JP2009210285A - Reactor apparatus and its surface modification method - Google Patents

Abstract

<P>PROBLEM TO BE SOLVED: To provide a reactor apparatus and its surface modification method capable of preventing surely beforehand generation of an SCC damage form by improving simultaneously a material factor and a stress factor for SCC generation prevention in a material to be executed. <P>SOLUTION: In this reactor apparatus, a surface modification layer is constituted, wherein a highly corrosion-resistant layer serving simultaneously as a compressive stress layer for compressive stress application is achieved in a high-temperature high-pressure fluid environment, on a material surface part of the material to be executed such as a reactor internal structure or piping. <P>COPYRIGHT: (C)2009,JPO&INPIT

Description

  The present invention relates to a surface modification technique for a construction material constituting a nuclear power plant, and more particularly to a nuclear reactor apparatus and a surface modification method for the construction material subjected to a surface modification process.

  Numerous boiling water reactors (BWRs) and pressurized water reactors (PWRs) are in operation in Japan and overseas as commercial light water reactors that make up nuclear power plants. Exposed to corrosive environment. In particular, the reactor internals are exposed to a corrosive environment in high-temperature and high-pressure water for a long period of time, and damages called stress corrosion cracking (SCC) occur in the welded parts of the reactor internals where tensile stress remains or in parts subjected to machining. Is known to occur.

  As measures for preventing SCC damage, measures are taken to prevent the occurrence of SCC by adopting a metal or alloy material having high SCC resistance, controlling water quality or improving residual stress. In particular, a stress improvement process that suppresses the occurrence of SCC has been developed by plastically deforming the tensile residual stress, which is the main cause of SCC generation, and converting it into compressive stress, and has been put into practical use as a peening technique (Patent Literature). 1).

  In addition, not only in the nuclear field, but also for the purpose of improving the reliability of equipment and parts used in corrosive environments and extending the life, surface modification that forms a surface layer with high corrosion resistance on the surface of the equipment and parts used. Quality technology has been filed (see Patent Document 2).

Furthermore, a technique has been filed in which a surface modification technique by laser peening is applied to slidable parts used in transportation equipment and rotating equipment such as automobiles to improve the hardness or lubricity of the part surface.
US Pat. No. 6,993,948 (B2) Japanese Patent Laid-Open No. 10-30190 JP 2000-34581 A JP 2006-320907 A

  Among nuclear power plants, especially in an aging plant that has been operating for a long time since the start of operation, an example of damage caused by the combination of residual stress, corrosive environment, and material deterioration called stress corrosion cracking (SCC) There are reports. The residual stress factor is mainly a tensile residual stress generated in a welded part of a structure. As an environmental factor, in the case of BWR, dissolved oxygen, various impurities, and in PWR, temperature and hydrogen in a specific concentration range are cited as factors. In addition, it is said that a decrease in chromium concentration in the vicinity of the grain boundary is one factor in terms of material (material deterioration factor).

  Various countermeasure methods have been developed and applied to actual machines for both BWR and PWR as countermeasures against the occurrence of SCC. From the standpoint of suppressing the residual stress factor, the peening process is applied to both BWR and PWR nuclear power plants. In the past, shot peening (SP) has been applied as an SCC countermeasure for the steam generator (SG) of PWR, and its effect has been demonstrated.

  In nuclear power plants, laser peening (LP) and water jet peening (WJP), which are excellent in remote workability, have been put to practical use as techniques for improving residual stress in in-core equipment of BWR and PWR.

  Moreover, from the point of environmental factor suppression, the reduction of the dissolved oxygen concentration by the hydrogen injection in a BWR plant and the noble metal injection technique in a PWR plant are applied, and the effect is being demonstrated.

  Furthermore, as a material improvement of metal and alloy materials, the application of nickel-base weld metal with higher chromium compared to conventional materials, or the development of high-chromium nickel-base alloys and application to PWR replacement equipment, etc. ing.

