JPH034145A - Device for diagnosing corrosion resistance of in-pile structual material - Google Patents
Device for diagnosing corrosion resistance of in-pile structual materialInfo
- Publication number
- JPH034145A JPH034145A JP1137372A JP13737289A JPH034145A JP H034145 A JPH034145 A JP H034145A JP 1137372 A JP1137372 A JP 1137372A JP 13737289 A JP13737289 A JP 13737289A JP H034145 A JPH034145 A JP H034145A
- Authority
- JP
- Japan
- Prior art keywords
- hardness
- corrosion resistance
- reactor
- arithmetic unit
- upper grid
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Pending
Links
- 239000000463 material Substances 0.000 title claims abstract description 35
- 230000007797 corrosion Effects 0.000 title claims abstract description 34
- 238000005260 corrosion Methods 0.000 title claims abstract description 34
- 238000007542 hardness measurement Methods 0.000 claims abstract description 4
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 abstract description 7
- 230000035945 sensitivity Effects 0.000 abstract 1
- 238000010586 diagram Methods 0.000 description 3
- 238000007689 inspection Methods 0.000 description 3
- 238000005259 measurement Methods 0.000 description 3
- 238000009835 boiling Methods 0.000 description 2
- 238000005336 cracking Methods 0.000 description 2
- 208000002925 dental caries Diseases 0.000 description 2
- 230000006866 deterioration Effects 0.000 description 2
- 238000003745 diagnosis Methods 0.000 description 2
- 238000012360 testing method Methods 0.000 description 2
- 238000011179 visual inspection Methods 0.000 description 2
- 206010061274 Malocclusion Diseases 0.000 description 1
- 229910000963 austenitic stainless steel Inorganic materials 0.000 description 1
- 239000003795 chemical substances by application Substances 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- 230000000246 remedial effect Effects 0.000 description 1
- 238000012216 screening Methods 0.000 description 1
- 238000009864 tensile test Methods 0.000 description 1
Classifications
-
- Y—GENERAL 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
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Testing Resistance To Weather, Investigating Materials By Mechanical Methods (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
Description
【発明の詳細な説明】
〔発明の目的〕
（産業上の利用分野）
本発明は、たとえば沸騰水型原子炉内における構造物材
料の耐食性劣化を診断できるようにした炉内構造物材料
の耐食性診断装置に関する。[Detailed Description of the Invention] [Object of the Invention] (Industrial Application Field) The present invention is directed to improving the corrosion resistance of reactor internal structure materials, which enables diagnosis of corrosion resistance deterioration of structural materials in boiling water nuclear reactors, for example. Related to diagnostic equipment.
（従来の技術）
軽水炉の原子力発電所には炉心を内蔵する原子炉圧力容
器が設けられ、この原子炉圧力容器の内部には炉心シュ
ラウド、炉心支持板、上部及び下部格子板、ジェットポ
ンプ等が設置されている。(Prior art) A light water reactor nuclear power plant is equipped with a reactor pressure vessel containing a reactor core, and inside this reactor pressure vessel there are a core shroud, a core support plate, upper and lower lattice plates, a jet pump, etc. is set up.
一般に原子力発電所はその健全性、信頼性を確保するた
め、定期的に運転を停止して点検を行っている。上述し
た原子炉の炉内構造物もこの時の検査が行われ、この検
査手段に水中テレビカメラが使用され、主として目視検
査が行われている。Generally, in order to ensure the health and reliability of nuclear power plants, operations are periodically halted and inspected. The internal structures of the above-mentioned nuclear reactor are also inspected at this time, and an underwater television camera is used as the inspection means, and mainly visual inspection is performed.
（発明が解決しようとする課題）
上述したように炉内構造物の検査手段としては水中テレ
ビカメラを使用しての目視検査が一般的であるが、炉内
構造物の形状が複雑であるため、水中テレビカメラを目
的の所へ接近させることが困難な場合がある。したがっ
て、水中テレビカメラでは検査範囲が限られる。また材
料自体の強度等に関する検査は行われていない。(Problems to be Solved by the Invention) As mentioned above, visual inspection using an underwater television camera is a common means of inspecting reactor internals, but because the shape of reactor internals is complex, , it may be difficult to bring an underwater television camera close to the target location. Therefore, the inspection range of underwater television cameras is limited. Furthermore, no tests have been conducted regarding the strength of the material itself.
一方、最近原子炉の長寿命化等の検討も行なわれ始め、
炉内構造物の強度に関する検査の必要性が増えている。On the other hand, studies have recently begun to consider extending the lifespan of nuclear reactors.
There is an increasing need for testing the strength of reactor internals.
