JPH09189790A - Method for diagnosing degradation of reactor structure - Google Patents

Method for diagnosing degradation of reactor structure

Info

Publication number
JPH09189790A
JPH09189790A JP8000479A JP47996A JPH09189790A JP H09189790 A JPH09189790 A JP H09189790A JP 8000479 A JP8000479 A JP 8000479A JP 47996 A JP47996 A JP 47996A JP H09189790 A JPH09189790 A JP H09189790A
Authority
JP
Japan
Prior art keywords
test
strength
deterioration
shroud
weld
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
Application number
JP8000479A
Other languages
Japanese (ja)
Inventor
Akihiko Hirano
明彦 平野
Masahiro Otaka
正廣 大高
Kunio Enomoto
邦夫 榎本
Shinobu Okido
忍 大城戸
Shigeo Hattori
成雄 服部
Takahiko Kato
隆彦 加藤
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Hitachi Ltd
Original Assignee
Hitachi Ltd
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Hitachi Ltd filed Critical Hitachi Ltd
Priority to JP8000479A priority Critical patent/JPH09189790A/en
Publication of JPH09189790A publication Critical patent/JPH09189790A/en
Pending legal-status Critical Current

Links

Classifications

    • 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

Abstract

PROBLEM TO BE SOLVED: To provide a material for a degradation diagnosis test which is required to diagnose the degree of secular degradation of a weld and a base material in materials for a structure in a nuclear reactor. SOLUTION: A material supplied for a degradation diagnosis is prepared by cutting a positioning protrusion 2 on the inner face of a shroud and a fillet weld 4 around the protrusion 2 and taking them out from a nuclear reactor. A degradation diagnosis of materials for the weld is conducted by cutting out a minute specimen 7 from the fillet weld 4 of the supplied material and conducting a strength test. Moreover, a degradation diagnosis of base materials is conducted by cutting out a specimen for strength evaluation from the protrusion 2 and conducting a strength test.

Description

【発明の詳細な説明】Detailed Description of the Invention

【0001】[0001]

【発明の属する技術分野】本発明は、中性子照射や長時
間の熱時効を受けて経年劣化する原子炉圧力容器及び原
子炉内構造物の経年劣化度診断方法に関する。
BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a reactor pressure vessel and a method for diagnosing aging deterioration of reactor internals, which deteriorate with age due to neutron irradiation and long-term thermal aging.

【0002】[0002]

【従来の技術】原子炉圧力容器の経年劣化度診断につい
ては、例えば社団法人日本原子力学会刊『軽水炉圧力容
器監視試験ハンドブック』に示されているように、原子
炉で用いているものと同じ素材から切り出した監視試験
片をカプセルに装入して原子炉内に設置しておき、所定
の期間運転した後に監視試験片を取り出してシャルピー
試験や引張り試験を行って強度を調べる方法が採られて
いた。原子炉内構造物で使用されている材料や溶接材料
については特に実施された方法はないが、圧力容器に対
するものと同じ方法を適用することができる。しかし、
これまで運転されてきた原子力プラントでは、原子炉内
構造物や溶接部の材料を監視試験片用カプセルに挿入し
ておらず、今後建設するプラントにはこの方法を適用で
きるが現在稼働中のプラントには適用できない。
2. Description of the Related Art For aging deterioration diagnosis of a reactor pressure vessel, for example, as shown in "Light Water Reactor Pressure Vessel Monitoring Test Handbook" published by the Japan Atomic Energy Society, the same materials as those used in the reactor are used. A method is used in which the monitoring test piece cut out from the above is placed in a capsule and installed in the reactor, and after operating for a predetermined period, the monitoring test piece is taken out and subjected to a Charpy test or a tensile test to check the strength. It was There is no particular method used for the materials or welding materials used in the reactor internals, but the same method as for the pressure vessel can be applied. But,
In the nuclear plants that have been operated so far, the materials of the reactor internals and welds have not been inserted into the capsule for monitoring test pieces, and this method can be applied to future plants, but the plant currently in operation Not applicable to.