  However, the conventional SCC occurrence prevention measures improve only one of the SCC occurrence prevention factors in any of the construction methods. Depending on the nuclear reactor equipment, there is a concern that the occurrence of SCC is induced by the influence of a machining layer inevitably formed by the manufacturing history, heat during operation, external load history, and the like.

  Therefore, if a surface modification process is developed that can improve the SCC generation prevention measures at the same time at a low cost, more reliable SCC generation prevention measures will be possible, leading to an increase in the reliability of the nuclear reactor equipment. It can contribute to the realization of a nuclear power plant that is safer, more reliable and more reliable.

  The present invention has been made in consideration of the above-mentioned circumstances. The material factor and the stress factor are improved at the same time in the work material to prevent the occurrence of SCC, and the occurrence of the SCC damage form is surely prevented. An object of the present invention is to provide a highly reliable nuclear reactor equipment and a surface modification method thereof.

  Another object of the present invention is not only a commercial reactor of a light water reactor, but also a reactor that can be applied to preventive maintenance of an aging plant with the construction material of all reactor equipment of a fast breeder reactor (FBR) as a target equipment. It is in providing an apparatus and its surface modification method.

  Another object of the present invention is to apply to the surface modification technology of welded parts of equipment and equipment welded parts at the time of plant construction to improve the reliability of the whole equipment and to add expensive improvement materials to the construction materials. An object of the present invention is to provide a nuclear reactor device and a surface modification method thereof that can reduce the manufacturing cost without using it.

  In order to solve the above-described problems, the nuclear reactor apparatus according to the present invention has a high corrosion resistance layer that also serves as a compressive stress layer for applying compressive stress to a material surface portion of a construction material such as a reactor internal structure and piping. This is a surface modification layer realized in a high-temperature and high-pressure fluid environment.

  In addition, the method for modifying the surface of a nuclear reactor device according to the present invention includes a high corrosion resistance layer that also serves as a compressive stress layer imparted with a compressive stress on a material surface of a work material such as a nuclear reactor device in a high temperature and high pressure water environment. This is a method of forming a surface modified layer to be realized.

  Here, the reactor equipment includes not only BWR and PWR as commercial light water reactors but also FBR reactor equipment in general. The work material is not only the reactor equipment but also the members that are exposed to the high-temperature and high-pressure fluid (water, steam) of the reactor internal structure, the furnace equipment, piping and parts, or the member that passes the high-temperature and high-pressure fluid.

  In the nuclear reactor equipment and the surface modification method thereof according to the present invention, a surface modification layer that simultaneously improves the material factor and the stress factor constituting the SCC generation is formed on the work material, and the occurrence of the SCC damage form is obviated. It can be reliably prevented and the reliability of the reactor equipment can be improved.

  Embodiments of a nuclear reactor apparatus and a surface modification method thereof according to the present invention will be described with reference to the accompanying drawings.

[First Embodiment]
FIG. 1 shows a first embodiment of a nuclear reactor apparatus and a surface modification method thereof according to the present invention. Reactor equipment 10 shown in this figure is applied to nuclear power plants (reactor-related facilities) of BWR and PWR, and in BWR, an internal structure exposed to high-temperature high-pressure fluid (water, steam), Used in various equipment such as main steam pipes, condensate / feed water pipes, and peripheral equipment for guiding in-furnace equipment and high-temperature / high-pressure fluid, and in PWR, internal structures, in-furnace equipment, Applicable to pressurizers, steam generators, peripheral equipment and various pipes that generate high-pressure water.

  The work-related material (structure material) 11 of the reactor-related facility that constitutes the reactor internal structure, the main steam pipe, and the like is exposed to a corrosive environment of high-temperature and high-pressure fluid (water, steam) for a long time. In the work material 11, a surface modification layer is formed on the surface layer portion 12 exposed to the high-temperature and high-pressure fluid. The work material 11 is obtained as a surface modified layer in which the surface layer portion 12 is improved from the base material 13 in terms of material factors and stress factors. Divided into layers.

