• 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:
    Reactor component adapted for use in fission reactors comprising a core (2) consisting of a first material and a layer (3) consisting of a second material. The layer (3) at least partially encloses the core (2). The reactor component is characterized in that the component (1) comprises an intermediate layer (4) of the metal core (2) and the layer (3). 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). (Fig. 1)
    公开号:SE1050188A1
    申请号:SE1050188
    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:

    other impact. Various forms of material-degrading processes, such as material-degrading abrasion, fretting and erosion corrosion, can also occur on the reactor components. Abrasion can occur, for example, by contact between adjacent components or by contact between the reactor component and a material stream from the external environment, such as the flow of the coolant through the reactor. In the latter case, material can be felled from the reactor component as the medium of the external environment collides with the reactor component at high speed and cuts material from the surface of the component. When one or more reactor components have been affected by abrasion, corrosion or other influences, it may be necessary to stop the reactor to replace the faulty reactor components. A shutdown entails large costs in the form of non-production and costs for repair or replacement of the faulty reactor components.
    Due to their action in the reactor, the reactor components may have been activated and become radioactive. The external environment in the reactor around the reactor components can be contaminated by the reactor components and the external environment reacting with each other or through various forms of material removal processes. Contamination of the external environment with materials from the reactor components means a spread of radioactive substances in the reactor. Removal of raw materials from reactor components can also cause pieces of the reactor components to be worn away. These pieces can flow around in the cooling system and wear on other reactor components, for example the casing pipes in a fuel element, which can lead to the function of the reactor components deteriorating or ceasing completely. In the example of wear on the casing pipes in a fuel element, this can lead to so-called fuel damage, where fissile material comes into contact with the external environment and contaminates the external environment. Contamination of the external environment means that maintenance personnel at the reactor are exposed to increased radiation doses during service work. It may also be required that the reactor be stopped and that the faulty reactor component be replaced.
    The thickness of the reactor components is dimensioned with safety margins against the occurrence of different degrees of impact from, for example, corrosion and abrasion. It is desirable to reduce the wall thickness of the reactor components through various types of improvements. One reason for reducing the material thickness of the components is that spent reactor components due to their radioactivity need to be specially treated or stored until their radioactivity has decreased to certain values. This type of treatment or storage is expensive, so a reduction in the amount of material of the reactor components is desirable. The function of some reactor components is improved as their wall thickness is reduced. An example of a reactor component whose function is improved by a reduced wall thickness is so-called diffusers, which have the task of separating fuel rods in a fuel element and creating turbulence in the flow of the coolant for transferring heat from the fuel rods to the cooling medium. By reducing the material thickness of the injectors, the pressure drop produced by the injectors in the fuel element is reduced. Thereby, for example, the number of injectors in a fuel element can be increased with an improved heat transfer capacity to the coolant, while the total pressure drop in the fuel element is maintained.
    A technique for treating spent nuclear fuel for further storage is described in EP-1249844. The document deals with spent nuclear fuel with aluminum and boron powders which are pressed by Cold lsostatic Pressing (CIP) and then sintered together by means of plasma sintering.
    WO 97150091 discloses a diffuser of a ceramic material for a fuel element. The ceramic diffuser is made by a traditional sintering process. A problem with the use of ceramic materials as construction materials is to ensure the mechanical properties of the material, such as strength, fatigue resistance and so on. In the traditional manufacture of ceramic components, introduce different types of defects in the material, which have a negative impact on the mechanical properties. The document does not show any material gradient between two different materials.
    WO 94/14164 discloses an abrasion resistant coating on a fuel element and a control rod. The coating comprises a ceramic material mixed in a glass matrix, where the glass matrix forms the bond to the underlying metallic material. The coating is applied to the metallic material by a spray method. The document does not show any material gradient between two different materials.
    SUMMARY OF THE INVENTION The object of the present invention is to provide a reactor component with improved properties.
    This object is achieved with the component stated in the introduction which comprises the features stated in the characterizing part of claim 1.
    The reactor component achieves the above-mentioned object by means of the intermediate layer between the core and the layer.
    Reactor component refers to a component that is adapted for use in fission reactors. The reactor component comprises a core and a layer which at least partially encloses the core.
    The core of the component consists of the first material and the layer of the component consists of the second material.
