Results 1 to 10 of about 30,790,443 (235)
Nuclear Engineering and Technology, 2022 In the one-dimensional thermal-hydraulic (TH) codes, a subcooled boiling model to predict the void fraction profiles in a vertical channel consists of wall heat flux partitioning, the vapor condensation rate, the bubbly-to-slug flow transition criterion,
Tae Beom Lee, Yong Hoon Jeong
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Prediction Model of the Outer Radiation Belt Developed by Chungbuk National University [PDF]
Journal of Astronomy and Space Sciences, 2014 The Earth’s outer radiation belt often suffers from drastic changes in the electron fluxes. Since the electrons can be a potential threat to satellites, efforts have long been made to model and predict electron flux variations.
Dae-Kyu Shin +3 more
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AIP Advances, 2021 We developed a numerical solver for the drift–diffusion and Poisson equations in one-dimensional semiconductor detectors, including the possibility of an arbitrary number of donors and acceptors acting as trapping centers, Schottky or Ohmic contact type,
P. Zambon
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Mechanisms of the electron density depletion in the SAR arc region [PDF]
Annales Geophysicae, 1996 This study compares the measurements of electron density and temperature and the integral airglow intensity at 630 nm in the SAR arc region and slightly south of this (obtained by the Isis 2 spacecraft during the 18 December 1971 magnetic storm), with
A. V. Pavlov
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Dynamically stable nanostructures in heavy-ion implanted silica glass
Nuclear Energy and Technology, 2016 Previously reported experimental data have been used for kinetic analysis of the dynamically stable structure formation under implantation of 60 keV Au– or Cu– ions into silica glass.
О.А. Plaksin
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Physics of toroidal gap heat loading on castellated plasma-facing components
Nuclear Materials and Energy, 2019 Because the gaps between plasma-facing components in fusion devices are comparable in size to the ion Larmor radius (of the order of 1 mm), magnetic field line tracing, the so-called ''optical approximation'', cannot accurately predict the fine scale ...
R. Dejarnac +5 more
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Yuanzineng kexue jishu, 2022 To ensure the safe operation of the steam generator (SG) in the nuclear power system is of great importance. A number of threedimensional thermalhydraulic SG analysis codes have been developed which used for SG thermal safety analysis and design ...
TIAN Wenxi;WANG Mingjun;ZENG Chunjie;QIU Suizheng;SU Guanghui
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Journal of MMIJ, 2017 A numerical simulator is developed as a part of a Japanese National hydrate research program (MH21, funded by METI) to examine performance of methane gas production system from methane hydrate layer under deep seabed.
Yoshiyuki SHIMIZU +2 more
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TAPINS: A THERMAL-HYDRAULIC SYSTEM CODE FOR TRANSIENT ANALYSIS OF A FULLY-PASSIVE INTEGRAL PWR
Nuclear Engineering and Technology, 2013 REX-10 is a fully-passive small modular reactor in which the coolant flow is driven by natural circulation, the RCS is pressurized by a steam-gas pressurizer, and the decay heat is removed by the PRHRS.
YEON-GUN LEE, GOON-CHERL PARK
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MathematicsThe arrival of tracers at boundaries with defined distances from the origin of their motion in stochastically fluctuating advection processes is investigated.
Holger Nobach, Stephan Eule
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