  FIG. 1 is a schematic view showing the residual stress distribution and the chromium (Cr) concentration distribution of the surface modification layer formed in the vicinity of the surface of the workpiece 11 in a cross-sectional structure display. This nuclear reactor apparatus 10 applies a surface modification process to the workpiece 11 exposed to the high-temperature and high-pressure fluid, and the surface layer portion 12 near the surface of the workpiece 11 has a chromium concentration α of the base material 13, for example, 18 wt%. A high-concentration chromium layer having a high concentration is formed, and at the same time, an effective compressive stress is applied to prevent stress corrosion cracking. The work material 11 to which the compressive stress is applied may be provided with high corrosion resistance in a high-temperature and high-pressure fluid environment to form a high corrosion-resistant layer on the surface layer portion 12.

  In the nuclear reactor apparatus 10 shown in FIG. 1, a surface modification layer is formed on the surface layer portion 12 of the workpiece 11, and this surface modification layer is a high-concentration chromium layer having a higher concentration than the chromium concentration α of the base material 13. The content has a compressive stress layer that also serves as a (high corrosion resistance layer).

  Compressive stress obtained by applying a surface modification process to the work material 11 of the nuclear reactor 10 and applying a high corrosion resistance layer made of high-concentration chromium and compressive stress to the surface layer portion 12 in a high-temperature and high-pressure fluid environment. Both layers are provided in common. For example, when the work material 11 is an in-furnace structure made of SUS304, the surface modification process is applied to the surface of the work material 11 in a highly corrosive environment exposed to high temperature and high pressure water. In comparison, it is possible to realize a highly reliable in-furnace structure having excellent stress corrosion cracking (SCC) resistance.

  Moreover, the work material 11 of the nuclear reactor equipment 10 controls the thickness of the compressive stress layer formed on the surface layer portion 12 of the work material 11 and the chromium concentration of the surface layer portion 12 by controlling the work conditions. Can do. High corrosion resistance can be ensured by forming the surface layer portion 12 containing a chromium concentration of the base material 13 of the work material 11, for example, a chromium concentration of 20 wt% or more, which is larger than 18 wt%. When the work material 11 is an in-furnace structure, high corrosion resistance can be ensured and reliability can be improved. The chromium concentration is preferably 26 wt% or less from the viewpoint of safety of the austenite layer of SUS steel.

  Further, the high chromium concentration layer formed on the surface layer portion 12 of the work material 11 is the work material when the reactor equipment 10 that is the work material 11 is exposed to a high-temperature high-pressure fluid (water, steam). A dense oxide film having good corrosion resistance is formed on the surface of No. 11, and a significant improvement in SCC resistance can be expected.

  The effect of improving the SCC resistance can also be obtained by incorporating zinc (Zn) in place of chromium (Cr) into the oxide film formed on the surface of the work material 11. The surface layer portion 12 of the work material 11 may be configured with a surface layer portion having a high zinc concentration as a highly corrosion-resistant layer instead of the chromium concentration.

  A surface modification process is applied to the nuclear reactor apparatus 10 shown in FIG. 1, and a surface modification having high corrosion resistance in a high-temperature and high-pressure fluid environment and a compressive stress layer provided with a compressive stress on the material surface of the work material 11. Among the factors constituting the SCC generation factor, a layer is formed, and the surface layer portion 12 of the work material 11 is made to have a function of a plastically deformed compressive stress layer and a highly corrosion-resistant surface modified layer at the same time. The factor and the stress factor can be improved at the same time, and more stable SCC generation prevention measures can be taken.

[Second Embodiment]
FIG. 2 shows a second embodiment of a surface modification method for nuclear reactor equipment.

