• 专利附录
  • 专利说明
  • 权利要求
  • 类似技术
  • 同族专利
  • 引用文献
  • 法律状态
  • 优先权
    • 专利摘要:
    The invention regards a neutron absorbing component (1) and a method for manufacturing a neutron absorbing component. The neutron absorbing component comprises a core (2) consisting of a first material, a layer (3) consisting of a second material. The layer encloses a least partly the core and is adapted to protect the core from an outer surrounding. The first material has a higher neutron absorption capability than the second material. The neutron absorbing component is manufactured by sintering in such a way that an intermediate layer (4) is formed between the core and the layer. The intermediate layer has a material gradient that comprises a decrease of the concentration of the first material from the core to the layer and an increase of the concentration of the second material from core to the layer.
    公开号:SE1050187A1
    申请号:SE1050187
    申请日:2010-03-01
    公开日:2011-09-02
    发明作者:Lars Hallstadius；Karin Backman；Bjoern Rebensdorff；Hans Widegren
    申请人:Westinghouse Electric Sweden；
    IPC主号:
    专利说明:

    to ensure that nuclear materials maintain their subcritical status, for example in the transport of nuclear fuel.
    Neutron-absorbing components are often used in an external environment, such as the reactive environment in a fission reactor. The external environment may include substances that are chemically aggressive at high temperatures and pressures. The external environment around the neutron-absorbing components can, for example, consist of the moderator and cooling medium, which includes light water in pressurized and boiling water reactors. The aggressive substances can react with neutron-absorbing substance in the neutron-absorbing components. As a result, the absorbent function of the components may be impaired. Furthermore, the external environment of the reactor around the neutron absorbing components may be contaminated by the neutron absorbing substance, and / or by gaseous substances formed upon neutron absorption in the neutron absorbing component. Contamination of the external environment can lead to uncertainty and / or imbalance in the reactivity of the reactor. When the neutron-absorbing components are affected, it may be required that the reactor be stopped and that the components be replaced and that the external environment in the reactor be cleaned of the neutron-absorbing substance or gaseous substances formed during neutron absorption. This entails large losses in the form of no energy production at the shutdown and the cost of replacing the neutron-absorbing components.
    When transporting nuclear materials, such as nuclear fuel assemblies, it is of the utmost importance that the material maintains its subcritical status. An example of transport of nuclear materials is transport of nuclear fuel assemblies. Unirradiated nuclear fuel assemblies are transported from nuclear fuel manufacturers to nuclear power reactors in dedicated transport containers, which include neutron-absorbing components. In the event of a potentially unsanitary situation where the containers are exposed to high temperatures, it is important that the function and position of the neutron-absorbing components in the transport containers are maintained.
    A technique for treating spent nuclear fuel for further storage is described in EP-1249844. The document treats spent nuclear fuel with aluminum and boron powders that are pressed by Cold lsostatic Pressing (ClP) and then sintered together using plasma sintering.
    SUMMARY OF THE INVENTION The object of the present invention is to provide a neutron absorbing component with improved properties.
    This object is achieved with the initially stated component which comprises the features stated in the characterizing part of claim 1.
    The neutron absorbing component achieves the above-mentioned object by means of the intermediate layer between the core and the layer.
    The intermediate layer, which can be obtained in connection with the production of the component sintering, is a layer between the core and the layer which gives 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 means a change in concentration in comparison with the core and in comparison with the layer. The material gradient may comprise a homogeneous mixture of the first and the second material. The material gradient may also include a change in the intermediate layer of the ratio between the concentration of the first and the second material. Thereby, the material gradient can be adapted to the material properties, for example with respect to temperature expansion, of the first and the second material in order to achieve good material properties of the component.
    The material gradient creates a transition between the first material in the core and the second material in the layer, which gives a strong adhesion between the layer and the core. The gradient of the material in the intermediate layer means that internal stresses in the component created by thermal and elastic differences between the first and the second material are reduced. This results in improved adhesion of the layer to the core, which gives the component improved functionality.
