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JP2008039579A - Supercritical light water reactor, treatment method thereof and oxidation treatment apparatus - Google Patents

Supercritical light water reactor, treatment method thereof and oxidation treatment apparatus Download PDF

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JP2008039579A
JP2008039579A JP2006214132A JP2006214132A JP2008039579A JP 2008039579 A JP2008039579 A JP 2008039579A JP 2006214132 A JP2006214132 A JP 2006214132A JP 2006214132 A JP2006214132 A JP 2006214132A JP 2008039579 A JP2008039579 A JP 2008039579A
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oxidation treatment
oxidation
water reactor
light water
water
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Seiji Yamamoto
誠二 山本
Nagayoshi Ichikawa
長佳 市川
Tetsuo Osato
哲夫 大里
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Toshiba Corp
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    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

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Abstract

<P>PROBLEM TO BE SOLVED: To control corrosion of metallic materials in a super-critical pressure light water reactor using a direct cycle, reduce transfer of radioactive corrosion products to a turbine system and reduce the dose of the turbine system. <P>SOLUTION: Oxidation treatment using high-temperature water or high-temperature steam is applied on at least part of the surface of a solid metallic material in contact with a coolant in the super-critical pressure light water reactor. The surface of the solid metallic material as an object of oxidation treatment may be mechanically polished or electrolytically polished before the oxidation treatment. Preferably, high-temperature water containing at least one of Ni, Zn, Fe, Cr, Mn, Cu, Pd, Pt, Al, Mo, V and W is used for the oxidation treatment. <P>COPYRIGHT: (C)2008,JPO&INPIT

Description

本発明は、直接サイクルを用いた超臨界圧軽水炉および、超臨界圧軽水炉の材料腐食抑制のための処理方法と、その処理方法のための酸化装置に関する。   The present invention relates to a supercritical light water reactor using a direct cycle, a treatment method for suppressing material corrosion of the supercritical light water reactor, and an oxidation apparatus for the treatment method.

沸騰水型軽水炉(BWR)は直接サイクルであり、原子炉冷却水は炉心部で約288℃に加熱され、発生した蒸気は熱交換器(蒸気発生器)を介さずに直接、蒸気タービンに送られる。冷却水中にはコバルト60をはじめとする放射性物質が含まれるが、そのほとんどは液相中に存在し、蒸気となって蒸気タービンに移行する割合は1/1000以下と考えられる。   The boiling water light water reactor (BWR) is a direct cycle, in which the reactor cooling water is heated to about 288 ° C in the core, and the generated steam is sent directly to the steam turbine without going through the heat exchanger (steam generator). It is done. The cooling water contains radioactive substances such as cobalt 60, but most of them are present in the liquid phase, and the ratio of transition to steam turbine is considered to be 1/1000 or less.

一方、現在研究が進められている超臨界圧軽水炉では、冷却水の温度を374℃、圧力を22.1MPa以上の超臨界状態とし、全量をタービンに送ることにより、従来のBWRより、高い熱効率を得ることができると考えられている(特許文献1)。また、BWRでは蒸気中の水分を除去するために、気水分離器や蒸気乾燥器が必要であるが、超臨界圧軽水炉ではこれらの機器が不要であり、原子炉を簡素化できるという利点がある。
特開平8−313664号公報 K. Sue et al. “Solubility of lead (II) oxide and copper (II) oxide in subcritical and supercritical water” J. Chem. Eng. Data, No.44, p1422 (1999)
On the other hand, in the supercritical light water reactor that is currently being researched, the temperature of the cooling water is set to a supercritical state of 374 ° C. and the pressure is 22.1 MPa or more, and the entire amount is sent to the turbine, so that the thermal efficiency is higher than that of the conventional BWR. It is thought that can be obtained (patent document 1). In addition, in BWR, a steam separator and a steam dryer are necessary to remove moisture in the steam. However, these devices are unnecessary in a supercritical light water reactor, and the reactor can be simplified. is there.
JP-A-8-313664 K. Sue et al. “Solubility of lead (II) oxide and copper (II) oxide in subcritical and supercritical water” J. Chem. Eng. Data, No. 44, p1422 (1999)

