Patent Application
20130051512
The present invention relates to a neutron absorbing component, comprising a core consisting of a first material, a layer consisting of a second material, wherein the layer at least partly encloses the core and is adapted to protect the core from an outer surrounding, wherein the first material has a higher neutron absorption capability than the second material.
The present invention also relates to a method for manufacturing of a neutron absorbing component, comprising a core consisting of a first material, a layer consisting of a second material, wherein the layer at least partly encloses the core and is adapted to protect the core from an outer surrounding, wherein the first material has a higher neutron absorption capability than the second material.
In fission reactors different types of neutron absorbing components are used to control the reactivity in the reactor. The components can be used during operation of reactor for adjusting the reactivity, wherein an adjustment of the power of the reactor is obtained. This type of adjustment can for example be found in boiling water reactors. Neutron absorbing components can also be used for terminating the chain reaction that creates the neutrons that maintain a fission process, wherein the criticality of the fission process ceases and the reactor is shut down. Components for this type of termination of the fission process, so called control rods, are for example found in boiling water reactors and pressurized water reactors. Neutron absorbing components can moreover be used for assuring that nuclear materials maintain their non-critical status, for example during transport of nuclear fuel.
Neutron absorbing components are often used in an outer surrounding, such as the reactive environment in a fission reactor. The outer environment can comprise substances that are chemically aggressive at high temperatures and pressures. The outer surrounding around the neutron absorbing components can for example be the moderator and cooling medium, which comprises light water in pressurized and boiling water reactors. The aggressive substances can react with the neutron absorbing substance in the neutron absorbing components. Thereby, the component's absorbing function can deteriorate. Furthermore, the outer surrounding in the reactor around the neutron absorbing components can be contaminated by the neutron absorbing substance, and/or by substances in gaseous state formed during neutron absorption in the neutron absorbing component. The contamination of the outer surrounding can result in uncertainty and/or unbalance in the reactivity of the reactor. In case of influence on the neutron absorbing components, it may be necessary to shut down the reactor and replace the components, and to decontaminate the outer surrounding of the reactor from the neutron absorbing substance or substances in gaseous state formed during neutron absorption. This results in great losses in form of lacking energy production at the operational shut down and cost for replacing the neutron absorbing components.
At transports of nuclear materials, such as nuclear fuel elements, it is of highest importance that material maintains its non-critical status. One example of transports of nuclear materials is transport of nuclear fuel elements. Non-radiated nuclear fuel elements are transported from the nuclear fuel manufacturer to the nuclear fission reactors in for it intended transport containers that comprise neutron absorbing components. In the event of an unlikely situation where the containers are subjected to high temperatures, it is important that the function of neutron absorbing components and their position in the transport containers are maintained.
A technique for treatment of burned out nuclear fuel for further deposition is disclosed in EP-1249844. In the document the burned out nuclear fuel is treated with powder of aluminium and boron that is pressed by Cold Isostatic Pressing (CIP) and then sintered together by means of plasma sintering.
The object of the present invention is to provide a neutron absorbing component with improved properties.
A neutron absorbing component, comprising: a core consisting of a first material and a layer consisting of a second material, wherein the layer at least partly encloses the core and is adapted to protect the core from an outer surrounding, wherein the first material has a higher neutron absorption capability than the second material, wherein the neutron absorbing component comprises an intermediate layer between the core and the layer, and that the intermediate layer has a material gradient that comprises a decrease of the concentration of the first material from the core to the later and an increase of the concentration of the second material from the core to the layer.
The neutron absorbing component achieves the above mentioned object by means of the intermediate layer between the core and the layer. The intermediate layer comprises or consists of a mixture of the first material and the second material.
The intermediate layer, which can be obtained in conjunction with manufacturing of the component by sintering, is a layer between the core and the layer that provides a transition of the properties from the first material to the second material. The intermediate layer comprises a stepwise or gradual transition of the concentration of the first and the second material. The intermediate layer has a material gradient, which means that the concentration of the first material and the second material in the intermediate layer is greater than zero. The material gradient involves a concentration change in comparison with the core and in comparison with the layer. The material gradient can comprise a homogenous mixture of the first and the second material. The material gradient can also comprise a change within the intermediate layer of the proportion between the concentration of the first and the second material. Thereby, the material gradient can be adjusted based on the material properties, for example with regard to temperature expansion, of the first and the second material in order to obtain good material properties of the component. By means of the material gradient, a transition is formed between the first material in the core and the second material in the layer, which provides a strong adhesion between the layer and the core. The material gradient in the intermediate layer results in a reduction of inner stresses in the component formed due to thermal and elastic differences between the first and the second material. Thereby, an improved adhesion of the layer to the core arises which provides an improved functionality to the components.