    The component is prepared by a suitable sintering process which gives the component a good sintering of the first material with the second material. The sintering process may involve or be combined with an applied pressure and / or an elevated temperature. The sintering process must ensure that a variety of material properties, such as grain size and porosity, of the sintered component can be controlled over a wide range.
    The neutron-absorbing component refers to a component that is adapted to influence the reactivity and criticality of nuclear material. The neutron absorbing component has the ability to capture neutrons. When the neutron-absorbing component traps neutrons, it lowers the ratio between existing and formed neutrons, and thereby the reactivity decreases, for example in a fission reactor. The neutron absorbing component can, for example, be used to regulate or shut down the reactivity in fission reactors. Furthermore, the neutron absorbing component can ensure the subcritical status of nuclear material.
    The core of the neutron absorbing component consists of the first material. The first material has a higher neutron absorption capacity than the second material. The neutron absorption capacity of the nucleus mainly arises from the ability of the neutron absorbing component to influence the reactivity in fission reactors. The layer of the neutron-absorbing component is adapted to protect the nucleus from an external environment. The layer consists of the second material, which has properties that are suitable for protecting the core of the component.
    The external environment can be of different types depending on the area of use. For example, in a fission reactor, the external environment consists mainly of a moderating and a cooling medium. In a use to ensure subcritical status, the external environment may, for example, consist of air or concrete. During reactor operation, a reactive environment is formed that affects, among other things, the neutron-absorbing components in the reactor. With the help of the protective effect of the layer, it is ensured that the core of the component is not affected by the external environment, such as the environment in a fission reactor. Because the layer protects the core from the external environment, the influence of the function of the neutron-absorbing component is avoided. The protection of the core also means that the external environment, for example the moderator of an easily selected fission reactor, is not contaminated by the first material or by gaseous substances formed in the core of the neutron-absorbing component. By preventing the external environment from being contaminated, uncertainties in the reactivity of the reactor are avoided. This allows the control and monitoring of the reactor to take place accurately and safely. The layer can also protect the neutron-absorbing component from exposure in the event of an unlikely situation with very high temperatures, for example during transport. Thus, the maintenance of the neutron absorbing function of the component and its position can be ensured.
    By neutron absorption capacity of a material is meant the degree to which the material has the ability to capture neutrons. The neutron absorption capacity of a material varies with the energy spectrum of the neutrons, and at certain neutron energies different materials have so-called resonance peaks in the neutron absorption cross section, where a very high neutron absorption capacity is achieved. By neutron absorption capacity in this context is meant the ability of a material to capture neutrons, above the applicable neutron energy spectrum of a fission reactor, and thereby reduce the reactivity of the reactor. An example of a measure that reflects a material's neutron absorbency in a fission reactor is Equivalent Boron Concentration (EBC), where a value close to one constitutes a material with high neutron absorbency and a value close to zero constitutes a material with low neutron absorbency.
    According to one embodiment of the invention, the neutron absorbing component is adapted for use in fission reactors.
    Thus, the properties of the component given by the core, the layer and the properties of the intermediate layer are designed to be used under the conditions and environments that exist in fission reactors, for example in boiling water and pressurized water reactors.
    According to an embodiment of the invention, the material gradient comprises a successive decrease in the concentration of the first material from the core to the layer and a gradual increase in the concentration of the second material from the core to the layer.
    Thus, the material gradient is designed to give a gradual transition of the properties from f-the first material to the second material, and vice versa.
    According to one embodiment of the invention, the layer of the neutron-absorbing component is substantially impermeable to gaseous substances, at least helium. Because the layer is substantially impermeable, gaseous substances formed upon the capture of neutrons in the first material can be retained in the interior of the neutron absorbing component. As a result, there is no contamination of the external environment with gaseous substances formed in the neutron-absorbing component.
    According to one embodiment of the invention, the layer of the neutron absorbing component is substantially corrosion resistant in an environment of a fission reactor. By substantially corrosion resistant is meant that the layer is chemically inert, or substantially chemically inert, and that its protective effect is thereby retained upon exposure to the external environment of a fission reactor. The corrosion resistance of the layer protects the core of the neutron-absorbing component from being affected by the external environment. This ensures the integrity and function of the neutron absorbing component.