ところで、上記の超臨界圧軽水炉では、炉心を流れる冷却水の全量が超臨界状態となりタービンに移行する。その結果、冷却水中に含まれる全ての放射性物質が冷却水と共にタービンに移行するという問題点がある。冷却水中の放射性物質の源は、原子炉構造材や燃料被覆管材料中に含まれるコバルトなどが放射化して放出されることである。放出される際の放射化金属の形態としては、金属酸化物あるいはイオンの形態がある。したがって、金属材料の腐食によるはく離および溶解を抑制することにより、放射性物質のタービンへの移行を抑制できる。また、最近の研究の結果より、金属酸化物の溶解度は350℃近辺で大きくなることが知られている(非特許文献1)。   By the way, in the above supercritical pressure light water reactor, the entire amount of cooling water flowing through the core becomes supercritical and shifts to the turbine. As a result, there is a problem that all radioactive substances contained in the cooling water are transferred to the turbine together with the cooling water. The source of radioactive material in the cooling water is that cobalt contained in the nuclear reactor structural material and fuel cladding material is activated and released. The form of the activated metal when released is in the form of a metal oxide or ion. Therefore, the migration of radioactive materials to the turbine can be suppressed by suppressing the separation and dissolution due to the corrosion of the metal material. From the results of recent studies, it is known that the solubility of metal oxides increases around 350 ° C. (Non-patent Document 1).

本発明は上記背景技術の課題を解決するためになされたものであり、直接サイクルを用いた超臨界圧軽水炉の金属材料腐食を抑制し、放射性腐食生成物のタービン系への移行を低減し、タービン系の線量を低減することを目的とする。   The present invention has been made to solve the above-mentioned problems of the background art, suppresses the metal material corrosion of the supercritical pressure light water reactor using the direct cycle, reduces the transition of radioactive corrosion products to the turbine system, The purpose is to reduce the dose of the turbine system.

本発明は上記目的を達成するものであって、本発明に係る超臨界圧軽水炉処理方法は、直接サイクルを用いた超臨界圧軽水炉の処理方法であって、前記超臨界圧軽水炉内の冷却材に接する部分の固体金属材料の表面の少なくとも一部に酸化処理を施すことを特徴とする。   The present invention achieves the above object, and the supercritical pressure light water reactor treatment method according to the present invention is a treatment method of a supercritical pressure light water reactor using a direct cycle, and a coolant in the supercritical pressure light water reactor An oxidation treatment is performed on at least a part of the surface of the solid metal material in a portion in contact with the surface.

また、本発明に係る超臨界圧軽水炉は、直接サイクルを用いた超臨界圧軽水炉において、冷却材に接する部分の固体金属材料の表面の少なくとも一部に酸化処理が施されていること、を特徴とする。   Further, the supercritical pressure light water reactor according to the present invention is characterized in that in the supercritical pressure light water reactor using a direct cycle, at least a part of the surface of the solid metal material in contact with the coolant is subjected to oxidation treatment. And