特に炉内構造物の中でも燃料領域に近接する上部格子板
、シュラウド等では高速中性子に曝されることから構造
物材料の強度増加。Particularly in reactor internal structures, such as the upper grid plate and shroud, which are close to the fuel area, are exposed to fast neutrons, which increases the strength of the structural materials.
伸びの減少が生ずる。また、高速中性子に曝されると耐
食性、特に耐応力腐食性割れ性（耐ＳＣＣ性）が劣化す
る可能性がある。よって、このような炉内構造物材料の
健全性を確認するための検査手段が必要となるが、従来
まで炉内構造物材料の耐食性の劣化を診断することは知
られていない。A decrease in elongation occurs. Furthermore, when exposed to fast neutrons, corrosion resistance, particularly stress corrosion cracking resistance (SCC resistance), may deteriorate. Therefore, there is a need for an inspection means for confirming the soundness of such reactor internal structure materials, but until now it has not been known to diagnose deterioration in the corrosion resistance of reactor internal structure materials.
本発明はこのような点に鑑みなされたもので軽水炉の炉
内構造物材料の硬度から応力腐食割れ（ＳＣＣ）感受性
の有無を判定して耐食性を容易に診断できる炉内構造物
材料の耐食性診断装置を提供することにある。The present invention was developed in view of the above points, and is a method for diagnosing the corrosion resistance of light water reactor internal structure materials, which can easily diagnose the corrosion resistance by determining the presence or absence of stress corrosion cracking (SCC) susceptibility from the hardness of the reactor internal structure materials. The goal is to provide equipment.
（課題を解決するための手段）
本発明は、被診断材料としての炉内構造物材料の硬度を
測定する硬度測定装置と、この硬度測定装置で得られた
材料の硬度から材料の耐食性を予測・演算する演算装置
と、この演算装置からの演算結果を表示する表示装りと
からなることを特徴とする。(Means for Solving the Problems) The present invention provides a hardness measuring device for measuring the hardness of a reactor internal structure material as a material to be diagnosed, and predicting the corrosion resistance of the material from the hardness of the material obtained by this hardness measuring device. - It is characterized by consisting of an arithmetic device that performs calculations and a display device that displays the calculation results from this arithmetic device.
（作用）
本発明は、被診断材料としての軽水炉用炉内構造物材料
の硬度を硬度計で測定し、その測定結果から硬度と耐食
性の相関関係を用いて、耐食性を予想演算する。すなわ
ち、中性子照射による硬度の増加とＳＣＣ感受性の増加
の相関関係から構造物材料の耐食性を診断する。従って
、この結果をみることによって測定時点における構造物
材料の耐食性を判断できる。(Function) The present invention measures the hardness of a light water reactor internal structure material as a material to be diagnosed using a hardness meter, and uses the correlation between hardness and corrosion resistance from the measurement results to predict the corrosion resistance. That is, the corrosion resistance of the structural material is diagnosed from the correlation between the increase in hardness due to neutron irradiation and the increase in SCC susceptibility. Therefore, by looking at this result, the corrosion resistance of the structural material at the time of measurement can be determined.
（実施例）
第１図および第２図を参照しながら本発明の一実施例を
説明する。(Example) An example of the present invention will be described with reference to FIGS. 1 and 2.
第１図においては原子炉構造物材料の被診断材料１の硬
度を硬度測定装Ｍ２で測定し、演算装置３で演算し、そ
の演算結果を表示装置４で表示する構造材料の耐食性診
断装置をブロック図で示している。第２図は３００℃に
おける高速中性子を照射されたオーステナイト系ステン
レス鋼のビッカース硬度増加量と、中性子照射後、２９
０℃の高温水中で低歪速度引張試験を行うことによって
得られたＳＣＣ感受性の関係を示したものである。ここ
で、照射後の硬度は、硬射前後の硬度の差すなわち、照
射による硬度の増加量と照射前の硬度の比を％で表わし
ＳＣＣ感受性は、低歪速度引張試験で得られた材料波面
の粒界割れ破面率を％で表示している。In FIG. 1, there is shown a corrosion resistance diagnostic device for structural materials in which the hardness of a material to be diagnosed 1, which is a nuclear reactor structure material, is measured by a hardness measuring device M2, the calculation is performed by a calculation device 3, and the calculation result is displayed by a display device 4. It is shown in a block diagram. Figure 2 shows the increase in Vickers hardness of austenitic stainless steel irradiated with fast neutrons at 300°C and the increase in Vickers hardness at 29°C after neutron irradiation.
