2B and 08Kh18N10T steels used for fabrication of WWER-440 nuclear reactor pressure vessel and core internals were obtained using the automated ball indentation (ABI) test technique and compared with flow curves ...
Aleš Materna +2 more
doaj +1 more source
Integrity analysis of an upper guide structure flange
Nuclear Engineering and Technology, 2015 The integrity assessment of reactor vessel internals should be conducted in the design process to secure the safety of nuclear power plants. Various loads such as self-weight, seismic load, flow-induced load, and preload are applied to the internals ...
Ki-Hyoung Lee +2 more
doaj +1 more source