また、本発明に係る酸化処理装置は、直接サイクルを用いた超臨界圧軽水炉の冷却材に接する部分の固体金属材料の表面の少なくとも一部に酸化処理を施すための酸化処理装置であって、水を溜めるリザーバタンクと、固体被処理金属材料を収容し、ヒーターを有する耐圧容器である酸化処理用容器と、前記リザーバタンク内の水を前記酸化処理用容器に送るポンプと、前記リザーバタンクから前記酸化処理用容器に流入する水と前記酸化処理用容器から前記リザーバタンクに向かう水との間で熱交換を行なわせる熱交換器と、前記酸化処理用容器内の圧力を測定する圧力計と、前記酸化処理用容器内の温度を測定する温度計と、を有することを特徴とする。   Moreover, the oxidation treatment apparatus according to the present invention is an oxidation treatment apparatus for performing oxidation treatment on at least a part of the surface of the solid metal material in contact with the coolant of the supercritical light water reactor using a direct cycle, A reservoir tank for storing water; an oxidation processing container that is a pressure-resistant container containing a solid metal material to be processed and having a heater; a pump for sending water in the reservoir tank to the oxidation processing container; A heat exchanger for exchanging heat between the water flowing into the oxidation treatment vessel and the water from the oxidation treatment vessel toward the reservoir tank; and a pressure gauge for measuring the pressure in the oxidation treatment vessel; And a thermometer for measuring the temperature in the oxidation treatment container.

本発明によれば、直接サイクルを用いた超臨界圧軽水炉の材料腐食を抑制し、それによって、放射性腐食生成物のタービン系への移行を低減し、タービン系の線量を低減することができる。   According to the present invention, material corrosion of a supercritical pressure light water reactor using a direct cycle can be suppressed, thereby reducing the migration of radioactive corrosion products to the turbine system and reducing the dose of the turbine system.

以下に、図面を参照しながら本発明の実施形態を説明する。ここで、互いに同一または類似の部分には共通の符号を付して、重複説明は省略する。   Embodiments of the present invention will be described below with reference to the drawings. Here, the same or similar parts are denoted by common reference numerals, and redundant description is omitted.

[第1の実施形態]
本発明の第1の実施形態に係る超臨界圧軽水炉およびその処理方法ならびに酸化処理装置を、図1および図2を参照して説明する。
[First Embodiment]
A supercritical light water reactor, a treatment method thereof, and an oxidation treatment apparatus according to a first embodiment of the present invention will be described with reference to FIGS. 1 and 2.

図1は、本発明の第1の実施形態に係る超臨界圧軽水炉を示す概略系統図である。この超臨界圧軽水炉は直接サイクルを用いたものであって、原子炉内の蒸気が熱交換器(蒸気発生器)を介さずに直接、蒸気タービンに送られ、復水後に再び原子炉内に戻る構造になっている。   FIG. 1 is a schematic system diagram showing a supercritical light water reactor according to a first embodiment of the present invention. This supercritical light water reactor uses a direct cycle, and the steam in the reactor is sent directly to the steam turbine without going through the heat exchanger (steam generator), and again into the reactor after condensing. It has a back structure.

原子炉圧力容器31内に炉心32が収容されている。炉心32で発生した超臨界圧の高温水(蒸気)が蒸気タービン33に導かれ、ここで蒸気タービン33を駆動し、蒸気タービン33によって発電機40を駆動する。蒸気タービン33で仕事を終えた蒸気は復水器34で冷却されて復水になる。この復水は、冷却材浄化装置35、復水ポンプ36、給水加熱器37を経て給水として原子炉圧力容器31に戻される。炉心32内には、燃料被覆管によって被覆された多数の燃料棒が装荷されている。   A reactor core 32 is accommodated in the reactor pressure vessel 31. Supercritical high-temperature water (steam) generated in the core 32 is guided to the steam turbine 33, where the steam turbine 33 is driven, and the generator 40 is driven by the steam turbine 33. The steam that has finished work in the steam turbine 33 is cooled in the condenser 34 to become condensed water. This condensate is returned to the reactor pressure vessel 31 as feed water through the coolant purification device 35, the condensate pump 36, and the feed water heater 37. A large number of fuel rods covered with a fuel cladding tube are loaded in the core 32.

