JPH0114532B2 - - Google Patents
Info
- Publication number
- JPH0114532B2 JPH0114532B2 JP55095663A JP9566380A JPH0114532B2 JP H0114532 B2 JPH0114532 B2 JP H0114532B2 JP 55095663 A JP55095663 A JP 55095663A JP 9566380 A JP9566380 A JP 9566380A JP H0114532 B2 JPH0114532 B2 JP H0114532B2
- Authority
- JP
- Japan
- Prior art keywords
- sample
- temperature
- autoclave
- nodular corrosion
- corrosion
- 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.)
- Expired
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- 238000005260 corrosion Methods 0.000 claims description 29
- 230000007797 corrosion Effects 0.000 claims description 29
- 238000012360 testing method Methods 0.000 claims description 18
- 229910001093 Zr alloy Inorganic materials 0.000 claims description 17
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Chemical compound O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 16
- 229910052739 hydrogen Inorganic materials 0.000 claims description 13
- 239000001257 hydrogen Substances 0.000 claims description 13
- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 claims description 12
- 230000007246 mechanism Effects 0.000 claims description 8
- 238000010998 test method Methods 0.000 claims description 5
- 230000035945 sensitivity Effects 0.000 claims 1
- 239000000446 fuel Substances 0.000 description 6
- KDLHZDBZIXYQEI-UHFFFAOYSA-N Palladium Chemical compound [Pd] KDLHZDBZIXYQEI-UHFFFAOYSA-N 0.000 description 4
- 238000005253 cladding Methods 0.000 description 3
- 238000000034 method Methods 0.000 description 3
- 230000000712 assembly Effects 0.000 description 2
- 238000000429 assembly Methods 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 229910001055 inconels 600 Inorganic materials 0.000 description 2
- 238000001000 micrograph Methods 0.000 description 2
- 229910052763 palladium Inorganic materials 0.000 description 2
- 230000004584 weight gain Effects 0.000 description 2
- 235000019786 weight gain Nutrition 0.000 description 2
- 241000519995 Stachys sylvatica Species 0.000 description 1
- 230000002159 abnormal effect Effects 0.000 description 1
- 229910045601 alloy Inorganic materials 0.000 description 1
- 239000000956 alloy Substances 0.000 description 1
- 230000007423 decrease Effects 0.000 description 1
- 238000007872 degassing Methods 0.000 description 1
- 239000008367 deionised water Substances 0.000 description 1
- 229910021641 deionized water Inorganic materials 0.000 description 1
- 239000012153 distilled water Substances 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000010438 heat treatment Methods 0.000 description 1
- 150000002431 hydrogen Chemical class 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 229910052751 metal Inorganic materials 0.000 description 1
- 239000002184 metal Substances 0.000 description 1
- 239000003758 nuclear fuel Substances 0.000 description 1
- 125000006850 spacer group Chemical group 0.000 description 1
- 239000010935 stainless steel Substances 0.000 description 1
- 229910001220 stainless steel Inorganic materials 0.000 description 1
Classifications
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
- G01N17/00—Investigating resistance of materials to the weather, to corrosion, or to light
Landscapes
- Life Sciences & Earth Sciences (AREA)
- Biodiversity & Conservation Biology (AREA)
- Ecology (AREA)
- Environmental & Geological Engineering (AREA)
- Environmental Sciences (AREA)
- Physics & Mathematics (AREA)
- Health & Medical Sciences (AREA)
- Chemical & Material Sciences (AREA)
- Analytical Chemistry (AREA)
- Biochemistry (AREA)
- General Health & Medical Sciences (AREA)
- General Physics & Mathematics (AREA)
- Immunology (AREA)
- Pathology (AREA)
- Testing Resistance To Weather, Investigating Materials By Mechanical Methods (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
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、たとえば核燃料集合体をケーシング
する為に使用されているチヤンネルボツクス、被
覆管等に利用されるジルコニウム合金のノデユラ
ーコロージヨン感受性試験方法およびその装置に
関するものである。Detailed Description of the Invention [Objective of the Invention] (Industrial Application Field) The present invention is directed to the production of zirconium alloy nodes used for channel boxes, cladding tubes, etc. used for casing nuclear fuel assemblies, for example. This invention relates to a method and apparatus for testing susceptibility to yular corrosion.
