Results 31 to 40 of about 279 (157)
CONSOLIDATED EDISON THORIUM REACTOR-REACTOR VESSEL INTERNAL COMPONENTS DESIGN [PDF]
, 1960 The design functions and fabrication details for internal components of the CETR are presented and pertinent analytical stress studies are summarized. Functions of the internal components include proper orientation and support for the fuel elements, proper distribution of primary coolant within the reactor vessel, and the establishment of guide ...
Ficor, J. +3 more
openaire +2 more sources
Nuclear Engineering and TechnologyThe construction of random turbulent excitation on the surface of reactor core barrel plays a very important role in the vibration fatigue analysis of the core barrel structure. In order to construct the power spectral density function of the core barrel
Tiancai Tan +4 more
doaj +1 more source
Temperature Response of the HTR-10 during the Power Ascension Test
Science and Technology of Nuclear Installations, 2015 The 10 MW High Temperature Gas-Cooled Reactor-Test Module (HTR-10) is the first High Temperature Gas-Cooled Reactor in China. With the objective of raising the reactor power from 30% to 100% rated power, the power ascension test was planned and performed
Fubing Chen, Yujie Dong, Zuoyi Zhang
doaj +1 more source
Westinghouse fluence methodology uncertainty estimates for reactor vessel internals fast neutron exposure evaluation in subsequent license renewal period [PDF]
EPJ Web of ConferencesThe United States Nuclear Regulatory Commission (USNRC) has expressed concerns about the calculated fast neutron fluence exposure uncertainties for the reactor vessel internals (RVI) of light water reactors for extended operation [1, 2].
Chen Jianwei, Amiri Benjamin, Geer Jared
doaj +1 more source
Earthquake response of a core shroud for APR1400
Nuclear Engineering and Technology, 2021 The core shroud is one of the most important internal components of the reactor vessel internals because it meets the neutron fluence directly emitted by the nuclear fuel.
Myung Jo Jhung +2 more
doaj +1 more source
Verification and Validation of CFD analysis for 1/7th scale model of APR1400 for CVAP
Nuclear Engineering and TechnologyThis paper presents a methodology for analyzing the internal flow of the APR1400 Reactor Vessel Internals (RVI) using Computational Fluid Dynamics (CFD).
Giwon La +3 more
doaj +1 more source
EnergiesThe aim of this paper is to present the isotopic changes in nuclear fuel during the first reactor cycle of the Korean Advanced Power Reactor 1400 (APR1400).
Mikołaj Oettingen, Juyoul Kim
doaj +1 more source
Normalizing treatment influence on the forged steel SAE 8620 fracture properties
Materials Research, 2005 In a PWR nuclear power plant, the reactor pressure vessel (RPV) contains the fuel assemblies and reactor vessels internals and keeps the coolant at high temperature and high pressure during normal operation.
Paulo de Tarso Vida Gomes +3 more
doaj +1 more source
(International Thermonuclear Experimental Reactor support) [PDF]
, 1990 This report summarizes the activities under LLNL Purchase Order B089367, the purpose of which is to support the University/Lawrence Livermore National Laboratory Magnetic Fusion Program by evaluating the status of research relative to other national and international programs and assist in long-range plans and development strategies for magnetic fusion
openaire +2 more sources
On the effect of the core boundary power distribution on the radiation situation in reactor components [PDF]
EPJ Web of ConferencesThe assessment of the neutron flux distribution in nuclear power plant components, like reactor internals and the pressure vessel, is one of the most important parts of their residual lifetime evaluation process because the irradiation damage of these ...
Košťál Michal +14 more
doaj +1 more source