この実施形態では、原子炉圧力容器31内の構造材や燃料被覆管等の、冷却材に接する部分の固体金属材料の表面の少なくとも一部に、予備酸化処理が施され、この予備酸化処理によって、その被処理部に酸化皮膜が形成されている。これにより被処理材の腐食が抑制され、水中に放出される放射性物質の量が抑制される。その結果、炉水中の放射能濃度が低下し、蒸気タービン33や復水器34を含むタービン系への放射性腐食生成物の移行を抑制することができる。   In this embodiment, at least a part of the surface of the solid metal material in the portion in contact with the coolant, such as the structural material in the reactor pressure vessel 31 or the fuel cladding tube, is subjected to a pre-oxidation treatment. The oxide film is formed on the treated portion. Thereby, corrosion of a to-be-processed material is suppressed and the quantity of the radioactive substance discharge | released in water is suppressed. As a result, the radioactive concentration in the reactor water decreases, and the migration of radioactive corrosion products to the turbine system including the steam turbine 33 and the condenser 34 can be suppressed.

図2は、本発明の第1の実施形態に係る表面酸化装置を示す模式的系統図である。ここでは、被処理材料の一例として、燃料被覆管の場合について説明する。超臨界圧軽水炉に用いられる燃料被覆管1は、原子炉への装荷前に酸化処理用容器2内に設置される。リザーバタンク3内には水が溜められ、この水は、酸素注入装置20、水素注入装置21、窒素注入装置22によって水質調整されている。リザーバタンク3内の水は、高圧ポンプ4で昇圧され、熱交換器5を通って加熱された後、酸化処理用容器2に送られる。酸化処理用容器2にはヒーター6が設置され、所定の温度まで加熱される。酸化処理用容器2内の圧力と温度はそれぞれ、圧力計7と温度計8で測定される。   FIG. 2 is a schematic system diagram showing the surface oxidation apparatus according to the first embodiment of the present invention. Here, the case of a fuel cladding tube will be described as an example of the material to be processed. The fuel cladding tube 1 used in the supercritical light water reactor is installed in the oxidation treatment container 2 before loading into the nuclear reactor. Water is stored in the reservoir tank 3, and the water quality is adjusted by the oxygen injection device 20, the hydrogen injection device 21, and the nitrogen injection device 22. The water in the reservoir tank 3 is pressurized by the high-pressure pump 4, heated through the heat exchanger 5, and then sent to the oxidation treatment container 2. A heater 6 is installed in the oxidation treatment container 2 and heated to a predetermined temperature. The pressure and temperature in the oxidation treatment container 2 are measured by a pressure gauge 7 and a thermometer 8, respectively.

酸化処理用容器2内の水は、熱交換器5を通って減温され、溶存水素計23、溶存酸素計24、導電率計25、イオン交換樹脂26を順次通ってリザーバタンク3に戻る。リザーバタンク3内に溜まった水の水質を測定するために、溶存水素計26、溶存酸素計27、導電率計28が配置されている。   The water in the oxidation treatment container 2 is cooled through the heat exchanger 5 and returns to the reservoir tank 3 through the dissolved hydrogen meter 23, dissolved oxygen meter 24, conductivity meter 25, and ion exchange resin 26 in order. In order to measure the quality of the water accumulated in the reservoir tank 3, a dissolved hydrogen meter 26, a dissolved oxygen meter 27, and a conductivity meter 28 are arranged.

この装置を用いることによって、燃料被覆管1の表面に、目標とする酸化皮膜を形成することができる。   By using this apparatus, a target oxide film can be formed on the surface of the fuel cladding tube 1.

図3は、オーステナイト系ステンレス鋼(SUS316L)について、予備酸化処理による腐食溶出量の低減効果を示す試験結果のグラフである。標準材(メーカーから受け入れたままの状態)と、350℃の純水中で200時間の予備酸化処理を施した試験材について、350℃の水中で500時間の腐食試験を行なった。この腐食試験における皮膜の溶出量の相対値をグラフに示している。図3から明らかなように、予備酸化処理されていることにより、ステンレス鋼の溶出量は減少する。   FIG. 3 is a graph of test results showing the effect of reducing the corrosion elution amount by pre-oxidation treatment for austenitic stainless steel (SUS316L). A corrosion test for 500 hours in 350 ° C. water was performed on the standard material (as received from the manufacturer) and a test material subjected to a pre-oxidation treatment for 200 hours in pure water at 350 ° C. The relative value of the film elution amount in this corrosion test is shown in the graph. As is apparent from FIG. 3, the amount of elution of stainless steel decreases due to the pre-oxidation treatment.