【0003】[0003]

【発明が解決しようとする課題】ある期間運転され、構
造物材料の材質的な変化をもたらす程度まで中性子の照
射を受けたり、高温状態での時効を受けたりした材料
は、運転初期に有した強度よりも劣化している可能性が
あり、原子炉の健全な運転状態を維持するためにこの劣
化の程度を診断する必要がある。圧力容器材料の劣化診
断は原子炉内に設置されている監視試験片を用いて行え
ばよいが、原子炉内構造物の材料や溶接部の材料につい
ては監視試験片が無いので劣化診断用の材料を用意する
ことができない。
A material which has been operated for a certain period of time and which has been irradiated with neutrons to such an extent as to cause a change in the material quality of the structural material or has been aged at a high temperature has a material at the initial stage of operation. It may have deteriorated rather than strength, and it is necessary to diagnose the degree of this deterioration in order to maintain the healthy operating condition of the reactor. Deterioration diagnosis of the pressure vessel material may be performed using the monitoring test piece installed in the reactor, but there is no monitoring test piece for the material of the internal structure of the reactor and the material of the welded part. Inability to prepare materials.

【0004】本発明の目的は、炉内構造物や構造物溶接
部の劣化診断用供試材を得る方法を提供することにあ
る。
It is an object of the present invention to provide a method for obtaining a test material for diagnosing deterioration of in-core structures and welded parts of structures.

【0005】本発明の他の目的は、体積の小さい溶接部
の劣化診断をする方法を提供することにある。
Another object of the present invention is to provide a method for diagnosing deterioration of a weld having a small volume.

【0006】本発明の他の目的は、母材の部分と溶接部
の境界部の劣化診断をする方法を提供することにある。
Another object of the present invention is to provide a method for diagnosing deterioration of a boundary portion between a base material portion and a welded portion.

【0007】[0007]

【課題を解決するための手段】本発明によれば、炉内構
造物の一つであるシュラウドの内面にある位置決め用の
突起及び突起の周囲に存在するすみ肉溶接部の材料が、
劣化診断用の供試材として提供される。
According to the present invention, the positioning projections on the inner surface of the shroud, which is one of the reactor internals, and the material of the fillet weld existing around the projections are
It is provided as a test material for deterioration diagnosis.

【0008】また、本発明によれば、シュラウド内面に
ある位置決め用突起の周囲に存在するすみ肉溶接部の劣
化診断に、微小試験片による強度試験方法を適用する方
法が提供される。
Further, according to the present invention, there is provided a method for applying a strength test method using a micro test piece to a deterioration diagnosis of a fillet weld portion existing around a positioning projection on an inner surface of a shroud.

【0009】また、本発明によれば、炉内構造物母材の
部分と溶接部との境界の部分の材料の劣化診断を行うた
めに、微小試験片による強度試験方法を適用する方法が
提供される。
Further, according to the present invention, there is provided a method of applying a strength test method using a micro test piece for diagnosing deterioration of a material at a boundary portion between a base material of a reactor internal structure and a welded portion. To be done.

【0010】本発明によれば、ある期間運転された原子
炉で、炉内構造物の一つであるシュラウドの内面にある
位置決め用の突起及び突起の周囲に存在するすみ肉溶接
部の材料一式を、原子炉の定期検査中に適切な方法によ
って切断して原子炉外に取り出し、この供試材を用いて
強度試験や物理的諸性質の測定の実施,金属組織の観
察,元素の偏析状態の測定、さらには電子顕微鏡による
転位組織の観察等を行い、溶接部の材料や炉内構造物母
材の劣化診断ができる。
According to the present invention, in a nuclear reactor which has been operated for a certain period of time, a set of materials for a positioning projection on the inner surface of a shroud which is one of the reactor internals and a fillet weld existing around the projection is provided. Is taken out of the reactor by an appropriate method during the periodic inspection of the reactor, and strength tests and physical properties are measured using this test material, observation of metallographic structure, segregation state of elements Of the welded part and the base material of the internal structure of the furnace can be diagnosed by observing the dislocation structure with an electron microscope.

