Results 51 to 60 of about 104,473 (310)

Research on Thermal-hydraulic Calculation Method of Steam Generator for Integrated Fast Reactor

Yuanzineng kexue jishu
Integrated fast reactors emerge as the future direction for sodium cooled fast reactor systems. Steam generator is critical components in reactor systems. Their design directly impacts integrated fast reactor construction quality.
YU Qi, ZHU Lina, ZHU Huanjun, HOU Bin
doaj   +1 more source

Development of a three-dimensional method for thermal-hydraulics/neutronics coupling analysis and its application on CFETR helium-cooled solid breeder blanket

International Journal of Advanced Nuclear Reactor Design and Technology, 2021
Blankets are of practical importance in the fusion reactor due to their main functions for engineering application. As the fusion power designed for the Chinese Fusion Engineering Test Reactor (CFETR) is increased from 200 MW to 1.5 GW during its phase ...
Qiang Lian, Wenxi Tian, Suizheng Qiu, G.H. Su   +3 more
doaj   +1 more source

Numerical analysis of temperature stratification in the CIRCE pool facility [PDF]

, 2019
In the framework of Heavy Liquid Metal (HLM) GEN IV Nuclear reactor development, the focus is in the combination of security and performance. Numerical simulations with Computational Fluid Dynamics (CFD) or system codes are useful tools to predict the ...
EDEMETTI, FRANCESCO, FERRONI, Luisa, GIANNETTI, FABIO, NARCISI, Vincenzo, TARANTINO, Mariano, TASSONE, ALESSANDRO   +5 more
core   +1 more source

Evaluation of Plasticity and Creep Parameters From Tensile Stress–Strain Data for a Range of Strain Rates

Advanced Engineering Materials, EarlyView.
This plot compares experimental tensile stress–strain curves (with 4 different strain rates) and corresponding modelled curves (obtained using the optimised sets of Voce and Miller–Norton parameter values shown). The inferred M‐N values, characterizing the creep, are very similar to those obtained via conventional creep testing.
S. Ooi, R. P. Thompson, T. W. Clyne
wiley   +1 more source

Characterizing groundwater flow and heat transport in fractured rock using Fiber-Optic Distributed Temperature Sensing [PDF]

, 2013
International audienceWe show how fully distributed space-time measurements with Fiber-Optic Distributed Temperature Sensing (FO-DTS) can be used to investigate groundwater flow and heat transport in fractured media.
Anderson, Becker, Brouyère, Dorn, Freifeld, Geiger, Hausner, Hurtig, Illman, Le Borgne, Le Borgne, Leaf, M.V. Klepikova, Ma, Macfarlane, N. Lavenant, Neuman, Neuville, Novakowski, O. Bour, P. Goderniaux, Paillet, Pehme, R. Hochreutener, Ruelleu, Selker, T. Le Borgne, T. Read, Tyler, V. Bense, V. Boschero   +30 more
core   +3 more sources

Calculations of research reactor thermal hydraulics based on VVER-440 fuel assamblies [PDF]

Nuclear Energy and Technology, 2019
Having thoroughly analyzed the design features of VVER-type pressurized water reactors and VVR-type research reactors, the authors propose a design of a research reactor with low-enriched fuel based on deeply updated VVER-440 fuel assemblies. The research reactor is intended to solve a wide range of applied problems in nuclear physics, radiation ...
Doan,Thi Zieu Chang, Lazarenko,Georgy, Lazarenko,Denis   +2 more
openaire   +2 more sources

Exploring Dipolar Dynamics and Ionic Transport in Metal‐Organic Frameworks: Experimental and Theoretical Insights

Advanced Functional Materials, EarlyView.
In this study, the interplay of dipolar dynamics and ionic charge transport in MOF compounds is investigated. Synthesizing the novel structure CFA‐25 with integrated freely rotating dipolar groups, local and macroscopic effects, including interactions with Cs cations are explored.
Ralph Freund, Arthur Schulz, Peter Lunkenheimer, Maryana Kraft, Thomas Bergler, Harald Oberhofer, Dirk Volkmer   +6 more
wiley   +1 more source

Cooling the intact loop of primary heat transport system using Shutdown Cooling System in case of LOCA events

EPJ Nuclear Sciences & Technologies, 2015
The purpose of this paper is to model the operation of the Shutdown Cooling System (SDCS) for CANDU 6 nuclear power plants in case of LOCA accidents, using Flowmaster calculation code, by delimiting models and setting calculation assumptions, input data ...
Icleanu Diana Laura, Prisecaru Ilie, Jianu Iulia Nicoleta   +2 more
doaj   +1 more source

Effects of Freezing on Soil Temperature, Freezing Front Propagation and Moisture Redistribution in Peat: Laboratory Investigations [PDF]

, 2012
There are not many studies that report water movement in freezing peat. Soil column studies under controlled laboratory settings can help isolate and understand the effects of different factors controlling freezing of the active layer in organic covered ...
Hayashi, Masaki, Nagare, Ranjeet M., Quinton, William L., Schincariol, Robert A.   +3 more
core   +1 more source

Technological complex for production, transportation and storage of gas from the offshore gas and gas hydrates fields [PDF]

, 2016
Purpose. Substantiation and development of schematics acceptable for the existing technological methods of natural gas production and transportation from the offshore fields of gas or gas hydrates.
Pedchenko, L, Pedchenko, М
core   +2 more sources