Patent Application
20070263762
This INVENTION relates to nuclear fuel. More particularly, the invention relates to a method of preparing a nuclear fuel, to a nuclear fuel particle and to a nuclear fuel element.
In a nuclear reactor of the high temperature gas-cooled type, use is made of fuel comprising a plurality of generally spherical fuel elements. The fuel elements include a core comprising fuel particles, each having a kernel of fissile material, dispersed in a matrix. The spherical fuel elements are known as pebbles and the nuclear reactor of this type is generally known as a pebble bed reactor.
According to one aspect of the invention, there is provided a method of preparing a nuclear fuel, which method includes the steps of
Preferably, the silicon carbide deposited will be beta polytype silicon carbide. The deposition may be by chemical vapor deposition techniques.
Reducing the silicon carbide may include reacting the silicon carbide with hydrogen chloride or chlorine. Naturally, however, any other suitable reducing agent may be used.
According to another aspect of the invention, there is provided a nuclear fuel element which includes a core comprising a plurality of nuclear fuel particles dispersed in a matrix, each fuel particle having a kernel of fissile material and diamond deposited around the kernel.
The diamond may have a thickness of between about 8 micrometers and about 90 micrometers. More particularly, the diamond may have a thickness of 40 micrometers.
Each fuel particle may have at least one carbon material or compound, selected from the group consisting of porous carbon, pyrolytic carbon, silicon carbide and silicon-nitride-bonded-silicon carbide, deposited around the kernel.
More particularly, each fuel particle may have deposited on its kernel, in sequence, porous carbon, pyrolytic carbon, silicon carbide and/or silicon-nitride-bonded-silicon-carbide, and diamond.
The porous carbon may be deposited to a thickness of between about 10 micrometers and about 90 micrometers, preferably about 95 micrometers. The pyrolytic carbon may be deposited to a thickness of between about 10 micrometers and about 90 micrometers, preferably about 40 micrometers.
The silicon carbide and/or silicon-nitride-bonded-silicon-carbide may have a thickness of about 30 micrometers.
According to still another aspect of the invention, there is provided a nuclear fuel element, which includes
Each fuel particle may have a kernel of fissile material surrounded by a coating including at least one carbon material or compound selected from the group consisting of porous carbon, pyrolytic carbon, silicon carbide, silicon-nitride-bonded-silicon-carbide and diamond.
The fuel particles may be dispersed in a graphite matrix. More particularly, the matrix may comprise graphite powder and phenolic resin.
The nuclear fuel element may be generally spherical in shape. The nuclear fuel element may have a diameter of between about 50 millimeters and about 100 millimeters, preferably between about 55 millimeters and about 60 millimeters.
According to a still further aspect of the invention, there is provided a nuclear fuel particle, which includes a kernel of a fissile material and diamond deposited around the kernel.
The kernel may be provided by a uranium dioxide particle.
The diamond may be deposited to a thickness of between about 8 micrometers and about 90 micrometers. More particularly, the diamond may have a thickness of 40 micrometers.
The fuel particle may have at least one carbon material or compound, selected from the group consisting of porous carbon, pyrolytic carbon, silicon carbide and silicon-nitride-bonded-silicon-carbide, deposited around the kernel.
More particularly, the fuel particle may have deposited on its kernel, in sequence, porous carbon, pyrolytic carbon, silicon carbide and/or silicon-nitride-bonded-silicon-carbide, and diamond.
The porous carbon may be deposited to a thickness of between about 10 micrometers and about 90 micrometers, preferably about 95 micrometers. The pyrolytic carbon may be deposited to a thickness of between about 10 micrometers and about 90 micrometers, preferably about 40 micrometers.
The invention will now be described, by way of example, with reference to the accompanying diagrammatic drawings and the following Examples:
A plurality of nuclear fuel particles was formed by atomisation of uranyl nitrate to form microspheres. The microspheres were then gelled and baked at a high temperature, ie. calcinated, to yield uranium dioxide particles, each to provide a kernel of fissile material for a nuclear fuel particle.
A batch of uranium dioxide particles was suspended in a fluidised bed type deposition chamber of a chemical vapor deposition reactor, the deposition chamber having an argon environment. The deposition chamber was heated to a temperature of about 1000 degrees Celsius.
Porous carbon was deposited on the surface of the uranium dioxide particles to a thickness of 95 micrometers. Next, pyrolytic carbon was deposited on the porous carbon coated surface of the uranium dioxide particles to a thickness of 40 micrometers.
Silicon carbide of about 70 micrometers thickness was deposited on the pyrolytic carbon coated surfaces of the fuel particle kernels. The deposition was carried out a pressure of 1.5 kPa.
The source gases for deposition were then switched to pure argon at a pressure of between 1 kPa and 2 kPa in a manner that ensured minimal disturbance of the floating bed dynamics of the coater volume. The temperature of the circulating argon was decreased to 950 degrees Celsius and argon circulation was maintained for fifteen minutes.
A chlorine (Cl2) source was then connected to an inlet end of the deposition chamber whilst maintaining the temperature of about 950 degrees Celsius. The silicon carbide was reduced to diamond to a depth of about 40 micrometers such that silicon carbide of thickness about 30 millimeters underlies the diamond.
Reference is made to
Discussion
Preferably, a single silicon carbide crystallographic type, viz. beta-type silicon carbide is deposited as the silicon carbide. Where the fraction of alpha-type silicon carbide is greater than 5%, internal stresses arise within the deposited material which reduce the strength thereof.