【0011】また、本発明によれば、シュラウド内面の
位置決め用突起の周囲にある体積がたいへん小さいすみ
肉溶接部から、微小ディスク試験片や微小引張り試験片
を切り出して溶接部材料の強度試験を実施することによ
り、溶接部材料の強度の変化を調べて、溶接部の劣化診
断をすることができる。
Further, according to the present invention, a minute disc test piece or a minute tensile test piece is cut out from a fillet weld having a very small volume around the positioning projection on the inner surface of the shroud, and the strength test of the weld material is performed. By carrying out the method, it is possible to check the change in the strength of the material of the welded portion and diagnose the deterioration of the welded portion.

【0012】また、本発明によれば、シュラウド内面の
位置決め用突起と、その周囲にあるすみ肉溶接部との境
界部から、微小ディスク試験片をその中心部に境界部が
存在するように切り出して、微小ディスク試験片の強度
試験を実施することにより、炉内構造物母材と溶接部材
料の境界部の劣化を診断することができる。
Further, according to the present invention, a minute disc test piece is cut out from the boundary between the positioning projection on the inner surface of the shroud and the fillet weld around the shroud so that the boundary exists at the center thereof. Then, the strength test of the small disc test piece can be performed to diagnose the deterioration of the boundary portion between the core material of the reactor internals and the weld material.

【0013】[0013]

【発明の実施の形態】図1及び図2は、劣化診断用の供
試材を切り取る部位を示す図である。シュラウド1は原
子炉内構造物の一つであり、その中心部分には燃料集合
体が入る。原子炉の運転中に炉内構造物は軽水中に浸漬
しているため、燃料集合体から発せられる中性子は軽水
中を通過してシュラウド1をはじめとする炉内構造物を
照射する。したがって、長時間使用されたシュラウド1
は、中性子照射を受けて材質が変化する可能性がある。
また、原子炉の運転中に軽水は約290℃の高温になっ
ているため、長時間運転されると熱時効によってシュラ
ウド1を含めた炉内構造物の材質が変化する可能性があ
る。シュラウド1には、プラント建設時に位置決めをす
るために使用される位置決め用突起2が、シュラウド内
壁3の表面に4個溶接されている。位置決め用突起2の
周囲には、すみ肉溶接部4が存在する。位置決め用突起
2は、プラントの建設が終了した段階で不要となる。し
たがって、プラント建設の終了後であれば、位置決め用
突起2を図3に示すように切断しても差し支えない。位
置決め用突起2はすみ肉溶接部4とともに、例えばカッ
ターを利用する方法や放電加工を利用する方法によって
切断することができる。切断された位置決め用突起2と
すみ肉溶接部4は、原子炉外に取り出して劣化診断用の
供試材として利用する。
1 and 2 are views showing a portion from which a test material for deterioration diagnosis is cut out. The shroud 1 is one of the nuclear reactor internal structures, and the fuel assembly enters the central part thereof. Since the reactor internals are immersed in the light water during the operation of the nuclear reactor, the neutrons emitted from the fuel assembly pass through the light water and irradiate the reactor internals including the shroud 1. Therefore, shroud 1 used for a long time
May change its material when exposed to neutron irradiation.
In addition, since light water has a high temperature of about 290 ° C. during the operation of the nuclear reactor, the material of the reactor internal structure including the shroud 1 may change due to thermal aging when operated for a long time. The shroud 1 is provided with four positioning projections 2 welded to the surface of the inner wall 3 of the shroud for use in positioning during plant construction. A fillet weld 4 is present around the positioning projection 2. The positioning protrusion 2 becomes unnecessary when the plant construction is completed. Therefore, after the plant construction is completed, the positioning projection 2 may be cut as shown in FIG. The positioning projection 2 can be cut together with the fillet weld 4 by, for example, a method using a cutter or a method using electric discharge machining. The cut positioning projections 2 and fillet welded portions 4 are taken out of the nuclear reactor and used as test materials for deterioration diagnosis.