This figure shows the relationship between SCC susceptibility obtained by conducting a low strain rate tensile test in high-temperature water at 0°C. Here, the hardness after irradiation is expressed as a percentage of the difference in hardness before and after irradiation, that is, the ratio of the hardness increase due to irradiation to the hardness before irradiation, and the SCC susceptibility is the difference in hardness before and after irradiation. The grain boundary crack fracture surface ratio is expressed in %.
この図から明らかなようにＳＣＣ感受性と硬さ増加量に
は、相関関係があるので、構造材料の硬さを測定するこ
とによって耐食性を予測することができる６本実施例で
は、耐食性の基準を２０％としており構造物材料の硬度
の増加量が１００％であれば、ＳＣＣ感受性は十分低く
、構造物材料は健全であると判定できる。一方、構造物
材料の硬度の増加量が１５０％であれば、この構造物は
ＳＣＣ感受性が高いと判断でき、必要な改善策をとるこ
とができる。As is clear from this figure, there is a correlation between SCC susceptibility and hardness increase, so corrosion resistance can be predicted by measuring the hardness of structural materials. If the increase in hardness of the structural material is 100%, it can be determined that the SCC susceptibility is sufficiently low and the structural material is sound. On the other hand, if the increase in hardness of the structure material is 150%, it can be determined that this structure is highly susceptible to SCC, and necessary remedial measures can be taken.
耐食性の判断基準は、構造物の環境等から適宜決定され
ばよい。The criteria for determining corrosion resistance may be appropriately determined based on the environment of the structure, etc.
次に上記実施例にもとづき第３図を参照して本発明の具
体的使用例を説明する。すなわち、第３図において原子
炉圧力容器５の内部には上部格子板６が設置されている
。原子炉上部のオペレーティングフロア９には演算装置
３と表示装置４が設置され、さらに原子炉圧力容器５の
真上には、補助ホイスト８が設けられている。補助ホイ
スト８から硬度測定装置２が吊り下げられており、硬度
測定装置２と演算装Ｍ３は信号ケーブル７で接続されて
いる。Next, a specific usage example of the present invention will be explained based on the above embodiment with reference to FIG. That is, in FIG. 3, an upper grid plate 6 is installed inside the reactor pressure vessel 5. A computing device 3 and a display device 4 are installed on the operating floor 9 in the upper part of the reactor, and furthermore, an auxiliary hoist 8 is installed directly above the reactor pressure vessel 5. The hardness measuring device 2 is suspended from the auxiliary hoist 8, and the hardness measuring device 2 and the computing device M3 are connected by a signal cable 7.
硬度測定装置！２は、振動式硬度測定を行う装置であり
、構造物の振動振幅を測定して硬度を測定する。Hardness measuring device! Reference numeral 2 denotes a device for performing vibration type hardness measurement, which measures the vibration amplitude of a structure to measure hardness.
本実施例による耐食性診断装置では、まづ補助ホイスト
８によ、り硬度測定装置１２を診断を実施したい位置の
被診断材料、つまり上部格子板６まで吊り下し硬度測定
を行う、硬度測定結果を電気信号として演算装置３に送
り込まれる。一方、演算装置１３には第２図に示したよ
うな硬度と耐食性の関係を表わす表式データが組込まれ
ており、また、あらかじめ、使用前の上部格子板６の硬
度データを入手しておく、この２つのデータを用いて、
測定箇所の耐食性レベルを演算・予測する０表示装Ｍ４
は、この演算結果を表示する。In the corrosion resistance diagnostic device according to this embodiment, first, the hardness measuring device 12 is suspended by the auxiliary hoist 8 to the material to be diagnosed at the position where the diagnosis is desired, that is, the upper grid plate 6, and the hardness is measured. is sent to the arithmetic unit 3 as an electrical signal. On the other hand, the calculation device 13 has built-in tabular data representing the relationship between hardness and corrosion resistance as shown in FIG. 2, and hardness data of the upper grid plate 6 before use is obtained in advance. , using these two data,
0 display device M4 that calculates and predicts the corrosion resistance level of the measurement point
displays the result of this operation.
この耐食性診断装置によれば、上部格子板６の耐食性を
判定できる。また、耐食性のスクリーニングレベルをあ
らかじめ演算装置１３に入力しておけば、健全であるか
、また対策が必要であるかを直接表示できる。According to this corrosion resistance diagnostic device, the corrosion resistance of the upper grid plate 6 can be determined. Furthermore, by inputting the corrosion resistance screening level into the arithmetic unit 13 in advance, it is possible to directly display whether the product is healthy or whether countermeasures are required.
上記実施例においては、硬度測定袋！２は振動式を使用
したが、これに限定するものではなく。In the above example, the hardness measurement bag! 2 uses a vibration type, but is not limited to this.