    The intermediate layer is a layer between the core and the layer which 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 second materials. 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 noil. The material gradient means a change in concentration compared with the core and in comparison with the s-layer.
    The material gradient may comprise a homogeneous mixture of the first and second materials. The material gradient may also include a change in the intermediate layer of the relationship 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 reactor 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 material gradient 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.
    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 provide a gradual transition of the properties from the first material to the second material, and vice versa.
    According to an embodiment of the invention, the reactor component is produced by sintering, which gives the component a good co-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 ensures that a number of material properties, such as grain size and porosity, of the sintered component can be controlled within a wide range. The sintering process may comprise the steps of: 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, and sintering the first and the second material to the neutron-absorbing component, so that the intermediate layer between the core and the layer is formed. When the first material and the second material are supplied, an intermediate zone is bit between an inner part of the space and an outer part of the space. The intermediate zone comprises a decrease in 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. Furthermore, the space can be expanded in such a way that the first material and the second material are brought together and form the intermediate zone. The first material added may be in powder form. The other material that is added can also be in powder form.
    Furthermore, the space can be divided by an inner partition member comprising the inner part and by an outer partition member comprising the outer part, an intermediate part being formed between the outer partition member and the inner partition member. The separating means may, for example, be designed as pipes depending on the shape of the component to be manufactured. The intermediate part is supplied with a mixture of the first material and the second material for creating the intermediate zone. The intermediate part can also be divided into compartments of at least one metal member, the compartments being supplied with mixtures of different ratios between the concentration of the first material and the second material.
    According to an embodiment of the invention, the layer is arranged to protect the core, for example from an external environment. This protects the core of the reactor component from interaction, such as various types of corrosion and abrasion. Interactions may involve a reaction between the reactor component and an external environment, such as corrosion of the reactor component or material felling on the reactor component. Interaction may also include abrasion between adjacent reactor components. The layer's protection of the reactor component's core ensures the functionality of the reactor component, thereby increasing the operational reliability of the reactor component. In the same way, the layer protects surrounding components from being affected by the reactor component, such as the effect of shadow corrosion. Thereby, downtime of the reactor due to faulty reactor components can be avoided. By protecting the core of the reactor component from the layer, pieces of the reactor components are also avoided. worn away from the reactor component. These pieces can cause damage to other reactor components, for example in the form of fuel damage to fuel elements. The protection of the reactor component by the layer also prevents material felling of materials containing radioactive substances from the reactor component. Thereby, a spread of radioactive substances in the external environment can be avoided. By preventing the external environment from being contaminated, maintenance personnel's exposure to radiation doses during service work at the reactor is reduced. The protection of the layer can also be used to reduce the wall thickness of the reactor component. As a result, the costs of waste treatment of spent reactor components can be reduced. For some reactor components, for example injectors in fuel elements, a reduction in the material thickness of the reactor component provides improved performance. This improved performance can, for example, be used to increase the efficiency of the reactor's production.
    The external environment consists of the environment around the reactor component, which mainly comprises a moderating and a cooling medium. During reactor operation, the external environment constitutes a reactive environment which, on contact, can react with the reactor component.
    According to one embodiment of the invention, the layer 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 reactor component from being affected by the external environment. This ensures the integrity and function of the reactor component.
    According to an embodiment of the invention, the layer is arranged to at least partially electrically insulate the core from an external environment. By electrical insulation is meant that the layer opposes the conduction of an electric current. Because the layer at least partially electrically insulates the core, different types of corrosion impact, such as shadow corrosion, on reactor components or corrosion impact between different reactor components are prevented. According to an embodiment of the invention, the layer has a higher abrasion resistance than the core of the reactor component. Thereby. The layer protects the core of the reactor component from various forms of abrasion, such as mechanical abrasion between adjacent reactor components, erosion corrosion, and so on. This ensures the integrity and function of the reactor component.
    According to an embodiment of the invention, the layer of the reactor 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, some have. ceramic materials, such as SiC, 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.
    According to an embodiment of the invention, the layer of the reactor component consists of at least one substance selected from the group Ti, Zr, Al, Fe, Cr, Ni, SiC, SiN, ZrO 2, Al 2 O 3, mixtures thereof, and of any balance. Substances from this group have properties that are advantageous for the layer of the reactor component.