    According to one embodiment of the invention, the pore volume of the porosity in the layer of the neutron absorbing component is considerably smaller than the pore volume of the porosity in the core. The porosity of the core is used to at least partially retain formed gases within the grains of the material structure. Due to the lower porosity of the layer, desirable material properties of the layer are achieved, such as a high density, which gives the layer a separating effect which protects the core from the external environment and prevents gaseous substances formed in the core. from penetrating out of the neutron absorbing component. This ensures the integrity and function of the neutron-absorbing component, as well as reduces the risk of the external environment being contaminated by the first material or by gaseous substances formed in the core. According to one embodiment of the invention, the layer of the neutron absorbing component comprises at least one of a metallic material and a ceramic material. Some materials from these groups have properties that are particularly suitable in reactor environments. For example, certain ceramic materials, such as SiC, have a high corrosion resistance, a high hardness and are heat resistant. For example, certain metallic materials, such as Zr, have a high corrosion resistance and good mechanical properties. SiN, ZrOg, Al2O3, mixtures thereof, and of any balance. Substances from this group have properties that are beneficial to the layer of the neutron absorbing component.
    According to one embodiment of the invention, the core of the neutron absorbing component consists of a substance selected from the group Hf, B, ln, Cd, Hg, Ag, Gd, Er, ßxCy, BXNy, BXOy, mixtures thereof, and of any balance. Substances from this group have properties that are beneficial to the nucleus of the neutron-absorbing component. Within the scope 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 placed in a guide rod, the layer completely enclosing 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 acquires the improved properties of the neutron-absorbing component. Advantageously, the component forms at least part of a control rod intended to influence the reactivity. in a fission reactor. This allows the control rod to be composed of one or more of the neutron-absorbing components in different configurations. The control rod is thus adapted for use in different types of reactors.
    According to a further embodiment of the invention, the control rod is designed to be used in a light water fission reactor of the boiling water reactor type. Advantageously, the guide rod may be composed of at least one leaf-shaped neutron absorbing component.
    According to a further embodiment of the invention, the control rod is designed for use in a light water fission reactor of the pressurized water reactor type. Advantageously, the guide rod may be composed of at least one cylindrical neutron absorbing component.
    An object of the present invention is also to provide a process for producing a neutron absorbing component.
    This object is achieved by the method defined in claim 15.
    Such a method comprises supplying the first material and the second material to a space of a tool in such a way that the second material at least partially encloses the first material, followed by sintering of the first and the second material to the neutron absorbing the 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 intended to be supplied with material for sintering. Possibly. For example, a pressure and / or an elevated temperature can be applied to increase the density during the sintering process.
    According to one embodiment of the invention, the neutron absorbing component is adapted for use in fission reactors.
    According to an embodiment of the invention, the material gradient comprises a successive decrease in the concentration of the first material from the core to the layer and a gradual increase in the concentration of the second material from the core to the layer.
    According to an embodiment of the invention, in the supply of the first material and the second material, an intermediate zone is formed between an inner part of the space and an outer part of the space, and wherein the intermediate zone comprises a reduction of the concentration of the first material from the inner part of the space to the outer part of the space and an increase in the 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 the outer part of the space and consists of the first material and the second material. The intermediate zone comprises a material gradient, which means that the first and the second material gradually or gradually merge into each other. After the materials have been added to the space, the first material is joined to the second material 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 combined and form the intermediate zone. The space is vibrated after the first material and the second material have been added to the space but before sintering. Thus, 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 supplied in powder form. By a material in powder form is meant a material in the solid state comprising a large number! particles with small grain size. The powder may possibly move freely, which means that the powder is densely deformed when it is subjected to mechanical stresses. Thereby, the powder can fill the space in the tool for sintering. By using a material in powder form, the process is facilitated when the intermediate zone is formed.
    According to one embodiment of the invention, the second material is supplied in powder form. According to an embodiment of the invention, the space is divided by an inner tube comprising the inner part, the space being divided by an outer tube comprising the outer part, an intermediate part being formed between the outer tube and the inner tube and wherein the intermediate the part is supplied with a mixture of the first material and the second material for creating the intermediate zone. The inner part is adapted to be supplied - the first material which, after sintering, forms the core of the neutron-absorbing component. The outer part is adapted to be applied to the second material which, after sintering, forms the layer of the neutron-absorbing component. After sintering, the intermediate part forms the intermediate layer of the neutron absorbing component.