【0014】図4は、すみ肉溶接部4から強度試験用の
試験片を採取する方法を示した図である。原子炉構造物
の溶接部の材料は、通常フェライトとオーステナイトの
2相組織を有するステンレス鋼である。この種の材料
は、高温で長時間熱時効を受けると脆化することが知ら
れている。また、中性子照射によっても脆化が進行す
る。一方、オーステナイト組織だけからなる母材は、熱
時効による脆化はほとんど生じない。したがって、脆化
の観点から言うと、溶接部の材料を検査することがより
重要である。よって、長時間運転されたプラントのシュ
ラウド1から、位置決め用突起2と共にすみ肉溶接部4
を切断して劣化診断用供試材とすることが重要である。
ところが、図4に見られるようにすみ肉溶接部の体積は
非常に小さく、強度用試験片の採取は困難である。この
場合には、微小なディスクタイプの試験片を用いて強度
評価を行う方法を適用する。ディスクタイプの試験片を
用いて強度特性を調べる方法は、例えばスモールパンチ
試験法やディスクベンド試験法、またシェアパンチ試験
法などが提案されており、降伏強度や破壊強度,延性−
脆性遷移温度(DBTT)や破壊靭性値等の機械的性質
を推定することが可能である。図4に示すように、すみ
肉溶接部4から微小ディスク試験片6を1枚以上採取す
る。採取した微小ディスク試験片6を用いてスモールパ
ンチ試験法やディスクベンド試験法、またシェアパンチ
試験法により、降伏強度や破壊強度,延性−脆性遷移温
度(DBTT)や破壊靭性値等の機械的性質の推定を行
って、劣化度の診断を行う。
FIG. 4 is a view showing a method of collecting a test piece for strength test from the fillet welded portion 4. The material of the welded portion of a nuclear reactor structure is usually stainless steel having a dual phase structure of ferrite and austenite. It is known that this type of material becomes brittle when subjected to thermal aging at high temperature for a long time. Embrittlement also progresses by neutron irradiation. On the other hand, the base material consisting only of an austenite structure hardly causes embrittlement due to thermal aging. Therefore, in terms of embrittlement, it is more important to inspect the material of the weld. Therefore, from the shroud 1 of the plant that has been operated for a long time, the fillet welded portion 4 together with the positioning protrusion 2 is provided.
It is important to cut into a sample material for deterioration diagnosis.
However, as shown in FIG. 4, the volume of the fillet weld is very small, and it is difficult to collect the strength test piece. In this case, a method of performing strength evaluation using a minute disc type test piece is applied. As a method for examining strength characteristics using a disk type test piece, for example, a small punch test method, a disk bend test method, a shear punch test method, and the like have been proposed. Yield strength, fracture strength, ductility-
It is possible to estimate mechanical properties such as brittle transition temperature (DBTT) and fracture toughness value. As shown in FIG. 4, one or more micro disk test pieces 6 are sampled from the fillet welded portion 4. Mechanical properties such as yield strength, fracture strength, ductility-brittleness transition temperature (DBTT), fracture toughness value, etc. by small punch test method, disk bend test method, and shear punch test method using the collected minute disk test piece 6. And the degree of deterioration is diagnosed.

【0015】図5は、溶接部の材料の劣化を診断するた
めに、すみ肉溶接部4を利用する別の方法を示した図で
ある。この方法では、すみ肉溶接部4から微小引張り試
験片7を切り出し、引張り試験を行って降伏応力,破断
応力,破断のびや絞り等の機械的性質を調べて劣化の診
断を行う。
FIG. 5 is a diagram showing another method of utilizing the fillet weld 4 in order to diagnose deterioration of the material of the weld. In this method, a minute tensile test piece 7 is cut out from the fillet welded portion 4 and a tensile test is performed to examine mechanical properties such as yield stress, breaking stress, breaking stretch and drawing, and to diagnose deterioration.