上述のように、予備酸化処理を施した固体金属材料では、溶出量が減少し、水中に放出される放射性物質の量は減少する。その結果、炉水中の放射能濃度の低減が達成できる。   As described above, in the solid metal material subjected to the pre-oxidation treatment, the amount of elution is reduced, and the amount of radioactive substance released into water is reduced. As a result, a reduction in radioactivity concentration in the reactor water can be achieved.

予備酸化処理の条件は、上記の温度と圧力を変化させて制御できる。350℃以上の未臨界高温水を用いて20〜200時間処理すると、大きな腐食抑制効果があった。また、高温水以外に高温の水蒸気を用いても、同様の効果が得られる。たとえば、500℃以上の高温水蒸気を用いて20〜200時間処理すると、大きな腐食抑制効果があった。   The conditions for the pre-oxidation treatment can be controlled by changing the temperature and pressure. When treated for 20 to 200 hours with subcritical high temperature water at 350 ° C. or higher, there was a significant corrosion inhibition effect. Moreover, the same effect can be obtained by using high-temperature water vapor in addition to high-temperature water. For example, when treated for 20 to 200 hours using high-temperature steam at 500 ° C. or higher, there was a significant corrosion inhibition effect.

また、水中の酸素濃度はリザーバタンク3内のガスを制御することにより、所定の酸素濃度に調整することができる。溶存酸素濃度が8ppm以上の高温水を用いた酸化処理により、良好な腐食抑制効果があった。   Further, the oxygen concentration in water can be adjusted to a predetermined oxygen concentration by controlling the gas in the reservoir tank 3. Oxidation treatment using high temperature water having a dissolved oxygen concentration of 8 ppm or more had a good corrosion inhibitory effect.

[第2の実施形態]
本発明の第2の実施形態を、図4を参照して説明する。この実施形態では、前述の予備酸化処理に先立ち、その酸化処理の対象になる固体金属材料の表面に機械研磨処理を施す。図4に示す例では、処理対象となる固体金属材料は、燃料被覆管1であるとする。燃料被覆管1を固定し、回転させながら、研磨装置9により、表面に機械研磨処理を施す。機械研磨処理を施した材料では、表面が平滑になり、接液面積が小さくなる。この機械研磨処理の後に、たとえば第1の実施形態と同様の酸化処理を行なう。
[Second Embodiment]
A second embodiment of the present invention will be described with reference to FIG. In this embodiment, prior to the above-described preliminary oxidation treatment, a mechanical polishing treatment is performed on the surface of the solid metal material to be oxidized. In the example shown in FIG. 4, it is assumed that the solid metal material to be processed is the fuel cladding tube 1. While the fuel cladding 1 is fixed and rotated, the surface is mechanically polished by the polishing device 9. In the material subjected to the mechanical polishing treatment, the surface becomes smooth and the liquid contact area becomes small. After this mechanical polishing process, for example, an oxidation process similar to that of the first embodiment is performed.

予備酸化処理に先立って研磨処理を施すことにより、当該金属材料の接液面積が比較的小さくなり、溶出量が減少し、水中に放出される放射性物質の量が減少する。その結果、炉水中の放射能濃度の低減が達成できる。   By performing the polishing treatment prior to the pre-oxidation treatment, the wetted area of the metal material becomes relatively small, the amount of elution is reduced, and the amount of radioactive substance released into water is reduced. As a result, a reduction in radioactivity concentration in the reactor water can be achieved.

