Results 61 to 70 of about 273,037 (331)

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

open access: yesYuanzineng 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

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

open access: yes, 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   +3 more
core   +1 more source

Microstructural Evolution and Vacancy Defect Formation in Mn–Mo–Ni RPV Steel Under Low Cycle Fatigue: Insights From EBSD and PALS

open access: yesAdvanced Engineering Materials, EarlyView.
Low‐cycle fatigue damage in Mn–Mo–Ni reactor pressure vessel steel is examined using a combined electron backscatter diffraction and positron annihilation lifetime spectroscopy approach. The study correlates texture evolution, dislocation substructure development, and vacancy‐type defect formation across uniform, necked, and fracture regions, providing
Apu Sarkar   +2 more
wiley   +1 more source

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

open access: yesNuclear 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   +2 more
openaire   +2 more sources

Macroscopic fe-simulation of residual stresses in thermo-mechanically processed steels considering phase transformation effects [PDF]

open access: yes, 2019
Residual stresses are an important issue as they affect both the manufacturing processes as well as the performance of the final parts. Taking into account the whole process chain of hot forming, the integrated heat treatment provided by a defined ...
Behrens, B. A., Chugreev, A., Kock, C.
core  

A Mariotte-based verification system for heat-based sap flow sensors [PDF]

open access: yes, 2012
Determination of the accuracy of commonly used techniques for measuring sap flux density in trees often presents a challenge. We therefore designed and built a verification system for heat-based sap flow sensors typically used at stem level.
De Pauw, DJW, Steppe, Kathy, Teskey, RO
core   +1 more source

Thermal‐hydraulic analysis of an open‐grid megawatt gas‐cooled space nuclear reactor core

open access: yesInternational Journal of Energy Research, 2020
The development of deep space exploration requires space nuclear reactor with higher power and better endurance. In order to meet the increasing high power requirements for space applications, an Open‐grid MEgawatt Gas‐cooled spAce nuclear reactor (OMEGA)
Hao Qin   +6 more
semanticscholar   +1 more source

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

open access: yesAdvanced 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   +6 more
wiley   +1 more source

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

open access: yesEPJ 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   +2 more
doaj   +1 more source

Influence of asperities on fluid and thermal flow in a fracture: a coupled Lattice Boltzmann study

open access: yes, 2013
The characteristics of the hydro-thermal flow which occurs when a cold fluid is injected into a hot fractured bedrock depend on the morphology of the fracture.
Flekkøy, Eirik Grude   +2 more
core   +3 more sources

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