【0016】図6は、溶接部と母材部との融合点に対応
する境界部の劣化を診断するための方法を示す図であ
る。境界部では溶接部単独や母材単独の場合とは異なっ
た劣化が生じる可能性があり、強度試験によって劣化度
を調べる必要がある。しかし、位置決め用突起2とすみ
肉溶接部4との境界部を利用する場合、すみ肉溶接部4
の体積が小さいことから一般的な強度用試験片は採取で
きない。このときには、境界部試験用微小ディスク試験
片8を、溶接境界部が試験片の中心部に来るように採取
する。境界部試験用微小ディスク試験片8は、図7に示
すように片側が境界部試験用微小ディスク試験片母材側
9、その反対の片側が境界部試験用微小ディスク試験片
溶接部側10になっている。境界部試験用微小ディスク
試験片8を用いて、ディスクの中心部を押し込むタイプ
の試験法であるスモールパンチ試験法かディスクベンド
試験法を適用して、試験片中心部の押し込み試験を実施
する。負荷を増加していく過程のある段階で、境界部試
験用微小ディスク試験片8には、その中心からき裂11
が発生する。このとき、境界部が弱ければき裂11は境
界部を伝播する。このときのき裂発生荷重や破断荷重あ
るいは破壊吸収エネルギ等の機械的性質を調べることに
よって、劣化度を診断する。
FIG. 6 is a diagram showing a method for diagnosing the deterioration of the boundary portion corresponding to the fusion point between the welded portion and the base metal portion. Deterioration may occur at the boundary, which is different from the case of welds alone or base metal alone, and it is necessary to examine the degree of deterioration by strength tests. However, when the boundary between the positioning projection 2 and the fillet weld 4 is used, the fillet weld 4
Because of the small volume, general strength test pieces cannot be collected. At this time, the micro disk test piece 8 for boundary test is sampled so that the weld boundary comes to the center of the test piece. As shown in FIG. 7, the boundary test micro disk test piece 8 has one side on the boundary test micro disk test piece base material side 9 and the other side on the boundary test micro disk test piece weld side 10 Has become. The indentation test of the center part of the test piece is performed by using the small disk test piece 8 for boundary part test and applying the small punch test method or the disk bend test method which is a test method of pressing the center part of the disk. At some stage in the process of increasing the load, the microdisk test piece for boundary test 8 was cracked from its center by a crack 11
Occurs. At this time, if the boundary is weak, the crack 11 propagates in the boundary. At this time, the degree of deterioration is diagnosed by examining the mechanical properties such as the crack initiation load, the fracture load, the fracture absorbed energy and the like.

【0017】図9は、母材の劣化診断方法を示す図であ
る。炉内構造物母材と同種の材料で製作されている位置
決め用突起2は、比較的大きな体積を有しており、一般
的な形状を有する破壊靭性試験片12を採取できる。図
9に示すように破壊靭性試験片12を採取して破壊靭性
試験を実施し、得られた破壊靭性値から劣化を診断す
る。
FIG. 9 is a diagram showing a method of diagnosing deterioration of a base material. The positioning projection 2 made of the same kind of material as the core material of the furnace has a relatively large volume, and the fracture toughness test piece 12 having a general shape can be sampled. As shown in FIG. 9, a fracture toughness test piece 12 is sampled, a fracture toughness test is performed, and deterioration is diagnosed from the obtained fracture toughness value.

【0018】[0018]

【発明の効果】本発明により、シュラウドの内面にある
位置決め用の突起及びその周囲に存在するすみ肉溶接部
を劣化診断用の供試材として利用することにより、原子
炉内構造物の材料特にその溶接部の材料の劣化を診断す
ることができる。
According to the present invention, by utilizing the positioning projections on the inner surface of the shroud and the fillet welds existing around the positioning projections as test materials for deterioration diagnosis, the material of the reactor internal structure, It is possible to diagnose deterioration of the material of the welded portion.

【図面の簡単な説明】[Brief description of the drawings]

【図1】劣化診断用の供試材として採取される構造物の
部位を示す説明図。
FIG. 1 is an explanatory view showing a portion of a structure taken as a test material for deterioration diagnosis.

【図2】劣化診断用の供試材として採取される部位を詳
細に示した斜視図。
FIG. 2 is a perspective view showing in detail a portion taken as a test material for deterioration diagnosis.

【図3】劣化診断用の供試材となる部位を採取した様子
を示す斜視図。
FIG. 3 is a perspective view showing a state in which a portion serving as a test material for deterioration diagnosis is sampled.

【図4】劣化診断用供試材の溶接部位からディスク型の
試験片を採取する位置を示す説明図。
FIG. 4 is an explanatory view showing a position where a disk-shaped test piece is sampled from a welded portion of a deterioration diagnosis test material.