この実施形態の変形例として、研磨の方法として機械研磨以外に、酸などの化学薬品による化学研磨や、電解液を用いた電解研磨などを用いることでも、同様の効果が得られる。   As a modification of this embodiment, the same effect can be obtained by using chemical polishing such as acid, electrolytic polishing using an electrolytic solution, or the like in addition to mechanical polishing as a polishing method.

[第3の実施形態]
本発明の第3の実施形態を、図5を参照して説明する。図5は、本発明の第3の実施形態に係る表面酸化装置を示す模式的系統図である。この実施形態は第1の実施形態の変形であって、熱交換器5から酸化処理用容器2へ向かう配管の途中に、薬液タンク10からの薬液を薬液ポンプ11によって注入する配管が接続されている。薬液タンク10内には注入しようとする金属イオンを含む溶液が入っている。ここで、注入される金属イオンとしては、たとえば、Ni、Zn、Fe、Cr、Mn、Cu、Pd、Pt、Al、Mo、V、Wのいずれか一種類または複数種類である。
[Third Embodiment]
A third embodiment of the present invention will be described with reference to FIG. FIG. 5 is a schematic system diagram showing a surface oxidation apparatus according to the third embodiment of the present invention. This embodiment is a modification of the first embodiment, and a pipe for injecting a chemical from the chemical tank 10 by the chemical pump 11 is connected to the middle of the pipe from the heat exchanger 5 toward the oxidation treatment container 2. Yes. The chemical tank 10 contains a solution containing metal ions to be injected. Here, the metal ions to be implanted are, for example, one or more of Ni, Zn, Fe, Cr, Mn, Cu, Pd, Pt, Al, Mo, V, and W.

上記構成の表面酸化装置を用いて第1の実施形態とほぼ同様の予備酸化処理を行なう際に、薬液タンク10内の薬液を酸化処理用容器2へ注入する。これにより、燃料被覆管1の表面に薬液タンク10内の金属を含む、保護性の高い複合酸化皮膜層が形成される。このようにして形成された複合酸化皮膜は、緻密で保護性が高いため、皮膜溶出量が減少し、水中に放出される放射性物質の量は減少する。その結果、炉水中の放射能濃度の低減が達成できる。   When performing a pre-oxidation process substantially the same as that of the first embodiment using the surface oxidation apparatus having the above-described configuration, the chemical solution in the chemical solution tank 10 is injected into the oxidation treatment container 2. As a result, a highly protective composite oxide film layer containing the metal in the chemical tank 10 is formed on the surface of the fuel cladding tube 1. Since the composite oxide film formed in this way is dense and highly protective, the amount of elution of the film decreases and the amount of radioactive material released into water decreases. As a result, a reduction in radioactivity concentration in the reactor water can be achieved.

本発明の第1の実施形態に係る超臨界圧軽水炉を示す概略系統図。1 is a schematic system diagram showing a supercritical light water reactor according to a first embodiment of the present invention. 本発明の第1の実施形態に係る表面酸化装置を示す模式的系統図。1 is a schematic system diagram showing a surface oxidation apparatus according to a first embodiment of the present invention. 本発明の第1の実施形態の効果を示すグラフであって、標準材とこの実施形態によって酸化処理された予備酸化材の腐食溶出量を相対値で示すグラフ。It is a graph which shows the effect of the 1st Embodiment of this invention, Comprising: The graph which shows the corrosion elution amount of the pre-oxidation material oxidized by this embodiment and this embodiment by a relative value. 本発明の第2の実施形態に係る機械研磨処理のようすを示す模式的斜視図。The typical perspective view which shows the appearance of the mechanical polishing process which concerns on the 2nd Embodiment of this invention. 本発明の第3の実施形態に係る表面酸化装置を示す模式的系統図。The typical systematic diagram which shows the surface oxidation apparatus which concerns on the 3rd Embodiment of this invention.