（従来の技術）
軽水炉に使用される燃料は通常数十本の燃料棒
を並行に束状に組立てた集合体の状態で原子炉に
装荷される。燃料棒は各々上部タイプレート及び
下部タイプレートに挿入され、さらにスペーサあ
るいはスプリング等で相互の関係が維持され、上
部より眺めると網目状に規則正しく並んでいる。
チヤンネルボツクスとしては、燃料集合体のケー
シングとして通常使用されているジルコニウム合
金であるジルカロイ−４等を用いる事が多い。(Prior Art) Fuel used in a light water reactor is normally loaded into the reactor in the form of an assembly of dozens of fuel rods assembled in parallel in a bundle. The fuel rods are inserted into the upper tie plate and the lower tie plate, respectively, and are maintained in mutual relationship by spacers or springs, and are regularly arranged in a mesh shape when viewed from above.
The channel box is often made of Zircaloy-4, which is a zirconium alloy commonly used as a casing for fuel assemblies.
これらのジルコニウム合金は高温水の雰囲気に
おいて極めて耐食性に優れている事はよく知られ
ているものの、原子炉内で用いた場合には、ノデ
ユラーコロージヨンにより白色酸化物を生成する
場合があつた。 Although it is well known that these zirconium alloys have excellent corrosion resistance in a high-temperature water atmosphere, when used in a nuclear reactor, white oxides may be produced due to nodular corrosion. .
原子炉の安全性、信頼性を高めるには、原子炉
実機を用いる事なく、各部材のノデユラーコロー
ジヨンの発生し易すさ（ノデユラーコロージヨン
感受性）を試験する方法の確立が望まれていた。 In order to improve the safety and reliability of nuclear reactors, it is desirable to establish a method to test the susceptibility to nodular corrosion of each member (nodular corrosion susceptibility) without using an actual reactor. Ta.
（発明が解決しようとする問題点）
本発明の目的は原子炉稼動中にチヤンネルボツ
クス、燃料被覆管等を構成するジルコニウム合金
表面にノデユラー性白色異常酸化物が発生しない
ことを炉外で材料のうちに簡単にかつ短時間で検
査し得る試験方法及びその試験装置を提供するこ
とにある。(Problems to be Solved by the Invention) The purpose of the present invention is to prevent the generation of nodular white abnormal oxides on the surfaces of zirconium alloys constituting channel boxes, fuel cladding tubes, etc. during nuclear reactor operation. The purpose of the present invention is to provide a test method and test device that can be easily and quickly inspected.
［発明の構成］
（問題点を解決するための手段）
本発明はジルコニウム合金のノデユラーコロー
ジヨンの感受性を判定するに際し、試料を温度
475〜525℃、圧力90〜120Kg／cm2の水蒸気中に５
時間以上放置した後、試料表面を観察して判定す
るジルコニウム合金のノデユラーコロージヨン感
受性試験方法、およびジルコニウム合金試料を内
部に保持可能とした耐熱圧力容器である試料室
と、この試料室内に生ずる水素を放出させる水素
放出機構と、前記試料室にバルブを介して高温、
高圧蒸気を提供する蒸気発生室とを具備したこと
を特徴とするジルコニウム合金のノデユラーコロ
ージヨン感受性試験装置を提供することにある。[Structure of the Invention] (Means for Solving the Problems) The present invention provides a method for determining the susceptibility of nodular corrosion of a zirconium alloy by subjecting a sample to temperature.
5 in water vapor at 475-525℃ and pressure 90-120Kg/ cm2.