    The material in the intermediate part, after sintering, forms the intermediate layer of the neutron absorbing component.
    According to an embodiment of the invention, the intermediate part is divided into compartments of at least one intermediate pipe, the compartments being supplied with mixtures of different ratios between the concentration of the first material and the second material. By dividing the metal-bearing part of the space into two or more compartments, the composition of the first and the second material in the compartments can be influenced so that the intermediate layer formed after sintering has a material gradient which gives the layer good adhesion to the core. .
    BRIEF DESCRIPTION OF THE DRAWINGS The invention will now be explained in more detail by describing various embodiments of the invention and with reference to the accompanying drawings.
    Figure 1 shows a cross section of a neutron absorbing component according to an embodiment of the invention in a side view. Figure 2 to 5 show diagrams with different examples of the material concentration of a cross section of neutron-absorbing components.
    Figure 6 shows a perspective view of an example of a control rod in boiling water reactors.
    Figure 7 shows a perspective view of an example of a control rod in pressurized water reactors.
    Figure 8 shows a cross-section of a tool for supplying material for sintering.
    DETAILED DESCRIPTION OF PREFERRED EMBODIMENTS OF THE INVENTION Figure 1 shows an example of a neutron absorbing component 1, hereinafter referred to as the component, according to an embodiment of the invention in a cross-sectional side view. Component 1 in Figure 1 has a cylindrical shape, with the center of the cylinder base at 0 and the cylinder surface at R, along an x-axis. Other shapes of component 1 are also possible, such as rectangular, square, spherical and so on.
    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 intended to absorb neutrons, for example for the purpose of affecting the reactivity of a fission reactor, such as boiling water reactors and pressurized water reactors. In the example shown in Figure 1, the layer 3 of the component completely encloses the core and protects the core 2 from an external environment. Layer 3 comprises the second material which has protective properties, such as corrosion resistance and resistance to gaseous substances. Component 1 is prepared by sintering in such a way that an intermediate layer 41 is formed between the core 2 and the layer 3. The intermediate layer 4 comprises both the first material and the second material.
    The intermediate layer 4 has a material gradient, which comprises a decrease in the concentration of the first material from the core 2 to the layer 3 and an increase in the concentration of the second material from the core 2 to the layer 3. The intermediate layer 4 forms a transition between the core 2 and the layer 3, so that the material properties of the first material change into the properties of the second material, and vice versa. This creates a good adhesion between the core 2 and the layer 3.
    Figures 2 to 5 show examples of the material concentration of a cross section of a neutron absorbing component. The x-axis of the figures is a dimensional axis, where 0 indicates the center of the component and R indicates the outer periphery of the component. The y-axis of the figures indicates the material concentration of the component in percent for the first material, here with the designation A and marked with a dashed line, and the second material, here with the designation B and marked with a solid line. In the figures, the core 2, the intermediate layer 4 and the layer 3 are marked along the x-axis of the figure.
    Figure 2 shows an example of a material concentration variation within a neutron absorbing component, where the intermediate layer 4 between the core 2 and the layer 3 has a material gradient which comprises a stepwise decrease in the concentration of a first material from the core to the layer, and a stepwise increase in the concentration of a second material from the core to the layer. In the example of Figure 2, the concentration of the first material from the core 2 to the intermediate layer 4 is reduced in a stepwise manner, where the concentration of the first material decreases from substantially 10-0% in the core 2 to substantially 50% in the intermediate layer. layer 4. The concentration of the first material is constant within the intermediate layer 4. Furthermore, the concentration of the first material from the intermediate layer 4 to the layer 3 decreases stepwise from substantially 50% to substantially 0%. Conversely, the concentration of the second material from the core 2 to the intermediate layer 4 increases in a stepwise manner, where the concentration of the second material increases from substantially 0% in the core to substantially 50% in the intermediate layer. The concentration of the second material is constant within the intermediate layer. Furthermore, an increase in the concentration of the second material from the intermediate layer to the layer takes place stepwise from substantially 50% to substantially 100%.