  In the method for modifying the surface of a nuclear reactor device shown in this embodiment, for example, ultrasonic shot peening is applied to a workpiece 11 made of SUS304 steel to apply a compressive stress near the surface of the workpiece 11. The surface modification was performed. The same components as those of the reactor equipment shown in FIG.

  FIG. 2 is a diagram illustrating the hardness distribution in the depth direction near the surface of the workpiece 11 when ultrasonic shot peening is applied to the surface layer portion 12 of the workpiece 11. Residual stress in the vicinity of the surface of the workpiece 11 is improved by ultrasonic shot peening, and a compressive stress is applied to the surface layer portion 12 to cause plastic deformation, thereby forming a work hardened layer.

  Since the surface layer portion of the work material 11 has a Vickers hardness exceeding 300 Hv, there is a concern about an adverse effect such as accelerating the crack growth rate. The hardness is desirably less than 300 Hv.

  According to this surface modification method for nuclear reactor equipment, by employing ultrasonic peening for the surface modification process, a surface modified layer having a Vickers hardness of 300 Hv or less is formed on the surface layer portion 12 of the workpiece 11. Thus, an excessive increase in hardness can be suppressed in the surface modified layer, and a more reliable in-furnace structure can be provided.

  According to the surface modification method for nuclear reactor equipment, a highly reliable surface modification layer can be formed by performing water jet peening or laser peening instead of ultrasonic shot peening on the compressive stress layer in the surface layer. This surface modification layer may be used in combination with a surface modification process treatment in which the chromium concentration and the zinc concentration are higher in a high temperature and high pressure fluid (water) environment.

[Third Embodiment]
FIG. 3 shows a third embodiment of a surface modification method for nuclear reactor equipment.

  The surface modification method for the reactor apparatus 10A shown in this embodiment is a corrosion resistance that obtains an alloy composition that forms a high corrosion resistance film on the surface of the work part of the work material 11 in advance in a high temperature and high pressure fluid (water, steam). A volatile solution containing the improving element (A) is applied to form the coating layer 15. A shot peening process is performed in which a shot material 16 such as a steel ball is applied to the coating layer 15 formed on the surface of the workpiece 11 to which the volatile solution is applied. The corrosion resistance improving element (A) is made of, for example, chromium (Cr) or zinc (Zn).

  A part of the corrosion resistance improving element (A) constituting the coating layer 15 applied to the surface of the workpiece 11 by performing the surface modification process of the shot peening process on the workpiece 11 in a high-temperature and high-pressure fluid environment. Is driven into the surface layer portion 12 of the work material 11 by shot peening energy, and a layer having a high concentration of the corrosion resistance improving element (A) is formed. At the same time, the surface layer portion 12 of the work material 11 is compressed by plastic deformation. A stress layer is formed.

  When the work material 11 such as an in-furnace structure to which this surface modification process is applied is exposed to a high-temperature and high-pressure fluid during the process, a stable film is formed on the surface of the work material 11 and SCC resistance is generated. The prevention effect can be improved.

  As a peening method for performing the surface modification process on the surface layer portion 12 of the work material 11, in addition to shot peening, laser peening, water jet peening, ultrasonic shot peening, ultrasonic cavitation peening, ultrasonic irradiating members Any construction method such as ultrasonic rotopeening by hitting with a rod or a rod may be used, and it is appropriately selected according to the construction environment and construction area.

  And by forming the coating layer 15 which apply | coated the volatile solution which has a corrosion-resistance improvement element (A) on the surface of the to-be-processed material 11, and performing a peening process by the surface modification process process on this coating layer 15, A surface-modified layer with an improved compressive stress layer that also serves as a high corrosion resistance layer can be formed on the surface layer portion 12 of the work material 11, and the material factor and stress factor of SCC can be improved at the same time. The occurrence of SCC can be prevented more effectively and reliably, and the reliability of the nuclear reactor equipment 10 can be improved.