The component is manufactured by means of a suitable sintering method that provides the component with a high sintering together of the first material with the second material. The sintering method can involve or be combined with an applied pressure and/or an elevated temperature. The sintering method shall assure that a plurality of material properties, such as grain size and porosity, of the sintered component can be controlled within a wide range.
With the neutron absorbing component, a component is intended that is adapted to control the reactivity and criticality of nuclear material. The neutron absorbing component has ability to capture neutrons. When the neutron absorbing component captures neutrons, it reduces the ratio between present and formed neutrons, and thereby the reactivity, for example in a fission reactor is reduced. The neutron absorbing component can for example be used for adjusting or terminating the reactivity in fission reactors. Furthermore, the neutron absorbing component can assure subcritical status of the nuclear material.
The core of the neutron absorbing component consists of the first material. The first material has a higher neutron absorbing capability than the second material. The neutron absorbing component's ability to affect the reactivity in fission reactors is mainly due to the neutron absorbing capability of the core.
The layer of a neutron absorbing component is adapted to protect the core from an outer surrounding. The layer consists of the second material, which has properties that are suitable for protecting the core of the component.
The outer surrounding can be of different types depending on the field of use. For example in a fission reactor, the outer surrounding comprises mainly a moderating and a cooling medium. In a use for assuring of subcritical status the outer surrounding can for example comprise air or concrete. During reactor operation a reactive environment is formed that affects among other things the neutron absorbing components in the reactor. By means of the protecting function of the layer, it is assured that the core of the component is not affected by the outer surrounding, such as the environment in a fission reactor. Since the layer protects the core from the outer surrounding influence of the functionality of a neutron absorbing component is avoided. The protection of the core also results in the outer surrounding, for example the moderator of a light water fission reactor, not being contaminated by the first material or by substances in gaseous state formed in the core of the the neutron absorbing component. By preventing the outer surrounding from being contaminated, uncertainty in the reactivity of the reactor is avoided. Thereby, the control and the surveillance of the reactor can be performed accurately and reliably. The layer can also protect the neutron absorbing component from being affected in the case of an unlikely situation with very high temperatures, for example at during transport. Thereby, the maintenance of the components neutron absorbing function and its position can be assured.
With the neutron absorption capability of a material it is to be understood to which degree the material has capability to capture neutrons. The neutron absorption capability of a material varies with the neutron energy spectrum, and different materials have at different neutron energies so called resonance peaks in the neutron absorption cross-section, where a very high neutron absorption capability is obtained. With neutron absorption capability is to be understood, in this context, the capability of a material to, over a suitable neutron spectrum for a fission reactor, capture neutrons, and thereby reducing the reactivity of the reactor. An example of a measure that reflects a material's neutron absorption capability in a fission reactor is Equivalent Boron Concentration (EBC), where a value close to one comprises a material with high neutron absorption capability and a value close to zero comprises a material with low neutron absorption capability.
According to an embodiment of the invention, the neutron absorbing component is adapted to be used in fission reactors. Thereby, the properties of the component, that are provided by the core, the layer and the intermediate layers, are arranged to be used under the condition and environments that are present in fission reactors, for example in boiling water- and pressure water reactors.
According to an embodiment of the invention, the material gradient comprises a successive decrease of the concentration of the first material from the core to the layer and a successive increase of the concentration of a second material from the core to the layer. Thereby, the material gradient is arranged to provide a gradual transition of a property from the first material to the second material, and vice versa.
According to an embodiment of the invention, the layer of a neutron absorbing component is essentially impermeable to substances in gaseous state, at least helium. Since the layer is essentially impermeable, substances in gaseous state that is formed when capturing neutrons in the first material can be maintained within the interior of the neutron absorbing component. Thereby, no contamination of the outer surrounding with substances in gaseous state formed in the neutron absorbing component occurs.