    Figure 3 shows the same. Figure 2 is an example of an s-te-g-wise material concentration variation within a neutron absorbing component, with the difference that the intermediate layer 4 comprises two concentration ranges, a first concentration range 41 and a second concentration range 42, with different concentrations of the first material and the second material. The concentration of the first material and the second material is constant within the first concentration range 41 and the second concentration range 42. In the example in Figure 3, the concentration of the first material from the core 2 to the intermediate layer 4 decreases in a stepwise manner. , where the concentration of the first material decreases from mainly 100% in core 2 to substantially 70% in the first concentration range 41 of the intermediate layer 4. Within the intermediate layer 4 there is a stepwise reduction of the concentration of the first material from the first concentration range 41 to the second concentration range 42, from mainly 70% to mainly 30%. There is a stepwise decrease in the concentration of the first material from the second concentration range 42 of the intermediate layer 4 to the layer 3, from substantially 30% to substantially 0%. Conversely, there is an increase in the concentration of the second material from the core 2 ti !! the intermediate layer 4.
    Figure 4 shows an example of a material concentration variation within a neutron absorbing component, where the intermediate layer 4 between the core 2 and the layer 3 has a material gradient which comprises a successive decrease of the concentration of a 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.
    Within the intermediate layer 4, from the core 2 to the layer 3, there is a constant proportional decrease in the concentration of the first material, from substantially 100% to substantially 0%. Conversely, there is an increase in the concentration of the second material within the intermediate layer, from the core 2 to that layer 3, from substantially 0% to substantially 100%.
    Figure 5 shows an example of a material concentration variant within a neutron absorbing component, where the intermediate layer 4 with the core 2 and the layer 3 has a material gradient which comprises a successive decrease of the concentration of a first material from the core 2 to the layer 3, and a successive increase. - increasing the concentration of a second material from the core 2 to the s-layer 3. In the example in figure 5, the concentration of the first material from the core 2 to the intermediate layer 4 decreases in a successive manner. Within the intermediate layer 4, there is a gradual decrease in the concentration of the first material, from mainly 100% tilt mainly 0%. The transition between the core 2 and the layer 3 can, for example, take place in a non-linear manner. Conversely, there is an increase in the concentration of the second material from the core 2. In the example shown, the intermediate layer 4 constitutes the main part of the component, while the core 2 and the layer 3 constitute a smaller part of the component.
    Figure 6 shows an example of a control rod 70 in a perspective view in boiling water reactors. The guide rod 70 may be composed of one or more leaf-shaped neutron-absorbing components 71 with a core 2 which is partially enclosed by a layer 3. In the example shown, the guide rod 70 comprises four leaf-shaped neutron-absorbing components 71. The components 71 are attached to each layer. second and forms the shape of a cross attached to a fastener 72. Controllers in the reactor, not shown in the figure, are attached to fastener 72 to control the degree to which the control rod 70 is inserted into the reactor.
    Figure 7 shows an example of a control rod 80 in a perspective view in pressurized water reactors. The guide rod 80 may be composed of one or more cylindrical neutron absorbing components 81 with a core 2 which is partially enclosed by a layer 3. In the example shown, the guide rod 80 comprises a cylindrical neutron absorbing component 81. The cylindrical component 81 is fixed. was attached to a fastener 82. Glass devices in the reactor, not shown in the figure, are attached to fastener 82 to be able to push the control rod 80 into the reactor.
    Figure 8 shows a cross section of an example of a tool for producing the neutron absorbing component. The tool shown can be used in any suitable sintering process to produce the neutron absorbing component. Examples of suitable sintering methods that can be used for the invention are classical sintering technology, sintering at atmospheric pressure and elevated temperature, Cold lsostatic Pressing, Hot lsostatic Pressing, Spark Plasma Sintering (spark plasma sintering) etc.