【図5】劣化診断用供試材の溶接部位から引張り試験片
を採取する位置を示す説明図。
FIG. 5 is an explanatory view showing a position where a tensile test piece is sampled from a welded portion of a test material for deterioration diagnosis.

【図6】劣化診断用供試材の溶接部位と母材部の境界部
を対象に、ディスク型の試験片を採取する採取位置を示
す説明図。
FIG. 6 is an explanatory view showing a sampling position at which a disc-shaped test piece is sampled, targeting a boundary portion between a welded portion and a base material portion of a test material for deterioration diagnosis.

【図7】劣化診断用供試材の溶接部位と母材部の境界部
から採取したディスク型試験片の試験前の様子を示す説
明図。
FIG. 7 is an explanatory diagram showing a state before a test of a disk-shaped test piece taken from a boundary portion between a welded portion and a base material portion of a test material for deterioration diagnosis.

【図8】劣化診断用供試材の溶接部位と母材部の境界部
から採取したディスク型試験片の試験後の様子を示す説
明図。
FIG. 8 is an explanatory diagram showing a state after the test of the disk-shaped test piece taken from the boundary portion between the welded portion and the base metal portion of the deterioration diagnosis test material.

【図9】劣化診断用供試材の母材部から、破壊靭性試験
用の試験片を採取する採取位置を示す説明図。
FIG. 9 is an explanatory view showing a sampling position for sampling a test piece for a fracture toughness test from a base material portion of a test material for deterioration diagnosis.

【符号の説明】[Explanation of symbols]

1…シュラウド、2…位置決め用突起、3…シュラウド
内壁、4…すみ肉溶接部、5…突起切断痕、6…微小デ
ィスク試験片、7…微小引張り試験片、8…境界部試験
用微小ディスク試験片、9…境界部試験用微小ディスク
試験片母材側、10…境界部試験用微小ディスク試験片
溶接部側、11…き裂、12…破壊靭性試験片。
DESCRIPTION OF SYMBOLS 1 ... Shroud, 2 ... Positioning protrusion, 3 ... Shroud inner wall, 4 ... Fillet weld, 5 ... Protrusion cutting mark, 6 ... Micro disk test piece, 7 ... Micro tensile test piece, 8 ... Boundary test micro disk Test piece, 9 ... Micro disk test piece base material side for boundary test, 10 ... Micro disk test piece weld side for boundary test, 11 ... Crack, 12 ... Fracture toughness test piece.

フロントページの続き (72)発明者 大城戸 忍 茨城県土浦市神立町502番地 株式会社日 立製作所機械研究所内 (72)発明者 服部 成雄 茨城県日立市幸町三丁目1番1号 株式会 社日立製作所日立工場内 (72)発明者 加藤 隆彦 茨城県日立市幸町三丁目1番1号 株式会 社日立製作所日立工場内Front Page Continuation (72) Inventor Shinobu Ogido 502 Jinritsucho, Tsuchiura-shi, Ibaraki Machinery Research Laboratory, Hiritsu Seisakusho Co., Ltd. (72) Inventor Shigeo Hattori 3-1-1 Sachimachi, Hitachi-shi, Ibaraki Stock Company Hitachi, Ltd., Hitachi Plant (72) Inventor, Takahiko Kato, 3-1-1, Saiwaicho, Hitachi City, Ibaraki Prefecture Hitachi Ltd., Hitachi Plant

Claims (6)