圧こん式でもよい、また、被診断材料として上部格子板
６を対象にしたが、原子炉圧力容器５内の構造物であれ
ば対象を限定するものではない、さらに、硬度測定装置
Ｅ２を任意の形に構成することにより対応できる。また
、沸騰水型原子炉のみではなく、加圧木型原子炉にも適
用可能である。In addition, although the upper grid plate 6 was targeted as the material to be diagnosed, the target is not limited to any structure within the reactor pressure vessel 5. Furthermore, the hardness measuring device E2 can be used as an arbitrary material. This can be handled by configuring it in the form of Moreover, it is applicable not only to boiling water reactors but also to pressurized wooden reactors.
本発明によれば原子炉内構造物材料の硬度を測定するこ
とによって耐食性を容易に診断することができる。According to the present invention, corrosion resistance can be easily diagnosed by measuring the hardness of reactor internal structure materials.
第１図は本発明に係る炉内構造物材料の耐食性診断装置
の一実施例を示すブロック図、第２図は第１図の実施例
をおける硬度の増加量と耐食性との関係を示す特性図、
第３図は第１図における耐食性診断装置の具体的使用例
を示す構成図である。
１・・・被測定材料、 ２・・・硬度測定装置、
３・・・演算装置、 ４・・・表示装置。
５・・・原子炉圧力容器、 ６・・・上部格子板。
７・・・信号ケーブル、 ８・・・補助ホイスト
、９・・・オペレーティングフロア。
（８７３３）代理人 弁理士 猪 股 祥 晃（ほか１
名）
第 ＩＩ！Ｉ
硬うｎ４ｊ口ｔ／うト末ｎ不咬さ（％）Ｊ＄−２図FIG. 1 is a block diagram showing an embodiment of the corrosion resistance diagnostic device for reactor internal structure materials according to the present invention, and FIG. 2 is a characteristic showing the relationship between the amount of increase in hardness and corrosion resistance in the embodiment of FIG. 1. figure,
FIG. 3 is a block diagram showing a specific usage example of the corrosion resistance diagnostic device shown in FIG. 1. 1... Material to be measured, 2... Hardness measuring device,
3... Arithmetic device, 4... Display device. 5...Reactor pressure vessel, 6...Upper grid plate. 7...Signal cable, 8...Auxiliary hoist, 9...Operating floor. (8733) Agent: Yoshiaki Inomata, patent attorney (and 1 others)
Name) Part II! I Dental cavity n 4j mouth t / dental cavity n malocclusion (%) J$-2 figure
Claims (1)
測定装置で得られた硬度測定値から耐食性を演算する演
算装置と、この演算装置から演算結果を表示する表示装
置とからなることを特徴とする炉内構造物材料の耐食性
診断装置。It is characterized by comprising a hardness measuring device that measures the hardness of the material to be diagnosed, a calculation device that calculates corrosion resistance from the hardness measurement value obtained by this hardness measuring device, and a display device that displays the calculation results from this calculation device. Corrosion resistance diagnostic equipment for reactor internal structure materials.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1137372A JPH034145A (en) | 1989-06-01 | 1989-06-01 | Device for diagnosing corrosion resistance of in-pile structual material |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1137372A JPH034145A (en) | 1989-06-01 | 1989-06-01 | Device for diagnosing corrosion resistance of in-pile structual material |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH034145A true JPH034145A (en) | 1991-01-10 |
Family
ID=15197146
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP1137372A Pending JPH034145A (en) | 1989-06-01 | 1989-06-01 | Device for diagnosing corrosion resistance of in-pile structual material |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH034145A (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2015524060A (en) * | 2012-06-22 | 2015-08-20 | コリア アトミック エナジー リサーチ インスティテュート | Method for nondestructive evaluation of intergranular stress corrosion cracking (IGSSC) in structural elements made of metal alloys, and method for evaluating the lifetime of structural elements |
| CN105021517A (en) * | 2015-07-10 | 2015-11-04 | 核工业理化工程研究院 | Movable corrosion test-bed |
-
1989
- 1989-06-01 JP JP1137372A patent/JPH034145A/en active Pending
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2015524060A (en) * | 2012-06-22 | 2015-08-20 | コリア アトミック エナジー リサーチ インスティテュート | Method for nondestructive evaluation of intergranular stress corrosion cracking (IGSSC) in structural elements made of metal alloys, and method for evaluating the lifetime of structural elements |
| CN105021517A (en) * | 2015-07-10 | 2015-11-04 | 核工业理化工程研究院 | Movable corrosion test-bed |
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