    The tool for the method comprises a tool part with a space intended to be supplied 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 tube 98 which creates an inner part 99, in which the first material is supplied which after sintering forms the core 2 of the component 2. The space of the tool is also divided by an outer tube 94 which creates an outer part 93 , in which the second material is supplied which after sintering forms the component layer 3. Between the outer tube 94 and the inner tube 98 an intermediate part 95 is formed, in which a mixture of the first material and the second material can be supplied as after sintering forms the intermediate layer 4 of the component. With such a design of the tool, for example, a component with the material concentration variation in Figure 2 can be produced.
    In the example of Figure 8, the intermediate portion 95 is divided into compartments of an intermediate tube 96. The compartments of the intermediate portion 95 are supplied with mixtures of different ratios between the concentration of the first material and the second material. The blends can be designed in such a way that the layer formed after sintering has a material gradient which comprises a decrease in the concentration of the first material from the core 2 to the layer 3 and an increase in the concentration of the second material from the core 2 to the layer 3 , for example as shown in Figure 3.
    By means of the above-mentioned vibration of the first and the second material, by means of the tool design shown in Fig. 8, the material concentration variation shown in Fig. 4 and Fig. 5 can also be achieved.
    In an embodiment of the invention, the tubes 94, 96, 98 shown in Figure 8 are pulled out of the space of the tool before the material in the space of the tool is sintered together to the neutron absorbing component. Alternatively, the material in the space of the tool before sintering can be further brought together by vibrating the space of the tool.
    In an exemplary embodiment of the invention, the tubes 94, 96, 98 shown in Figure 8 comprise a material which is gasified during the sintering process. Thereby, the tubes 94, 96, 98 can remain in the space nos the tool during the sintering process without affecting the chemical composition of the neutron absorbing component.
    In an exemplary embodiment of the invention, the tubes 94, 96, 98 shown in Figure 8 are positioned so that a distance is formed to the bottom of the space of the tool. Thereby, the second material can be supplied to the space of the tool so that it completely encloses the first material.
    The invention is not limited to the embodiments shown but can be modified and varied within the scope of the appended claims.
    权利要求:
    Claims (21)
    [1]
    A neutron absorbing component (1), comprising a core (2) consisting of a first material and a layer (3) consisting of a second material, the layer (3) at least partially enclosing the core (2) and adapted to protect the core (2) from an external environment, the first material having a higher neutron absorption capacity than the second material, characterized in that the neutron absorbing component (1) comprises an intermediate layer (4) between the core (2) and the layer (3) , and that the intermediate layer (4) has a material gradient which comprises a decrease in the concentration of the first material from the core (2) to the layer (3) and an increase in the concentration of the second material from the core (2) to the layer. (3).
    [2]
    Neutron-absorbing component (1) according to Claim 1, characterized in that the component (1) is adapted for use in fission reactors.
    [3]
    Neutron-absorbing component (1) according to one of Claims 1 and 2, characterized in that the material gradient comprises a gradual decrease in the concentration of the first material from the core (2) to the layer (3) and a gradual increase in the concentration of the second the material from the core (2) to the layer (3) -
    [4]
    Neutron-absorbing component (1) according to one of the preceding claims, characterized in that the layer (3) is substantially impermeable to gaseous substances, at least helium.
    [5]
    Neutron-absorbing component (1) according to one of the preceding claims, characterized in that the layer (3) is substantially corrosion-resistant in an environment of a fission reactor.
    [6]
    Neutron-absorbing component (1) according to one of the preceding claims, characterized in that the layer (3) has a porosity with a total pore volume greater than or equal to zero, and that the core (2) has a porosity with a total pore volume greater than zero, the pore volume of the porosity in the layer (3) being considerably less than the pore volume of the porosity in the core (2).
    [7]
    Neutron-absorbing component (1) according to one of the preceding claims, characterized in that the layer (3) comprises at least one of a metallic material and a ceramic material.
    [8]
    Neutron-absorbing component (1) according to one of the preceding claims, characterized in that the layer (3) consists of at least one substance selected from the group Ti, Zr, Al, Fe, Cr, Ni, SiC, SiN, ZrOZ, Al 2 O 3, and mixtures thereof, and aveventual balance.
