Molten-salt reactors for efficient nuclear fuel utilization without plutonium separation

  • 44 Pages
  • 3.53 MB
  • English
Dept. of Energy, [Office of Energy Technology], Oak Ridge National Laboratory, for sale by the National Technical Information Service , Oak Ridge, Tenn, Springfield, Va
Molten salt reactors., Nuclear fuels., Pluto
StatementJ. R. Engel ... [et al.]; prepared by the Oak Ridge National Laboratory.
SeriesORNL/TM ; 6413, ORNL/TM -- 6413.
ContributionsEngel, J. R.
The Physical Object
Paginationviii, 44 p. :
ID Numbers
Open LibraryOL15229697M

@article{osti_, title = {Molten-salt reactors for efficient nuclear fuel utilization without plutonium separation}, author = {Engel, J R and Grimes, W R and Rhoades, W A and Dearing, J F}, abstractNote = {Research and development studies of molten-salt reactors (MSRs) for special purposes have been under way since and for possible application as possible commercial nuclear Cited by: 5.

Molten-salt reactors (MSRs), because of the fluid nature of the fuel, appear to provide an attractive approach to efficient fuel utilization in the thorium-/sup /U cycle as well as a means for limiting the availability of plutonium and the general proliferation risks associated with nuclear power generation.

MOLTEN-SALT REACTORS FOR EFFICIENT NUCLEAR FUEL UTILIZATION WITHOUT PLUTONIUM SEPARATION J. Engel W. Rhoades W. Grimes J. Dearing i Date Published - August NOTICE: This document contains information of a preliminary nature and was prepared primarily for internal use at the Oak Ridge National Laboratory.

Get this from a library. Molten-salt reactors for efficient nuclear fuel utilization without plutonium separation. [J R Engel; Oak Ridge National Laboratory.]. BibTeX @INPROCEEDINGS{Engel78moltensalt, author = {J. Engel and W. Grimes and W. Rhoades and J. Dearing and Price Printed and Copy Microfiche and J.

Engel and W. A Rhoades and W. Grimes and J. Dearing}, title = {Molten Salt Reactors for the Efficient Nuclear Fuel Utilization without}, booktitle = {Plutonium Separation”, ORNL TM }. Abstract The thorium molten salt reactor nuclear energy system (TMSR) is designed for thorium-based nuclear energy utilization and hybrid nuclear energy application, based on a liquid-fueled thorium molten salt reactor (TMSR-LF) and a solid-fueled thorium molten salt reactor (TMSR-SF).

Description Molten-salt reactors for efficient nuclear fuel utilization without plutonium separation EPUB

Molten-Salt Reactors for Efficient Nuclear Fuel Utilization without Plutonium Separation ORNL-TM Status of Tellurium-Hastelloy-N Studies in Molten-Fluoride Salts ORNL-TM Status of Materials Development for Molten-Salt-Reactors.

Some have solid fuel similar to HTR fuel, others have fuel dissolved in the molten salt coolant. Molten salt reactors (MSRs) use molten fluoride salts as primary coolant, at low pressure. This itself is not a radical departure when the fuel is solid and fixed.

Molten Salt Reactors Nick Touran Molten Salt Reactors (MSRs) are nuclear reactors that use a fluid fuel in the form of very hot fluoride or chloride salt instead of the solid fuel used in most reactors.

Since the fuel salt is liquid, it can be both the fuel (producing the heat) and the coolant (transporting the heat to the power plant). Molten salt reactor (MSR) concepts are based on using a molten salt mixture as a primary nuclear reactor coolant, while the fuel can be either directly dissolved in.

The molten salt reactor (MSR), as one of the Generation IV advanced nuclear systems, has attracted a worldwide interest due to its excellent performances in safety, economics, sustainability, and proliferation resistance.

The aim of this work is to provide and evaluate possible solutions to fissile $$^{} \hbox {U}$$ production and further the fuel transition to thorium fuel Cited by: 4.

Fuels for Molten Salt Reactors Molten salt reactors are usually geared toward the thorium-uranium fuel cycle. They were developed initially when breeder reactor designs were being emphasized. The Molten Salt Fast Reactor (MSFR) proposed by the Centre National de la Recherche Scientifique (CNRS) is another liquid fueled fast reactor concept [7, 8].

The fuel. Molten Salt Reactors is a comprehensive reference on the status of molten salt reactor (MSR) research and thorium fuel utilization. There is growing awareness that nuclear energy is needed to complement intermittent energy sources and to avoid pollution from fossil fuels.


Engel. The history of the molten salt reactor dates back to the s. The design was first proposed as the propulsion system of a nuclear-powered aircraft at the Oak Ridge National Laboratory (MacPherson, ).After the program finished, the emphasis was put on the research of MSR running on the thorium fuel by: processing irradiated nuclear fuel.

