Results 41 to 50 of about 52,960 (385)

Molten Salt Reactor Sourdough Refueling and Waste Management Strategy

open access: yesJournal of Nuclear Engineering, 2021
This paper presents a new approach to the spent nuclear fuel (SNF) problem, which is uniquely enabled by a liquid fuel form, specifically as in the case of molten salt reactor (MSR) systems.
Alexander M. Wheeler, O. Chvála
semanticscholar   +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

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

A Preliminary Exergy Analysis of the EU DEMO Fusion Reactor [PDF]

open access: yes, 2019
Purpose of the present study is the exergy analysis of EU DEMO pulsed fusion power plant considering the Primary Heat Transfer Systems, the Intermediate Heat Transfer System (IHTS) including the Energy Storage System (ESS) as a first option to ensure the
Caruso, Gianfranco   +2 more
core   +1 more source

GEN-FOAM MODEL AND BENCHMARK OF DELAYED NEUTRON PRECURSOR DRIFT IN THE MOLTEN SALT REACTOR EXPERIMENT

open access: yes, 2021
The effective delayed neutron fraction is an important reactor kinetics parameter. In flowing liquid-fuel reactors, this differs from the delayed neutron fraction because of the emission of delayed neutrons with a lower energy spectrum than prompt and ...
Jun Shi, M. Fratoni
semanticscholar   +1 more source

Thermal Hydraulics Analysis of the Distribution Zone in Small Modular Dual Fluid Reactor

open access: yesMetals, 2020
The Small Modular Dual Fluid Reactor (SMDFR) is a novel molten salt reactor based on the dual fluid reactor concept, which employs molten salt as fuel and liquid lead/lead-bismuth eutectic (LBE) as coolant.
Chunyu Liu   +3 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

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

Analysis of submerged bearing eccentricity on support characteristics of molten salt pump for thorium nuclear power system

open access: yesHe jishu, 2022
BackgroundWith the development of thorium molten salt reactor nuclear energy system (TMSR) from experimental reactor to research, demonstration and commercial reactor, its shafting evolved into the slender flexible rotor supported by submerged bearing ...
MA Baiqing   +6 more
doaj   +1 more source

Molten salts and nuclear energy production

open access: yes, 2005
Molten salts (fluorides or chlorides) have been taken in consideration very soon in nuclear energy production researches. This was initially due to their advantageous physical properties: good heat transfer capacity, radiation insensitivity, high boiling
Le Brun, C.
core   +3 more sources

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