Treatment of the coated fuel particles in the pure argon environment at 950 degrees Celsius serves to reduce internal, or inter-granular, voids arising from thermal stress attendant upon intensive cooling, as well as to give an optimum temperature for the silicon carbide reduction process.
Instead of adding chlorine gas to the argon stream, hydrogen chloride vapor may be used as a reducing agent.
The reduction of silicon carbide occurs in accordance with the following reaction:
SiC+Cl2→C+SiCl2,
or, where hydrogen chloride is used as reducing agent:
SiC+2HCl→C+SiCl2+H2
At the temperature of about 950 degrees Celsius, the carbon crystallises in an sp2 hybridised face-centred cubic structure, ie. to yield its allotrope of diamond.
The reduction process may be continued until the entire depth of silicon carbide has been reduced, or reduction may be terminated when the desired thickness of diamond is obtained, such that silicon carbide underlies the diamond.
The sizes of diamond crystals in the diamond layer formed range from about 2 nanometers to about 10 nanometers, with more than 70% of crystals falling within the 2 nanometer to 4 nanometer limit.
Long term neutron irradiation is understood to lead to graphitisation of diamond. Diamond crystals larger than 8 nanometers in size are expected to undergo graphitisation after 300 days of irradiation at a flux of 6×1024 neutrons per square centimeter. The resulting mixture of diamond and graphite, in a ratio of approximately 95% to 5%, is expected to show reduced strength properties but has improved adhesion properties over pure diamond and is harder.
The Applicant believes that the method of the invention will yield nuclear fuel particles having improved strength, the outer diamond coating of the fuel particles being able to withstand quasi-dynamically applied contact pressure of the order of 30 GPa without microcracks forming. It is believed that this will facilitate the protection of the fuel particles from damage which can otherwise result from pressing the fuel particles dispersed in a matrix mixture into spherical nuclear fuel elements. Further, it is believed that the resistance of the fuel particles to oxidation will be improved due to the low rate of oxidation of diamond at high temperatures.
The Applicant believes that the method of the invention will yield coated nuclear fuel particles having improved fission product-retention properties.
A plurality of nuclear fuel particles was formed by atomisation of uranyl nitrate to form microspheres. The microspheres were then gelled and baked at a high temperature, ie. calcinated, to yield uranium dioxide particles, each to provide a kernel of fissile material for a nuclear fuel particle.
A batch of uranium dioxide particles was suspended in a deposition chamber of a chemical vapor deposition reactor, the deposition chamber having an argon environment. The deposition chamber was heated to a temperature of about 1000 degrees Celsius.
Carbon material and carbon compounds, selected from the group consisting of porous carbon, pyrolytic carbon, silicon carbide, silicon nitride bonded silicon carbide and diamond, were deposited on the surface of the uranium dioxide particles to yield generally spherical fuel particles of diameter about 1 millimeter.
Some 15 000 of these coated fuel particles were mixed with approximately 200 g of a matrix material comprising 80% by mass graphite powder and 20% by mass phenolic resin. The resulting mixture was pressed into spheres which were machined to a diameter of about 50 millimeters to yield cores for nuclear fuel elements. Each core thus includes a plurality of fuel particles, incorporating a fissile material, dispersed in a matrix and has a mass of about 210 grams.
A batch of such nuclear fuel element cores was suspended in a deposition chamber of a chemical vapor deposition reactor, the deposition chamber having an argon environment. To ensure free stable flotation of the fuel element cores within the coater volume, chemical precursors for deposition were transported through the deposition chamber at a rate of flow in accordance with their temperature and pressure so as to maintain the fuel element cores in a suspended condition.
Silicon carbide was deposited to a thickness of about 0.5 millimeters on the surfaces of the cores. The deposition was carried out a pressure of between 0.01 kPa and 0.7 kPa.
The source gases for deposition were then switched to pure argon at a pressure of between 1.5 kPa and 2 kPa in a manner that ensured minimal disturbance of the floating bed dynamics of the coater volume. The temperature of the circulating argon was decreased to 950 degrees Celsius and argon circulation was maintained for fifteen minutes.
A chlorine (Cl2) source was then connected to an inlet end of the deposition chamber whilst maintaining the temperature of about 950 degrees Celsius. The silicon carbide deposited on the cores was reduced to diamond through the full depth of silicon carbide.
Reference is now made to
Discussion
It is believed that, due to the mechanical wear resistance properties of the diamond protective outer coating, fuel element wear and the attendant production of irradiated dust (as a result of fuel element wear) will be reduced by at least 80%. This will improve the environmental safety of a nuclear reactor employing the fuel elements of the invention as nuclear fuel, eg. in the event of pipe or casing rupture in the nuclear reactor.
The Applicant further believes that the diamond outer coating of the fuel elements of the invention will provide an additional barrier to fission product release which will reduce the diffusion of fission product contaminants into the working fluid, typically helium, of the nuclear reactor.
Simulations show that the number of damaged fuel elements will be reduced one hundred thousand-fold and that the probability of fuel element disintegration or cracking will be reduced one thousand times, in the fuel elements of the invention as a result of the high contact pressure resistance of the diamond protective outer layer.
| Number | Date | Country | Kind |
|---|---|---|---|
| 2004/1665 | Mar 2004 | ZA | national |
| Filing Document | Filing Date | Country | Kind | 371c Date |
|---|---|---|---|---|
| PCT/IB05/50736 | 3/1/2005 | WO | 6/4/2007 |