According to an embodiment of the invention, the layer of a neutron absorbing component is essentially corrosion resistant in an environment of a fission reactor. With essentially corrosion resistant is to be understood that the layer is chemically inert, or essentially chemically inert, and that its protecting effect thereby is maintained when exposed to the outer surrounding in a fission reactor. By the corrosion resistance of the layer, the core of the neutron absorbing component is protected from being affected by the outer surrounding. Thereby, the integrity and function of the neutron absorbing component is assured.
According to an embodiment of the invention, the pore volume of the porosity in the layer of the neutron absorbing component is considerable less than the pore volume of the porosity in the core. The porosity of the core is used for at least partly maintaining formed gases within the grains of the material structure. By means of the lower porosity of the layer, desirable material properties of the layer are achieved, such as a high density, which provides the layer with a separating effect that protects the core from the outer surrounding and prevents substance in gaseous state formed in the core from escaping from the neutron absorbing component. Thereby the integrity and function of the neutron absorbing component are assured, and the risk that the outer surrounding is contaminated by the first material or by substance in gaseous state formed in the core is reduced.
According to an embodiment of the invention, the layer of the neutron absorbing component comprises at least one of a metallic material and a ceramic material. Certain materials from these groups possess properties that are particularly suitable in reactor environment. For example, certain ceramic materials, such as SiC, have a high corrosion resistance, a high hardness and are resistant to heat. For example, certain metallic materials, such as Zr, have a high corrosion resistance and good mechanical properties.
According to an embodiment of the invention, the layer of the neutron absorbing component consists of at least a substance chosen from the group Ti, Zr, Al, Fe, Cr, Ni, SiC, SiN, ZrO2, Al2O3, mixture thereof, and of possible balance. Substances from this group have properties that are preferable for the layer of the neutron absorbing component
According to an embodiment of the invention, the core of the neutron absorbing component consists of a substance chosen from the group Hf, B, In, Cd, Hg, Ag, Gd, Er, BxCy, BxNy, BxOy, mixture thereof, and of possible balance. Substances from this group have properties that are preferable for the core of the neutron absorbing component. Within the framework of the invention, it is possible to combine any of these substances of the core with any of the above mentioned substances of the layer, for example a layer of SiC and a core of BxCy, such as B4C.
According to an embodiment of the invention, the neutron absorbing component is intended to be located in a control rod, wherein the layer completely encloses the core. By filling the control rod with one or more neutron absorbing components, the core of which is completely enclosed and protected by the layer, the control rod is given the improved properties of the neutron absorbing component.
Advantageously, the component constitutes at least a part of a control rod intended for controlling the reactivity in a fission reactor. Thereby, the control rod can be composed of one or more neutron absorbing components in different configurations. The control rod is thereby adapted for use in different types of reactors.
According to a further embodiment of the invention, the control rod is configured to be used in a light water reactor of the type boiling water reactor. Advantageously, the control rod is constructed of at least a sheet formed neutron absorbing component.
According to a further embodiment of the invention, the control rod is configured to be used in a light water reactor of the type pressurized water reactor. Advantageously, the control rod can be constructed of at least a cylinder formed neutron absorbing component.
An object of the present invention is also to provide a method for manufacturing of a neutron absorbing component.
This object is achieved by means of the method of manufacturing of a neutron absorbing component, wherein the method comprises the steps of feeding the first material and the second material to a space of a tool in such a way that the second material at least partly encloses the first material, and sintering together the first material and the second material to the neutron absorbing component, so that the intermediate layer between the core and the layer is formed.
Such a method comprises feeding of the first material and the second material to a space of a tool in such a way that second material at least partly encloses the first material, thereafter sintering together the first and the second material to the neutron absorbing component, wherein the intermediate layer between the core and the layer is formed, and wherein the intermediate layer has a material gradient.
The tool for the method comprises a tool part with a space adapted to be fed with material for sintering. Possibly a pressure and/or an elevated temperature can be applied for increasing the densification during the sintering method.
According to an embodiment of the invention, the neutron absorbing component is adapted to be used in fission reactors.
According to an embodiment of the invention, the material gradient comprises a successive decrease of the concentration of the first material from the core to the layer and a successive increase of the concentration of the second material from the core to the layer.