[Fourth Embodiment]
FIG. 4 shows a fourth embodiment of a surface modification method for nuclear reactor equipment.

  In the surface modification method for the nuclear reactor 10B shown in this embodiment, chromium (Cr), zinc (which obtains an alloy composition that forms a highly corrosion-resistant film in a high-temperature high-pressure fluid (water, steam) on the surface of the work material 11 is obtained. The corrosion resistance improving element (A) such as Zn) or the powder layer 17 containing the element (A) at a high concentration is formed. And the surface modification process is given to the to-be-processed material 11 which formed this powder layer 17 on the surface, and a shot peening process is implemented.

  Part of the powder formed on the surface of the work material 11 is driven into the work part by shot peening energy to form a high-concentration layer in which the concentration of the corrosion resistance improving element is increased. A compressive stress layer is formed by plastic deformation of the surface layer portion 12 by injection.

  A surface modification process is applied to the surface layer portion 12 of the work material 11 to perform shot peening from above the powder layer 17 and expose it to a surface (surface layer portion 12) of the work material 11 by exposing it to a high temperature and high pressure fluid. A highly corrosion-resistant film imparted with a stable compressive stress is formed, and the effect of improving SCC resistance can be improved.

  Also in this case, as a peening method for performing the surface modification process on the surface layer portion 12 of the work material 11, in addition to shot peening, laser peening, water jet peening, ultrasonic shot peening, ultrasonic cavitation peening, ultrasonic Any construction method such as rotopeening may be used, and it is appropriately selected according to the construction environment and construction area.

[Fifth Embodiment]
FIG. 5 illustrates a fifth embodiment of a surface modification method for nuclear reactor equipment.

  In the surface modification method for reactor equipment 10C shown in this embodiment, chromium (Cr) or zinc (Zn) that obtains an alloy composition that forms a high corrosion-resistant film on the surface of the workpiece 11 in advance in a high-temperature and high-pressure fluid environment. Or the like, or a film-like or sheet-like thin film 18 containing the element (A) at a high concentration. A surface modification process is performed from above the sheet-like or film-like thin film 18 provided on the surface of the workpiece 11, and a shot peening process is performed.

  Due to the shot peening treatment mechanism, a part of the corrosion resistance improving element (A) constituting the thin film 18 formed on the surface of the workpiece 11 is driven into the construction portion by the shot peening energy, and the corrosion resistance improving element (A) At the same time as the high temperature layer is formed on the surface layer portion 12, a pressure stress layer that is plastically deformed by applying a compressive stress to the surface layer portion 12 is formed.

  By subjecting the surface of the work material 11 constituting the in-furnace structure to the shot peening process from above the thin film 18 in a state where the work material 11 to which the surface modification process is applied is exposed to the high-temperature and high-pressure fluid, A film to which stable corrosion resistance and compressive stress are applied is formed, and the effect of improving the SCC resistance can be enhanced.

  As a peening method for subjecting the surface of the workpiece 11 to surface modification, any of the construction methods such as laser peening, water jet peening, ultrasonic shot peening, ultrasonic cavitation peening, and ultrasonic rotopeening can be used in addition to shot peening. The required peening method is appropriately selected according to the construction environment and construction area.

[Sixth Embodiment]
FIG. 6 shows a sixth embodiment of a surface modification method for nuclear reactor equipment.

  The surface modification method for nuclear reactor equipment 10D shown in this embodiment is an example of a surface modification method using ultrasonic shot peening. The material of the shot material 20 made of a steel ball used for ultrasonic shot peening is made of chromium (Cr), zinc (Zn), or the like that obtains an alloy composition that forms a highly corrosion-resistant film in high-temperature high-pressure water on the surface of the work material 11. The corrosion resistance improving element (A) or an alloy containing this element (A) at a high concentration is used.