符号の説明Explanation of symbols

1…燃料被覆管、2…酸化処理用容器、3…リザーバタンク、4…高圧ポンプ、5…熱交換器、6…ヒーター、7…圧力計、8…温度計、9…研磨装置、10…薬液タンク、11…薬液ポンプ、31…原子炉圧力容器、32…炉心、33…蒸気タービン、34…復水器、35…冷却材浄化装置、36…復水ポンプ、37…給水加熱器、40…発電機 DESCRIPTION OF SYMBOLS 1 ... Fuel cladding tube, 2 ... Oxidation processing container, 3 ... Reservoir tank, 4 ... High pressure pump, 5 ... Heat exchanger, 6 ... Heater, 7 ... Pressure gauge, 8 ... Thermometer, 9 ... Polishing apparatus, 10 ... Chemical solution tank, 11 ... Chemical solution pump, 31 ... Reactor pressure vessel, 32 ... Reactor core, 33 ... Steam turbine, 34 ... Condenser, 35 ... Coolant purification device, 36 ... Condensate pump, 37 ... Feed water heater, 40 …Generator

Claims (13)

直接サイクルを用いた超臨界圧軽水炉の処理方法であって、前記超臨界圧軽水炉内の冷却材に接する部分の固体金属材料の表面の少なくとも一部に酸化処理を施すことを特徴とする超臨界圧軽水炉処理方法。   A supercritical pressure light water reactor treatment method using a direct cycle, characterized in that at least part of the surface of the solid metal material in contact with the coolant in the supercritical pressure light water reactor is subjected to oxidation treatment Pressure light water reactor treatment method. 前記酸化処理は高温水または高温水蒸気を用いるものであること、を特徴とする請求項1に記載の超臨界圧軽水炉処理方法。   The supercritical pressure light water reactor treatment method according to claim 1, wherein the oxidation treatment uses high-temperature water or high-temperature steam. 前記酸化処理は、温度が350℃以上の未臨界条件の高温水を用い、20時間ないし200時間処理するものであること、を特徴とする請求項2に記載の超臨界圧軽水炉処理方法。   The supercritical pressure light water reactor treatment method according to claim 2, wherein the oxidation treatment is performed for 20 hours to 200 hours using high-temperature water under subcritical conditions at a temperature of 350 ° C or higher. 前記酸化処理は、温度が500℃以上の高温蒸気を用い、20時間ないし200時間処理するものであること、を特徴とする請求項2に記載の超臨界圧軽水炉処理方法。   The supercritical pressure light water reactor treatment method according to claim 2, wherein the oxidation treatment is performed using high temperature steam having a temperature of 500 ° C or higher for 20 hours to 200 hours. 前記酸化処理は溶存酸素濃度が8ppm以上の高温水を用いること、を特徴とする請求項2または請求項3に記載の超臨界圧軽水炉処理方法。   The supercritical pressure light water reactor treatment method according to claim 2 or 3, wherein the oxidation treatment uses high-temperature water having a dissolved oxygen concentration of 8 ppm or more. 前記酸化処理は、Ni、Zn、Fe、Cr、Mn、Cu、Pd、Pt、Al、Mo、V、Wのうちの少なくとも1種類を含む高温水を用いて行なうものであること、を特徴とする請求項1ないし請求項5のいずれか一項に記載の超臨界圧軽水炉処理方法。   The oxidation treatment is performed using high-temperature water containing at least one of Ni, Zn, Fe, Cr, Mn, Cu, Pd, Pt, Al, Mo, V, and W. A supercritical light water reactor treatment method according to any one of claims 1 to 5. 前記酸化処理に先立って、酸化処理の対象となる固体金属材料の表面に研磨処理を施すこと、を特徴とする請求項1ないし請求項6のいずれかに記載の超臨界圧軽水炉処理方法。   The supercritical pressure light water reactor treatment method according to any one of claims 1 to 6, wherein a polishing process is performed on a surface of the solid metal material to be oxidized prior to the oxidation process. 前記研磨処理は機械研磨または電解研磨であること、を特徴とする請求項7に記載の超臨界圧軽水炉処理方法。   