According to an embodiment of the invention, an intermediate zone is formed between an inner part of the space and an outer part of the space at the feeding of the first material and the second material, and wherein the intermediate zone comprises a decrease of the concentration of the first material from the inner part of the space to the outer part of the space and an increase of a concentration of the second material from the inner part of the space to the outer part of the space. The intermediate zone is located in an intermediate part of the space between the inner part of the space and an outer part of the space, and consists of the first material and the second material. The intermediate zone comprises a material gradient, which results in that the first and the second material being stepwise or gradually transferred into each other. When the materials have been fed to the space the first material and the second material are joined together by sintering in such a way that the layer, the core and the intermediate layer are formed.
According to an embodiment of the invention, the space is vibrated in such a way that the first material and the second material are brought together and form the intermediate zone. The space is vibrated after that the first material and the second material have been fed to the space but before the sintering. Thereby, a material gradient of the first material and the second material arises between the inner part of the space and the outer part of the space.
According to an embodiment of the invention, the first material is fed in powder form. With a material in powder form is to be understood a material in solid state comprising a large number of particles with small particle size. The powder can possible also be free flowing, which means that the powder is easily deformed when it is subjected to mechanical stresses. Thereby, the powder can fill out the space of the tool for the sintering. By using a material in powder form, the method is facilitated when the intermediate zone is formed.
According to an embodiment of the invention, the second material is fed in powder form.
According to an embodiment of the invention, the space is divided by an inner pipe that comprises the inner part, wherein the space is divided by an outer pipe that comprises the outer part, wherein an intermediate part is formed between the outer pipe and the inner pipe and wherein the intermediate part is fed with a mixture of the first material and the second material for creating the intermediate zone. The inner part is adapted to be fed with the first material that after sintering forms of the core of the neutron absorbing component. The outer part is adapted to be fed with the second material that after sintering forms the layer of the neutron absorbing component. The intermediate part forms after sintering the intermediate layer of the neutron absorbing component.
The material in the intermediate part forms after sintering the intermediate layer of the neutron absorbing component.
According to an embodiment of the invention, the intermediate part is divided into divisions of at least an intermediate pipe, wherein the divisions are fed with mixtures of different proportion between the concentration of the first material and the second material. By dividing the intermediate part of the space in two or more divisions, the composition of the first and the second material in the divisions is arranged so that the intermediate layer formed after sintering receives a material gradient that provides a good adhesion of the layer to the core.
The invention will now be explained more closely by a description of different embodiments of the invention and with reference to the appended drawings.
The component 1 comprises a core 2 consisting of a first material and a layer 3 consisting of a second material. The core 2 of the component comprises a neutron absorbing material arranged to absorb neutrons, for example with the purpose of controlling the reactivity in a fission reactor, such as boiling water reactors and pressurized water reactors. The layer 3 of the component encloses, in the example disclosed in
The tool for the method comprises a tool part with a space arranged to be fed with material for sintering. The tool part comprises a surrounding element 91. The surrounding element 91 encloses the above mentioned space. The space of the tool is divided by an inner pipe 98 which creates an inner part 99, in which the first material is fed that after sintering forms the core 2 of the component. The space of the tool is also divided by an outer pipe 94 which forms an outer part 93, in which the second material is fed that after sintering forms the layer 3 of the component. Between the outer pipe 94 and the inner pipe 98 an intermediate part 95 is formed in which a mixture of a first material and the second material can be fed that after sintering forms the intermediate layer 4 of the component. With such an arrangement of the tool, a component with material concentration variation in
In the example in
By means of above mentioned vibration of the first and the second material, the material concentration variation as shown in
In an embodiment of the invention, the disclosed pipes 94, 96, 98 in
In an embodiment of the invention, the disclosed pipes 94, 96, 98 in
In an embodiment of the invention, the disclosed pipes 94, 96, 98 in
The invention is not limited to the disclosed embodiments but can be modified and varied within the scope of the proceeding claims.
| Number | Date | Country | Kind |
|---|---|---|---|
| 1050187-2 | Mar 2010 | SE | national |
| Filing Document | Filing Date | Country | Kind | 371c Date |
|---|---|---|---|---|
| PCT/SE11/50202 | 2/23/2011 | WO | 00 | 11/13/2012 |