  In this embodiment, the corrosion resistance improving element (A) or an alloy shot material 20 containing this element (A) at a high concentration is prepared, and the surface modification construction device 21 is installed on the surface of the work material 11. The surface modification construction device 21 is configured by attaching an ultrasonic transducer 23 in a processing box 22.

  In the surface treatment method for the nuclear reactor 10D shown in FIG. 6, a surface modification construction device 21 is installed on the surface of the work material 11, and ultrasonic waves are generated in a chamber 24 in the treatment box 22 in a high-temperature high-pressure fluid (water). The vibrator 23 is energized to perform ultrasonic shot peening. By this ultrasonic shot peening, the shot material 20 is transferred to the construction surface (surface) of the work material 11 and driven, and a high-concentration surface layer having the corrosion resistance improving element (A) is formed on the surface of the work material 11. At the same time, a compressive stress layer is formed on the surface layer portion 12 of the workpiece 11.

  In this embodiment, by applying ultrasonic shot peening by the surface modification process of the work material 11, the surface of the work material 11 is rich in corrosion resistance and is subjected to a plastic deformation due to a compressive stress. A quality layer is formed. The surface modification layer formed on the surface layer portion 12 of the workpiece 11 can simultaneously improve the material factor and the stress factor constituting the SCC generation factor. A stable high corrosion resistant layer and compressive stress layer can be simultaneously applied to the surface of the work material 11.

  In this embodiment, even when the work material 11 that has been subjected to the surface modification treatment process is used for the nuclear reactor equipment 10D, even if the work material 11 is exposed to a high-temperature and high-pressure fluid (water), a stable film is formed on the surface. Since it is formed, the effect of improving SCC resistance can be further enhanced. As a peening method, the same effect was obtained by shot peening instead of ultrasonic shot peening.

[Seventh Embodiment]
FIG. 7 shows a seventh embodiment of a surface modification method for nuclear reactor equipment.

  The surface modification method for reactor equipment 10E shown in this embodiment is an example of a surface modification method using ultrasonic shot peening.

  In this embodiment, the surface modification construction device 21 is installed on the surface of the work material 11, the ultrasonic vibrator 23 is attached in the processing box 22 of the construction device 21, and the ultrasonic vibrator 23 is energized. Thus, an ultrasonic shot peening process is performed in a state where the steel ball shot material 16 and the powder 25 are mixed.

  In the ultrasonic shot peening process, the corrosion resistance improving element (A) having an alloy composition for forming a high corrosion resistance film on the surface of the workpiece 11 in the high temperature and high pressure fluid in the ultrasonic shot peening chamber 24 in the processing box 22 or this Ultrasonic shot peening is performed in a state where powder containing the element (A) at a high concentration is mixed.

  During this ultrasonic shot peening construction, the surface improving element (A) constituting the powder moves to the surface of the work material 11 (work surface), and the surface modifying element (A) is formed on the surface of the work material 11. At the same time as the high concentration layer is formed, a compressive stress layer is formed on the surface layer portion 12.

  Even if the work material 11 subjected to this surface modification treatment process is used for the in-reactor structure of the nuclear reactor equipment 10E and exposed to high-temperature high-pressure water, a highly corrosion-resistant layer and a compressive stress layer are formed on the surface of the work material 11 Since the surface modification layer which consists of is formed, the stable membrane | film | coat is formed in the surface layer part 12 of the to-be-processed material 11, and the improvement effect of SCC generation | occurrence | production prevention can be heightened.

[Eighth Embodiment]
FIG. 8 shows an eighth embodiment of a surface modification method for nuclear reactor equipment.

  In the surface modification method for the reactor equipment 10F shown in this embodiment, the construction flow shown in FIG.

  In the surface modification method for the nuclear reactor 10 </ b> F, before the surface modification process is performed, fine uneven forming is performed on the surface of the workpiece 11 in advance by grinder processing, and adheres to the surface of the workpiece 11. It is possible to improve the adhesion probability of the corrosion resistance improving element (A) such as chromium (Cr) or zinc (Zn) or an element containing this element.