    According to an embodiment of the invention, the layer completely encloses the core. Thereby, the core is completely protected and separated from the external environment.
    According to an embodiment of the invention, the reactor component constitutes at least a part of a diffuser for a fuel element.
    This allows the diffuser to be assembled from one or more reactor components in different configurations. The spreader is thus adapted for use in different types of reactors. Through the layer, the spreader is protected from various forms of impact, such as shadow corrosion, abrasion, fretting, erosion corrosion and so on.
    A spreader has the task of separating fuel rods in a fuel element and creating turbulence in the flow of the coolant for transferring heat from the fuel rods to the coolant. The spreader comprises a grid of spreader cells, which are intended to receive fuel rods. The spreader's grid can be built up, for example, by longitudinal and transverse spreader walls, by interconnected sleeves, or by other constructions. The reactor component can, for example, constitute a diffuser wall, which together with a plurality of diffuser walls is mounted to a diffuser. In the same way, the reactor component can constitute a spreader sleeve, which together with a plurality of spreader sleeves is mounted to a spreader. Other designs of reactor components can also be combined so that they individually or together form a diffuser.
    According to an embodiment of the invention, the spreader is designed for use in a light water fission reactor of the boiling water reactor type.
    According to an embodiment of the invention, the reactor component constitutes at least a part of a control rod tip intended to be inserted into or in the vicinity of a fuel element. Through the layer, the tip of the control rod is protected from various forms of impact, such as shadow corrosion, abrasion, fretting, erosion corrosion and so on.
    A control rod has the task of influencing the reactivity of a fission reactor. The control rod can come into contact with or be affected by adjacent components, such as the guide pipes in a fuel element for a pressurized water reactor or the fuel box in a fuel element for a boiling water reactor.
    According to an embodiment of the invention, the control rod tip is designed to be used in a flat water fission reactor of the pressurized water reactor type.
    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 reactor component according to an embodiment of the invention in a side view.
    Figures 2 to 5 show diagrams with different examples of the material concentration of a cross section of reactor components.
    Figure 6a shows a perspective view of an example of the invention in the form of a diffuser for a fuel element.
    Figure Gb shows a cross section of a spreader wall in a spreader.
    Figure Ta shows a perspective view of an example of the invention in the form of a control rod tip to a control rod for a pressurized water reactor. Figure 7b shows a cross section of a control rod tip of a control rod for a pressurized water reactor.
    DETAILED DESCRIPTION OF PREFERRED EMBODIMENTS OF THE INVENTION Figure 1 shows an example of a reactor 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 is a body with a center at 0 and a surface at R, along an x-axis. The component can have any shape determined by its function in the reactor. For example, the shape of component 1 may be 'flat, rectangular, square, spherical, cylindrical, and so on.
    Component 1 is adapted for use in fission reactors and comprises a core 2 consisting of a first material and a layer 3 consisting of a second material. In the example shown in Figure 1, the layer 3 of the component completely encloses the core 2 and protects the core 2 from an external environment through its protective properties, such as corrosion resistance and electrical insulation.
    Component 1 is prepared by sintering by means of a suitable sintering process. 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 sintering is performed in such a way that an intermediate layer 4 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 12 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 reactor 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 as a percentage of the first food material, here marked A and marked with a dashed line, and the second material, here marked 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 reactor component, where the intermediate layer 4 between the core 2 and the layer 3 has a material gradient which comprises a stepwise decrease of the concentration of a first material from the core 2 to the layer 3, and a stepwise increase of the concentration of a second material from the core 2 to the layer 3. in the example in figure 2 a decrease of the concentration of the first material from the core 2 to the intermediate layer 4 takes place in a stepwise manner, where the concentration of the first material decreases from substantially 100% in the core 2 to substantially 50% in the intermediate layer 4. The concentration of the first material is constant within the intermediate layer 4. Furthermore, there is a reduction in the concentration of the first material from the intermediate layer. 4 to the layer 3 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 core 2 to substantially 50%. in the intermediate layer 4. The concentration of the second material is constant within the intermediate layer 4. Furthermore, there is an increase in the concentration of the second material from the intermediate layer 4 to the layer 3 stepwise from substantially 50% to substantially 100%.