【特許請求の範囲】[Claims] 【請求項1】原子炉内構造物であるシュラウドの内面に
ある位置決め用の突起の周囲に存在するすみ肉溶接部を
劣化診断用材料として利用することを特徴とする溶接部
の劣化診断方法。
1. A method for diagnosing deterioration of a welded part, wherein a fillet weld existing around a positioning projection on an inner surface of a shroud which is an internal structure of a nuclear reactor is used as a material for diagnosing deterioration.
【請求項2】請求項1の前記すみ肉溶接部から、パンチ
タイプの強度試験が行える微小ディスクを1個以上を切
断して、前記微小ディスクの強度試験によって溶接部の
脆性,延性,靭性,疲労強度,耐応力腐食割れ性を診断
する劣化診断方法。
2. A brittleness, ductility, and toughness of the welded part are obtained by cutting one or more micro disks capable of punch-type strength test from the fillet welded part according to claim 1 and conducting a strength test of the micro disk. Deterioration diagnosis method for diagnosing fatigue strength and stress corrosion cracking resistance.
【請求項3】請求項1の前記すみ肉溶接部から、微小引
張り試験片を切り出し、この試験片を用いて引張り試験
を行うことによって溶接部の降伏強度,破壊強度,延
性,疲労強度を調べる溶接部の劣化診断方法。
3. A microtensile test piece is cut out from the fillet welded portion of claim 1, and a tensile test is performed using this test piece to examine the yield strength, fracture strength, ductility, and fatigue strength of the welded portion. Deterioration diagnosis method for welds.
【請求項4】請求項1の前記シュラウドの位置決め用突
起のすみ肉溶接部で、パンチタイプの強度試験を行う微
小ディスクの中心に溶接部と母材の境界部が位置するよ
うに採取し、前記微小ディスクの強度試験から溶接境界
部の強度を調べる劣化診断方法。
4. The fillet weld of the positioning projection of the shroud according to claim 1, so that the boundary between the weld and the base metal is located at the center of the micro disk for punch-type strength test. A deterioration diagnosis method for checking the strength of a weld boundary portion from the strength test of the minute disk.
【請求項5】請求項1の前記シュラウドの位置決め用突
起で、溶接部以外の部分からも請求項2と請求項3ある
いは破壊靭性試験の行える切欠き入りの角柱状あるいは
円柱状の試験片を切り出して、母材の強度診断を行う劣
化診断方法。
5. The shroud positioning projection according to claim 1, wherein a notched prismatic or cylindrical test piece capable of performing a fracture toughness test from claim 2 and claim 3 or a portion other than a welded portion is used. Deterioration diagnosis method to cut out and perform strength diagnosis of the base material.
【請求項6】請求項1の前記シュラウドの位置決め用の
突起及びその周囲のすみ肉溶接部の材料を用いて、硬さ
試験,金属組織の観察,転位構造の観察,超音波試験,
電気化学的試験,EPR試験,パルスボルタメトリー試
験,磁気特性測定試験等の材料特性評価試験して原子炉
内構造物の材料劣化度を診断する方法。
6. A hardness test, an observation of a metal structure, an observation of a dislocation structure, an ultrasonic test using a material for a positioning protrusion of the shroud and a fillet weld portion around the shroud according to claim 1.
A method of diagnosing the degree of material deterioration of the reactor internal structure by conducting material property evaluation tests such as electrochemical tests, EPR tests, pulse voltammetry tests, and magnetic property measurement tests.
JP8000479A 1996-01-08 1996-01-08 Method for diagnosing degradation of reactor structure Pending JPH09189790A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP8000479A JPH09189790A (en) 1996-01-08 1996-01-08 Method for diagnosing degradation of reactor structure

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP8000479A JPH09189790A (en) 1996-01-08 1996-01-08 Method for diagnosing degradation of reactor structure

Publications (1)

Publication Number Publication Date
JPH09189790A true JPH09189790A (en) 1997-07-22

Family

ID=11474916

Family Applications (1)

Application Number Title Priority Date Filing Date
JP8000479A Pending JPH09189790A (en) 1996-01-08 1996-01-08 Method for diagnosing degradation of reactor structure

Country Status (1)

Country Link
JP (1) JPH09189790A (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2003329790A (en) * 2002-05-08 2003-11-19 Toshiba Corp Material degradation evaluation method for nuclear power plant structure
JP2012173173A (en) * 2011-02-22 2012-09-10 Toshiba Corp Tension and fracture toughness test method
JP2014197035A (en) * 2014-07-22 2014-10-16 株式会社東芝 Fracture toughness testing method

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2003329790A (en) * 2002-05-08 2003-11-19 Toshiba Corp Material degradation evaluation method for nuclear power plant structure
JP2012173173A (en) * 2011-02-22 2012-09-10 Toshiba Corp Tension and fracture toughness test method
JP2014197035A (en) * 2014-07-22 2014-10-16 株式会社東芝 Fracture toughness testing method

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