Results 21 to 30 of about 22,482 (311)

Entropy Generation Rate and Hydrogen Production Rate Analyses for Steam Methane Reforming Reactor Heated by Molten Salt

open access: yes发电技术, 2020
Solar thermochemical energy storage can effectively solve the uneven distribution of solar energy in time and space. Based on the model of industrial methane steam reforming reactor, the model of steam methane reforming reactor heated by molten salt (MS ...
Penglei LI   +5 more
doaj   +1 more source

XAFS analyses of molten metal fluorides [PDF]

open access: yes, 2009
X-ray absorption fine structure studies of molten metal fluorides containing the materials related to nuclear engineering are intensively summarized. By using XAFS spectra data of divalent and trivalent cation metal fluorides in molten state which have ...
Adya, Ashok K.   +4 more
core   +3 more sources

On the thermal dynamic behaviour of the helium-cooled DEMO fusion reactor [PDF]

open access: yes, 2019
The EU-DEMO conceptual design is being conducted among research institutions and universities from 26 countries of European Union, Switzerland and Ukraine. Its mission is to realise electricity from nuclear fusion reaction by 2050.
Barucca L.   +3 more
core   +1 more source

Lanthanides extraction processes in molten fluoride media. Application to nuclear spent fuel reprocessing [PDF]

open access: yes, 2009
This paper describes four techniques of extraction of lanthanides elements (Ln) from molten salts in the general frame of reprocessing nuclear wastes; One of them is chemical: the precipitation of Ln ions in insoluble compounds (oxides or oxifluorides);
Cassayre, Laurent   +5 more
core   +2 more sources

Calculation for Dose Distribution and for Equipment Shielding of Molten Salt Reactor Cooling Circuit

open access: yesYuanzineng kexue jishu, 2022
LiF-BeF2-ZrF4-UF4 and LiF-BeF2 have been employed as fuel salt and coolant in liquid fueled molten salt reactor, respectively. A heat exchanger containing both fuel salt and cooling salt is placed inside the reactor vessel to dissipate the heat produced
LI Changyuan;XIA Xiaobin;CAI Jun;ZHANG Zhihong;WANG Jianhua;QIAN Zhicheng;CHEN Defeng;XIE Guiying
doaj  

MSR Simulation with cGEMS: Fission Product Release and Aerosol Formation

open access: yesJournal of Nuclear Engineering, 2022
The release of fission products and fuel materials from a molten-salt fast-reactor fuel in hypothetical accident conditions was investigated. The molten-salt fast reactor in this investigation features a fast neutron spectrum, operating in the thorium ...
Sergii Nichenko   +2 more
doaj   +1 more source

ATWS accident analysis of rod withdrawal in small modular molten salt reactor

open access: yesHe jishu, 2022
[Backgrounds] Among all kinds of accidents beyond the design basis of molten salt reactor (MSR), the ATWS accident of rod withdrawal is the most typical one, which is the test of the safety capability limit of the reactor.
XU Tiangui   +4 more
doaj   +1 more source

Electrochemical extraction of europium from molten fluoride media [PDF]

open access: yes, 2009
This work concerns the extraction of europium from molten fluoride media. Two electrochemical ways have been examined: (i) the use of a reactive cathode made of copper and (ii) the co-deposition with aluminium on inert electrode, leading to the formation
Cassayre, Laurent   +4 more
core   +3 more sources

Passive residual heat removal characteristics of liquid fuel molten salt reactor salt drain tank

open access: yesHe jishu, 2023
BackgroundLiquid molten salt reactor has many features such as high economy, safety and on-line fuel processing. The emergency draining salt passive residual heat removal system (EDS-PRHRS) is a unique residual heat removal system design for liquid fuel ...
QU Pengrong   +4 more
doaj   +1 more source

Development of Pyrochemical Reprocessing of the Spent Nuclear Fuel and Prospects of Closed Fuel Cycle [PDF]

open access: yes, 2007
Molten-Salt Reactor (MSR) is a design of an advanced reactor system from the GEN IV family working in thermal or epithermal neutron spectrum and using thorium or transuranium fuel in the form of molten fluorides.
Chuchvalcova-Bimova, K. (K)   +4 more
core   +2 more sources

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