    Figure 3 shows, in the same way as Figure 2, an example of a stepwise material concentration variation within a reactor component, with the difference that the intermediate layer 4 comprises two concentration areas, a first concentration area 41 and a second concentration area 42, with different concentrations of the first the material and the other 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 of Figure 3, the concentration of the first material from the core 2 to the intermediate layer 4 on a stepwise manner, where the concentration of the first material decreases from substantially 100% in core 2 to substantially 70% in the first concentration range 41 of the intermediate layer 4. Within the intermediate layer 4, a stepwise decrease 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 gradual reduction in the concentration of the first material from the second concentration range 42 of the intermediate layer 4 to the layer 3, from mainly 30% to mainly 0%. Conversely, there is an increase in the concentration of the second material from the core 2 to the intermediate layer 4.
    Figure 4 shows an example of a material concentration variation within a reactor 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 2 to the layer 3, and a successive increase of concentration the ration of a second material from the core 2 to the layer 3. 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 mainly 100% to mainly 0%. Conversely, there is an increase in the concentration of the second material within the intermediate layer 4, from the core 2 to the layer 3, from substantially 0% to substantially 100%.
    Figure 5 shows an example of a material concentration variation within a reactor 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 2 to the layer 3, and a successive increase of concentration the ration of a second material from the core 2 to the layer 3. In the example in figure 5 a reduction of the first material from the core 2 to the intermediate layer 4 takes place in a successive manner. Within the intermediate layer 4, a gradual decrease in the concentration of the first material takes place, from mainly 100% to 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 6a shows a perspective view of an example of a reactor component in the form of a diffuser 60 for a fuel element. The task of the spreader 60 is to separate fuel rods in a fuel element, not shown in the figure, and create turbulence in the flow of the coolant for transferring heat from the fuel rods to the cooling medium. The spreader 60 includes spreader cells 62 for locating fuel rods. The spreader 60 is constructed of a plurality of spreader walls 64. The grid 60 of the spreader 60 can be built up, for example, by longitudinal and transverse spreader walls 64, by interconnected sleeves, or by other constructions. A spreader wall 64 can individually constitute the reactor component, which together with a plurality of spreader walls 64 is mounted to a spreader 60. In the same way, the reactor component can be constituted by a spreader sleeve, which together with a plurality of spreader sleeves is mounted to a spreader 60. Other embodiments of reactor components can also be combined so that they individually or together form a diffuser 60.
    Figure 6b shows a cross section of a spreader wall 64 in a spreader 60.
    The diffuser wall '64 comprises a core 2 of a metallic material, such as lnconel or Zircaloy, and a layer 3 of a ceramic material, such as zirconia (ZrO2). Between the layer 3 and the core 2 there is an intermediate layer 4, which creates a gradual transition of the material properties from the core 2 to the layer 3.
    The layer 3 has protective properties which allow the good thickness of the diffuser wall to be reduced compared to a diffuser without the layer 3, whereby the pressure drop in the fuel element produced by the diffuser 60 is reduced. Through the layer 3, the spreader 60 is protected against various forms of exposure, such as shadow corrosion, abrasion, fretting and erosion corrosion and so on. The protective effect of the layer 3 also protects surrounding components around the reactor component from various forms of impact, such as shadow corrosion, abrasion, fretting and erosion corrosion and so on.
    Figure 7a shows a perspective view of an example of a reactor component in the form of a control rod tip 74 on a control rod 70 entitled a pressurized water reactor. A plurality of control rods 70 are attached to a control rod element, not shown in the figure, which is adapted to the current fuel design. The task of the control rod 70 is to stop the fission process in a pressurized water reactor. The guide rod comprises guide rod tubes filled with a neutron absorbing material 72, such as boron, hafnium, cadmium and so on. The control rod 70 falls into a guide tube of a fuel element, not shown in the figure, when the reactor is to be shut down.
    Figure 7b shows a cross section of a guide rod tip 74. The guide rod tip 74 comprises a core 2 of a neutron absorbing material and a layer 3 of a ceramic material, such as silicon carbide (SiC). Between the layer 3 and the core 2 there is an intermediate layer 4, which creates a gradual transition of the material properties from the core 2 to the layer 3. The layer 3 has protective properties which ensure that the control rod tip 74 is not damaged in contact with the lead pipe of a fuel element . The protective effect of the layer 3 also protects surrounding components, such as guide pipes, p-positioning device ("guide card") for the control rod, etc., around the reactor component 1 from various forms of impact, such as abrasion, fretting and erosion corrosion and so on.