  An alloy composition that forms a highly corrosion-resistant film on the surface of the work material 11 in a high-temperature and high-pressure fluid may be obtained, and the corrosion resistance-improving element (A) or an element containing this element (A) is improved in the probability of adhesion and corrosion resistance. A high concentration layer of the improving element (A) can be formed as a surface layer of the work material 11. For this reason, the surface modification layer of the high concentration layer having high corrosion resistance can be formed on the surface of the work material 11.

  By forming a concavo-convex surface on the surface of the workpiece 11 by grinder processing or the like and using this concavo-convex forming means, it is possible to shorten the construction time of the surface modification process.

[Ninth Embodiment]
FIG. 9 shows a ninth embodiment of nuclear reactor equipment.

  The reactor equipment shown in this embodiment shows an example in which a surface modification treatment process of ultrasonic shot peening is performed on the reactor structure welded portion 26 of the work material 11. The reactor structure welded portion 26 is a portion where there is a concern about the occurrence of SCC due to material deterioration due to the welded portion, formation of tensile residual stress, or the like, such as a welded portion of a reactor internal structure or piping.

  In the nuclear reactor apparatus 10G shown in FIG. 9, the surface structure process is performed on the welded portion 26 of the reactor structure (pipe) that constitutes the workpiece 11, so that the reactor structure welded portion 26 and its welded portion 26 A surface modification layer can be formed on a nearby surface layer using the surface modification device 21. The surface modification layer is subjected to a surface modification treatment process in a high-temperature and high-pressure fluid environment by using the surface modification apparatus 21 and the surface modification treatment method according to any one of the third to seventh embodiments. Thus, a surface modification layer of a highly corrosion-resistant layer that also serves as a compressive stress layer can be applied to the reactor structure weld 26 and the surface layer in the vicinity thereof. The surface modification layer may be formed over the entire circumference of the reactor structure weld 26 and the vicinity thereof.

  Also in this reactor equipment 10G, it is possible to take measures to prevent SCC occurrence by simultaneously improving the material factor and the stress factor at the welded portion of the work material 11 and the vicinity thereof, so that the occurrence of the SCC damage form is ensured in advance. Can be prevented.

  In the embodiment of the present invention, an example is shown in which the present invention is applied to BWR and PWR nuclear reactor equipment. However, FBR nuclear reactor equipment can be targeted, and the reactor equipment includes in-core equipment and peripheral equipment. As well as in-furnace structures, piping, parts and the like.

BRIEF DESCRIPTION OF THE DRAWINGS The block diagram which shows 1st Embodiment of the nuclear reactor apparatus which concerns on this invention, and its surface modification method. The 2nd Embodiment of the surface modification method of the nuclear reactor apparatus which concerns on this invention is a figure which shows the cross-sectional hardness distribution measurement example of the to-be-processed material which performed the surface modification process. The block diagram of the surface modification process which shows 3rd Embodiment of the surface modification method of the nuclear reactor apparatus which concerns on this invention. The block diagram of the surface modification process which shows 4th Embodiment of the surface modification method of the nuclear reactor apparatus which concerns on this invention. The block diagram of the surface modification process which shows 5th Embodiment of the surface modification method of the nuclear reactor apparatus which concerns on this invention. The 6th Embodiment of the surface modification method of the nuclear reactor apparatus which concerns on this invention is shown, and the block diagram using the surface modification construction apparatus. The 7th Embodiment of the surface modification method of the nuclear reactor apparatus which concerns on this invention is shown, and the block diagram using the surface modification construction apparatus. The 8th Embodiment of the surface modification method of the nuclear reactor apparatus which concerns on this invention is shown, and the block diagram which shows the flow of a surface modification process. The block diagram which shows 9th Embodiment of the nuclear reactor apparatus which concerns on this invention.