    [9]
    Neutron-absorbing component (1) according to one of the preceding claims, characterized in that the core (2) consists of at least one substance selected from the group Hf, B, ln, Cd, Hg, Ag, Gd, Er, BxCy , BXNy, BXOy, and mixtures thereof, and of any balance.
    [10]
    Neutron-absorbing component (1) according to one of the preceding claims, characterized in that the component (1) is intended to be placed in a guide rod, the layer completely enclosing the core.
    [11]
    Neutron-absorbing component (1) according to claim 10, characterized in that the control rod is designed for use in a light water fission reactor of the boiling water reactor type.
    [12]
    Neutron-absorbing component (1) according to Claim 11, characterized in that the guide rod is made up of at least one leaf-shaped neutron-absorbing component. 10 15 20 25 30 35 21
    [13]
    Neutron-absorbing component (1) according to Claim 10, characterized in that the control rod is designed for use in a light water fission reactor of the pressurized water reactor type.
    [14]
    Neutron-absorbing component (1) according to Claim 13, characterized in that the guide rod is composed of at least one cylindrical neutron-absorbing component.
    [15]
    A method of making a neutron absorbing component according to any one of claims 1 to 14, wherein the method comprises the steps of: supplying the first material and the second material to a space with a tool such that the second material the material at least partially encloses the first material, sintering the first and the second material into the neutron absorbing component, so that the intermediate layer between the core and the layer is formed.
    [16]
    A method according to claim 15, wherein upon supply of the first material and the second material, an intermediate zone is formed between an inner part of the space and an outer part of the space, and wherein the intermediate zone comprises a reduction of the concentration of the first material from the inner part of the space to the outer part of the space and an increase in the concentration of the second material from the inner part of the space to the outer part of the space.
    [17]
    A method according to claim 16, wherein the space is vibrated in such a way that the first material and the second material are combined and form the intermediate zone.
    [18]
    A method according to any one of claims 15-17, wherein the first material to be supplied is in powder form.
    [19]
    A method according to any one of claims 15-18, wherein the second material to be supplied is in powder form. 10 15 22
    [20]
    A method according to any one of claims 15-19, wherein the space is divided by an inner tube comprising the inner part, the space is divided by an outer tube comprising the outer part, an intermediate part being formed between the outer tube and the inner tube, and the intermediate portion is supplied with a mixture of the first material and the second material for creating the intermediate zone.
    [21]
    A method according to claim 20, wherein the intermediate part is divided into compartments of at least one intermediate pipe, the compartments being supplied with mixtures of different ratios between the concentration of the first material and the second material.
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    同族专利:
    公开号 | 公开日
    KR20130036179A|2013-04-11|
    EP2543044B1|2018-08-15|
    EP2543044A1|2013-01-09|
    JP5947224B2|2016-07-06|
    US20130051512A1|2013-02-28|
    JP2013521492A|2013-06-10|
    ES2696992T3|2019-01-21|
    SE536814C2|2014-09-16|
    WO2011108973A1|2011-09-09|
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    法律状态:
    优先权:
    申请号 | 申请日 | 专利标题
    SE1050187A|SE536814C2|2010-03-01|2010-03-01|Neutron Absorbing Component and Process for Preparing a Neutron Absorbing Component|SE1050187A| SE536814C2|2010-03-01|2010-03-01|Neutron Absorbing Component and Process for Preparing a Neutron Absorbing Component|
    KR1020127022273A| KR20130036179A|2010-03-01|2011-02-23|A neutron absorbing component and a method for producing of a neutron absorbing component|
    ES11717051T| ES2696992T3|2010-03-01|2011-02-23|A neutron absorbing component and a method for producing a neutron absorbing component|
    US13/581,714| US20130051512A1|2010-03-01|2011-02-23|Neutron absorbing component and a method for producing a neutron absorbing component|
    JP2012556037A| JP5947224B2|2010-03-01|2011-02-23|Neutron absorber and method for the production of neutron absorber|
    EP11717051.4A| EP2543044B1|2010-03-01|2011-02-23|A neutron absorbing component and a method for producing of a neutron absorbing component|
    PCT/SE2011/050202| WO2011108973A1|2010-03-01|2011-02-23|A neutron absorbing component and a method for producing of a neutron absorbing component|
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