    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 (14)
    [1]
    Reactor component (1) adapted for use in fission reactors, 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) , characterized in that the reactor 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 reduction of the concentration of the first the material from the core (2) to the layer (3) and an increase in the concentration of the other material from the core (2) to the layer (3).
    [2]
    Reactor component (1) according to claim 1, characterized in that the material gradient comprises a successive decrease of the concentration of the first material from the core (2) to the layer (3) and a successive increase of the concentration of the second material from the core. (2) to the layer (3).
    [3]
    Reactor component (1) according to one of Claims 1 and 2, characterized in that the reactor component (1) is produced by sintering.
    [4]
    Reactor 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.
    [5]
    Reactor component (1) according to one of the preceding claims, characterized in that the layer (3) is arranged to protect the core (2) from an external environment.
    [6]
    Reactor component (1) according to one of the preceding claims, characterized in that the layer (3) is arranged to at least partially electrically insulate the core (1) from an external environment. 10 15 20 25 30 18
    [7]
    Reactor component (1) according to one of the preceding claims, characterized in that the layer (3) has a higher abrasion resistance than the core (2).
    [8]
    Reactor 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.
    [9]
    Reactor 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, ZrOg, A | 2O3, and mixtures thereof, and of any balance.
    [10]
    Reactor component (1) according to one of the preceding claims, characterized in that the layer (3) completely encloses the core (2).
    [11]
    Reactor component (1) according to one of the preceding claims, characterized in that the component (1) forms at least a part of a diffuser (60) for a fuel element.
    [12]
    Reactor component (1) according to Claim 11, characterized in that the diffuser (60) is designed for use in a light water fission reactor of the boiling water reactor type.
    [13]
    Reactor component (1) according to one of the preceding claims, characterized in that the component (1) forms at least a part of a control rod tip (74) intended to be inserted into or in the vicinity of a fuel element.
    [14]
    Reactor component (t) according to claim 13, characterized in that the control rod tip (74) is designed for use in a light water fission reactor of the pressurized water reactor type.
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    同族专利:
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    引用文献:
    公开号 | 申请日 | 公开日 | 申请人 | 专利标题
    GB928517A|1959-01-21|1963-06-12|Parsons C A & Co Ltd|Improvements in and relating to fuel elements for nuclear reactors|
    US3255092A|1961-03-24|1966-06-07|Gen Dynamics Corp|Control rods|
    US3249509A|1964-12-10|1966-05-03|Jr John M Blocher|Nuclear fuel particles coated with mixture of pyrolytic carbon and silicon carbide|
    US3650896A|1969-10-09|1972-03-21|Atomic Energy Commission|Nuclear fuel particles|
    US4267019A|1978-05-10|1981-05-12|General Atomic Company|Nuclear fuel particles|
    SU735101A1|1978-12-15|1981-12-15|Ордена Ленина физико-технический институт им.А.Ф.Иоффе|Thermal neutron crystal monochromator|
    JPS6259789B2|1980-01-07|1987-12-12|Hitachi Ltd|
    JPH0645862B2|1986-12-29|1994-06-15|トヨタ自動車株式会社|Method for forming ceramic sprayed layer|
    JPH0727047B2|1988-03-16|1995-03-29|原子燃料工業株式会社|Control rod for pressurized water reactor|
    JPH01312015A|1988-06-10|1989-12-15|Toshiba Corp|Production of thermal expansion adjusting member|
    US5158653A|1988-09-26|1992-10-27|Lashmore David S|Method for production of predetermined concentration graded alloys|