Explanation of symbols

10, 10A, 10B, 10C, 10D, 10E, 10F, 10G Reactor equipment 11 Construction material (component)
12 Surface layer (surface modified layer)
13 Base Material 15 Coating Layer 16 Shot Material 17 Powder Layer 18 Thin Film 21 Surface Modification Equipment 22 Processing Box 23 Ultrasonic Vibrator 24 Ultrasonic Shot Peening Chamber 25 Powder 26 Reactor Structure Welding Portion

Claims (15)

The surface modification layer that realizes a high corrosion resistance layer that also serves as a compressive stress layer for applying compressive stress in a high-temperature and high-pressure fluid environment on the material surface of work materials used in reactor-related facilities. Reactor equipment. The reactor apparatus according to claim 1, wherein the surface modification layer of the work material is a surface layer having a concentration higher than a chromium concentration or a zinc concentration in the base material. The reactor apparatus according to claim 1, wherein the surface modification layer of the work material is a surface layer having a chromium concentration of 20 wt% or more and 26 wt% or less. The reactor apparatus according to claim 1, wherein the surface modified layer of the work material has a Vickers hardness of 300 Hv or less. The reactor apparatus according to claim 1, wherein the work material has a surface modification layer formed on a welded portion thereof and a surface layer near the welded portion. It is characterized by forming a surface modification layer that realizes a high corrosion resistance layer that also serves as a compressive stress layer to which compressive stress is applied in a high-temperature and high-pressure water environment on the material surface of work materials used in nuclear reactor-related facilities. Reactor equipment surface modification method. The surface modification method for nuclear reactor equipment according to claim 6, wherein the work material is formed with a surface layer having a concentration higher than a chromium concentration or a zinc concentration in a base material as a surface modification layer. The surface modification method for a nuclear reactor apparatus according to claim 6, wherein the work material is formed with a surface layer having a chromium concentration of 20 wt% or more and 26 wt% or less as a surface modification layer. The surface modification method for nuclear reactor equipment according to claim 6, wherein the work material is formed with a surface layer having a Vickers hardness of 300 Hv or less as a surface modification layer. The reactor apparatus according to claim 6, wherein the work material is subjected to a peening treatment in a state where a corrosion resistance improving element that imparts high corrosion resistance in high-temperature and high-pressure water is present on the surface or surface layer of the work part to form a surface modified layer. Surface modification method. The surface modification of nuclear reactor equipment according to claim 10, wherein the means for applying compressive stress to the surface or surface layer of the workpiece is shot peening, laser peening, water jet peening, ultrasonic shot peening or ultrasonic rotopeening. Method. The atom according to claim 10, wherein a solution or a powder containing a corrosion resistance improving element that imparts high corrosion resistance in a high-temperature and high-pressure fluid is applied to the surface of the workpiece before peening the surface or surface layer of the workpiece. Surface modification method for furnace equipment. The reactor apparatus according to claim 10, wherein a thin film containing a corrosion resistance improving element that imparts high corrosion resistance in a high-temperature and high-pressure fluid is formed on a surface of a work part before peening the surface or surface layer of the work material. Surface modification method. The means for imparting compressive stress to the surface or surface layer of the work material is ultrasonic shot peening or shot peening, and the shot material used for the peening treatment is an element for improving corrosion resistance that imparts high corrosion resistance in a high-temperature and high-pressure fluid. The method for modifying the surface of a nuclear reactor device according to claim 6, wherein the surface modification method is an alloy containing a corrosion resistance improving element or a composite material having a corrosion resistance improving element as a constituent element. The means for imparting compressive stress to the surface or surface layer of the workpiece is ultrasonic shot peening, and the ultrasonic shot peening chamber is mixed with a powder containing a corrosion resistance improving element that imparts high corrosion resistance in high-temperature high-pressure water. The method for modifying the surface of a nuclear reactor device according to claim 6, wherein the ultrasonic shot peening is performed in a state of being caused to occur.

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