Results 31 to 40 of about 23,190 (286)

Thermal Characteristics of High Temperature Naturally Circulating Helium Cooling Loop

open access: yesJournal of Mechanical Engineering, 2018
The paper deals with the process properties in terms of the heat transfer, i.e. the thermal performance of the thermal-process units within a helium loop intended for the testing of the decay heat removal (DHR) from the model of the gas-cooled fast ...
Dzianik František   +2 more
doaj   +1 more source

Hydrodynamic Properties of High Temperature Natural Circulating Helium Cooling Loop

open access: yesJournal of Mechanical Engineering, 2017
The paper deals with the hydrodynamic properties, i.e. the consumption of mechanical energy expressed by pressure drops within a helium loop intended for the testing of decay heat removal (DHR) from the model of a gas-cooled fast reactor (GFR).
Dzianik František, Gužela Štefan
doaj   +1 more source

Investigation of Characteristics of Passive Heat Removal System Based on the Assembled Heat Transfer Tube

open access: yesNuclear Engineering and Technology, 2016
To get an insight into the operating characteristics of the passive residual heat removal system of molten salt reactors, a two-phase natural circulation test facility was constructed.
Xiangcheng Wu   +6 more
doaj   +1 more source

The Gas-Cooled Fast Reactor: Report on Safety System Design for Decay Heat Removal [PDF]

open access: yes, 2003
The gas-cooled fast reactor (GFR) was chosen as one of the Generation IV nuclear reactor systems to be developed based on its excellent potential for sustainability through reduction of the volume and radiotoxicity of both its own fuel and other spent ...
Driscoll, M. J.   +5 more
core   +1 more source

Study on Inherent Safety Characteristic on Thermal-hydraulic of Pool-type Sodium-cooled Fast Reactors

open access: yesYuanzineng kexue jishu, 2023
The concept of the inherent safety characteristic on thermal-hydraulic of the pool-type sodium-cooled fast reactor was proposed and its formation mechanism was analyzed.
ZHOU Zhiwei;XUE Xiuli;YANG Yong;YANG Hongyi
doaj  

CRBRP decay heat removal systems [PDF]

open access: yes, 1977
The Decay Heat Removal Systems for the Clinch River Breeder Reactor Plant (CRBRP) are designed to adequately remove sensible and decay heat from the reactor following normal shutdown, operational occurrences, and postulated accidents on both a short term
Louison, R.   +3 more
core  

Structural insights into an engineered feruloyl esterase with improved MHET degrading properties

open access: yesFEBS Letters, EarlyView.
A feruloyl esterase was engineered to mimic key features of MHETase, enhancing the degradation of PET oligomers. Structural and computational analysis reveal how a point mutation stabilizes the active site and reshapes the binding cleft, expading substrate scope.
Panagiota Karampa   +5 more
wiley   +1 more source

A light‐triggered Time‐Resolved X‐ray Solution Scattering (TR‐XSS) workflow with application to protein conformational dynamics

open access: yesFEBS Open Bio, EarlyView.
Time‐resolved X‐ray solution scattering captures how proteins change shape in real time under near‐native conditions. This article presents a practical workflow for light‐triggered TR‐XSS experiments, from data collection to structural refinement. Using a calcium‐transporting membrane protein as an example, the approach can be broadly applied to study ...
Fatemeh Sabzian‐Molaei   +3 more
wiley   +1 more source

ASSESSMENT OF CONDENSATION HEAT TRANSFER MODEL TO EVALUATE PERFORMANCE OF THE PASSIVE AUXILIARY FEEDWATER SYSTEM

open access: yesNuclear Engineering and Technology, 2013
As passive safety features for nuclear power plants receive increasing attention, various studies have been conducted to develop safety systems for 3rd-generation (GEN-III) nuclear power plants that are driven by passive systems.
YUN-JE CHO   +5 more
doaj   +1 more source

Natural circulation characteristics of main loop after shutdown of liquid-fuel molten salt reactor

open access: yesHe jishu
BackgroundThe molten salt reactor (MSR) is one of the six advanced reactors identified by the Generation IV International Forum. The MSR exhibits unique characteristics, such as intrinsic safety, sustainable development, nuclear nonproliferation, natural
XUE Shuaiyu   +3 more
doaj   +1 more source

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