    US5268235A|1988-09-26|1993-12-07|The United States Of America As Represented By The Secretary Of Commerce|Predetermined concentration graded alloys|
    US5434896A|1990-09-04|1995-07-18|Combustion Engineering, Inc.|Wear resistant coating for components of fuel assemblies and control assemblies, and method of enhancing wear resistance of fuel assembly and control assembly components using wear-resistant coating|
    JPH04177198A|1990-11-13|1992-06-24|Toshiba Corp|Control rod for reactor and its fabrication method|
    JP3080983B2|1990-11-21|2000-08-28|東芝タンガロイ株式会社|Hard sintered alloy having gradient composition structure and method for producing the same|
    JPH04299289A|1991-03-28|1992-10-22|Toshiba Corp|Inclined function material and atomic reactor utilizing this function material|
    JPH04337011A|1991-05-15|1992-11-25|Toshiba Corp|Production of compositionally gradient material|
    US5519748A|1993-04-23|1996-05-21|General Electric Company|Zircaloy tubing having high resistance to crack propagation|
    JP3290000B2|1993-07-07|2002-06-10|科学技術振興事業団|Functionally graded molding material and its sintered product|
    US5793830A|1995-07-03|1998-08-11|General Electric Company|Metal alloy coating for mitigation of stress corrosion cracking of metal components in high-temperature water|
    JPH09131828A|1995-11-09|1997-05-20|Kanegafuchi Chem Ind Co Ltd|Functionally gradient material and manufacture thereof|
    US5711826A|1996-04-12|1998-01-27|Crs Holdings, Inc.|Functionally gradient cladding for nuclear fuel rods|
    SE9602541D0|1996-06-27|1996-06-27|Asea Atom Ab|Fuel cartridge comprising a component for holding elongate elements together|
    JP2002502462A|1997-05-28|2002-01-22|シーメンスアクチエンゲゼルシヤフト|Gradient material of metal and ceramic, product thereof, and method of manufacturing gradient material of metal and ceramic|
    JPH1112758A|1997-06-25|1999-01-19|Asahi Glass Co Ltd|Metallic parts coated with cermet sintered compact, and their production|
    WO1999006605A1|1997-07-31|1999-02-11|Fraunhofer-Gesellschaft zur Förderung der angewandten Forschung e.V.|Process for manufacturing component parts made of composite materials and their use|
    JP3901338B2|1998-04-17|2007-04-04|電気化学工業株式会社|BN-AlN laminate and use thereof|
    SE512804C2|1998-09-11|2000-05-15|Abb Ab|Device and method for preventing shadow corrosion|
    JP2000226898A|1999-02-08|2000-08-15|Kanegafuchi Chem Ind Co Ltd|Buried structure to concrete slab base board|
    JP2001124891A|1999-07-09|2001-05-11|Hitachi Ltd|Surface treatment method for nuclear power plant structure, and nuclear power plant|
    JP3207833B2|1999-10-15|2001-09-10|三菱重工業株式会社|Method for producing spent fuel storage member and mixed powder|
    AT6636U1|2003-04-02|2004-01-26|Plansee Ag|COMPOSITE COMPONENT FOR FUSION REACTOR|
    JP4604153B2|2005-02-18|2010-12-22|国立大学法人東京海洋大学|Forming functional coatings with excellent anticorrosion properties|
    US20060227924A1|2005-04-08|2006-10-12|Westinghouse Electric Company Llc|High heat flux rate nuclear fuel cladding and other nuclear reactor components|
    US7700202B2|2006-02-16|2010-04-20|Alliant Techsystems Inc.|Precursor formulation of a silicon carbide material|
    JP2009210266A|2008-02-29|2009-09-17|Ibiden Co Ltd|Tubular body|
    法律状态:
    优先权:
    申请号 | 申请日 | 专利标题
    SE1050188A|SE536815C2|2010-03-01|2010-03-01|reactor Component|SE1050188A| SE536815C2|2010-03-01|2010-03-01|reactor Component|
    KR1020127022845A| KR20130012113A|2010-03-01|2011-02-23|A reactor component|
    US13/581,938| US20130051513A1|2010-03-01|2011-02-23|Reactor component|
    ES11716087.9T| ES2628581T3|2010-03-01|2011-02-23|Reactor component|
    EP11716087.9A| EP2543043B1|2010-03-01|2011-02-23|A reactor component|
    JP2012556038A| JP2013521493A|2010-03-01|2011-02-23|Reactor component|
    PCT/SE2011/050203| WO2011108974A1|2010-03-01|2011-02-23|A reactor component|
    JP2015035365A| JP2015148617A|2010-03-01|2015-02-25|reactor component|
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