The supercritical pressure light water reactor treatment method according to claim 7, wherein the polishing treatment is mechanical polishing or electrolytic polishing. 前記酸化処理の対象となる固体金属材料は燃料被覆管を含むこと、を特徴とする請求項1ないし請求項8のいずれかに記載の超臨界圧軽水炉処理方法。   The supercritical light water reactor treatment method according to any one of claims 1 to 8, wherein the solid metal material to be subjected to the oxidation treatment includes a fuel cladding tube. 直接サイクルを用いた超臨界圧軽水炉において、冷却材に接する部分の固体金属材料の表面の少なくとも一部に酸化処理が施されていること、を特徴とする超臨界圧軽水炉。   A supercritical light water reactor using a direct cycle, wherein at least part of the surface of the solid metal material in contact with the coolant is oxidized. 直接サイクルを用いた超臨界圧軽水炉の冷却材に接する部分の固体金属材料の表面の少なくとも一部に酸化処理を施すための酸化処理装置であって、
水を溜めるリザーバタンクと、
固体被処理金属材料を収容し、ヒーターを有する耐圧容器である酸化処理用容器と、
前記リザーバタンク内の水を前記酸化処理用容器に送るポンプと、
前記リザーバタンクから前記酸化処理用容器に流入する水と前記酸化処理用容器から前記リザーバタンクに向かう水との間で熱交換を行なわせる熱交換器と、
前記酸化処理用容器内の圧力を測定する圧力計と、
前記酸化処理用容器内の温度を測定する温度計と、
を有することを特徴とする酸化処理装置。
An oxidation treatment apparatus for subjecting at least part of the surface of a solid metal material in contact with a coolant of a supercritical pressure light water reactor using a direct cycle to oxidation treatment,
A reservoir tank for storing water,
A container for oxidation treatment which is a pressure vessel containing a solid metal material to be treated and having a heater;
A pump for sending water in the reservoir tank to the oxidation treatment container;
A heat exchanger that exchanges heat between water flowing from the reservoir tank into the oxidation treatment container and water from the oxidation treatment container toward the reservoir tank;
A pressure gauge for measuring the pressure in the oxidation treatment container;
A thermometer for measuring the temperature in the oxidation treatment container;
An oxidation processing apparatus comprising:
前記水の溶存水素を測定する溶存水素計と、
前記水の溶存酸素を測定する溶存酸素計と、
前記水の導電率を測定する導電率計と、
をさらに有することを特徴とする請求項11に記載の酸化処理装置。
A dissolved hydrogen meter for measuring dissolved hydrogen in the water;
A dissolved oxygen meter for measuring the dissolved oxygen of the water;
A conductivity meter for measuring the conductivity of the water;
The oxidation processing apparatus according to claim 11, further comprising:
金属イオンを含む薬液を溜める薬液タンクと、
前記薬液タンク内の薬液を前記酸化処理用容器内に注入するための薬液ポンプと、
をさらに有することを特徴とする請求項11または請求項12に記載の酸化処理装置。
A chemical tank for storing a chemical containing metal ions;
A chemical pump for injecting the chemical in the chemical tank into the oxidation container;
The oxidation treatment apparatus according to claim 11, further comprising:
JP2006214132A 2006-08-07 2006-08-07 Supercritical light water reactor, treatment method thereof and oxidation treatment apparatus Withdrawn JP2008039579A (en)

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Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN102568624A (en) * 2011-12-05 2012-07-11 李正蔚 High-temperature supercritical nuclear reactor

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN102568624A (en) * 2011-12-05 2012-07-11 李正蔚 High-temperature supercritical nuclear reactor

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