The first separation techniques were developed in the s and were applied to the separation of plutonium for military purposes. Later, reprocessing of civilian irradiated nuclear fuel was introduced as a means of extending uranium resources, considered to be limited at the time.

Molten salt reactors – nuclear power reactors that use liquid salt as primary coolant or a molten salt mixture as fuel – have many favourable characteristics for nuclear safety and sustainability. The concept was developed in the s, but put aside in favour of what has become mainstream nuclear technology since.

The solubility of Th, U, Ce, La, and Pr in melted salt 45LiF–12NaF–43KF, which supports a fast neutron spectrum for the molten-salt reactor, is found experimentally to be high in the interval –°C. On the basis of an analysis of the physicochemical and nuclear-physical properties of different fluoride salts, it is proposed that the eutectic LiF–NaF–42KF be Cited by: A molten salt reactor (MSR) is a class of nuclear fission reactor in which the primary nuclear reactor coolant and/or the fuel is a molten salt mixture.

MSRs offer multiple advantages over conventional nuclear power plants, although for historical. The potential for burning of Reactor Grade Plutonium in Molten Salt Breeder Reactors is clear in ORNL-TM, "Molten-salt reactors for efficient nuclear fuel utilization without plutonium separation." This was not the only ORNL paper suggesting the MSBR option that Till chose to : Charles Barton.

Liquid Fueled Reactors: Molten Salt Reactor Technologyfor the U.S.

Download Molten-salt reactors for efficient nuclear fuel utilization without plutonium separation PDF

Department of Energy Motivations for Liquid Fuels •Liquid fuels seem novel today, but as will be described in the following slides, they were not seen as being unusual in the early days of nuclear energy •Liquid fuel uniquely allows:File Size: 1MB.

An efficient burning of the plutonium produced during light water reactor (LWR) operation has the potential to significantly improve the sustainability indices of LWR operations. The work offers a comparison of the efficiency of Pu burning in different reactor configurations—a molten salt fast reactor, a LWR with mixed oxide (MOX) fuel, and a sodium cooled fast by: 7.

What if we could design and build a reactor: that uses no water and so can't have high pressure steam or hydrogen explosions, - that fissions over 99% of its fuel so there's no waste to store for hundreds of thousands of years, - with fuel that can't have a nuclear melt down, can never get hot enough to melt the reactor vessel?/5(16).

Liquid fluoride thorium reactor. The liquid fluoride thorium reactor (acronym LFTR; often pronounced lifter) is a type of molten salt reactor.

LFTRs use the thorium fuel cycle with a fluoride-based, molten, liquid salt for fuel. Initially developed in the s, molten salt reactors have benefits in higher efficiencies and lower waste generation. Some designs do not require solid fuel, which eliminates the need for manufacturing and disposing of it.

In recent years, growing interest in this technology has led to renewed development activities.

Details Molten-salt reactors for efficient nuclear fuel utilization without plutonium separation EPUB

Introduction. In the today’s view molten salt reactors have a long history, based on a, somewhat curious idea of the early phase of nuclear development in the late 40s and early 50s.

>>The idea of using molten fluoride salts and thus liquid nuclear fuel in a reactor is rather by: 8. • A fuel salt is a molten salt that contains fissile material – C. Baes, Jr., “The Chemistry and Thermodynamics of Molten Salt Reactor Fuels,” Journal of Nuclear Materials, 51 () – W.

Grimes, “Molten Salt Reactor Chemistry,” Nuclear Applications and Technology, 8(2) () – This disclosure describes nuclear fuel salts usable in certain molten salt reactor designs and related systems and methods. Binary, ternary and quaternary chloride fuel salts of uranium, as well as other fissionable elements, are described.

In addition, fuel salts of UCl x F y are disclosed as well as bromide fuel salts. This disclosure also presents methods and systems for Cited by: 7. Transuranic elements, in particular plutonium, can be recycled from the liquid fuel without the problems and costs of reprocessing solid fuels, making the nuclear.

The Molten-Salt Reactor Experiment (MSRE) was an experimental molten salt reactor at the Oak Ridge National Laboratory (ORNL) researching this technology through the s; constructed byit went critical in and was operated until The MSRE was a MW th test reactor simulating the neutronic "kernel" of a type of inherently safer epithermal thorium breeder reactor.

Thorium: a safer nuclear power In the same month as the Three Mile Island and Fukushima nuclear disasters, China announces it is speeding up its research into so-called molten salt reactors that.USA USA USA US A US A US A US A US A US A US A US A US A Authority US United States Prior art keywords protactinium salt molten metal steel wool Prior art date Legal status (The legal status is an assumption and is not a legal by: 5.