A zirconium alloy nodular corrosion susceptibility test method that determines by observing the surface of a sample after it has been left for a period of time, a sample chamber that is a heat-resistant pressure vessel that can hold a zirconium alloy sample, and a sample chamber that is a heat-resistant pressure vessel that can hold a zirconium alloy sample inside, and A hydrogen release mechanism that releases hydrogen, and a high temperature,
An object of the present invention is to provide a nodular corrosion susceptibility testing apparatus for zirconium alloys, characterized in that it is equipped with a steam generation chamber that provides high-pressure steam.
（作用）
本発明は以上の如き機構を用いることにより、
原子炉の実機を用いる事なく、容易にかつ確実に
ジルコニウム合金のノデユラーコロージヨン感受
性を試験できるものである。(Function) By using the above mechanism, the present invention
The nodular corrosion susceptibility of zirconium alloys can be easily and reliably tested without using an actual nuclear reactor.
本発明において試料室内の温度を475〜525℃と
水蒸気の圧力を90〜120Kg／cm2としたのはこの範
囲内では、原子炉内に対応するノデユラーコロー
ジヨンの発生を効率よく行う事ができ、温度475
℃又は圧力90Kg／cm2未満では、必要なノデユラー
コロージヨンを発生させることができず、又温度
525℃又は圧力120Kg／cm2を超えると必要以上にノ
デユラーコロージヨンが発生し、剥離、落剥して
しまうことがあるためである。 In the present invention, the temperature in the sample chamber is set at 475-525℃ and the water vapor pressure is set at 90-120Kg/ cm2 . Within these ranges, it is possible to efficiently generate nodular corrosion corresponding to the inside of the reactor. Can, temperature 475
℃ or pressure below 90Kg/cm 2 , the necessary nodular corrosion cannot be generated, and the temperature
This is because if the temperature exceeds 525° C. or the pressure exceeds 120 kg/cm 2 , nodular corrosion may occur more than necessary, resulting in peeling and flaking.
また上記の如き温度、水蒸気圧力下で５時間上
放置するのは、５時間未満では原子炉内で発生す
るノデユラーコロージヨンと同等のものが得られ
ない為である。 The reason why the material is left to stand for 5 hours under the above temperature and steam pressure is that if it is less than 5 hours, it will not be possible to obtain a nodular corrosion equivalent to that generated in a nuclear reactor.
なお本発明においては上記の如き試験法を用い
るが、必要に応じ、事前に他の温度、水蒸気圧下
での処理を施すこともできる。 In the present invention, the test method described above is used, but if necessary, treatment at other temperatures and water vapor pressures can also be performed in advance.
（実施例）
以下、本発明の一実施例と図面を参照して詳細
に説明する。第１図に本発明に係る試験装置の概
要を示す。図においてオートクレーブ１は蒸気発
生用、オートクレーブ２はノデユラーコロージヨ
ン試験用、即ち試験室である。(Example) Hereinafter, an example of the present invention will be described in detail with reference to the drawings. FIG. 1 shows an outline of a test device according to the present invention. In the figure, autoclave 1 is for steam generation, and autoclave 2 is for nodular corrosion testing, that is, a test chamber.
オートクレーブ１とオートクレーブ２は夫々バ
ルブ３，４を介して連結しており、また圧力計
５，６により単独に圧力を計測できる。オートク
レーブ１は常用使用温度400℃、常用使用圧力150
Kg／cm2、内容積５、胴体はSuS316製である。
オートクレーブ２は試料室であるが、常用使用温
度500℃、圧力110Kg／cm2、内容積５、胴体は
SuS316にインコネル600（商品名）を内張りし、
更に蓋板もインコネル600（商品名）を使用して、
高温高圧にそなえている。 Autoclave 1 and autoclave 2 are connected via valves 3 and 4, respectively, and pressure can be measured independently using pressure gauges 5 and 6. Autoclave 1 has a normal operating temperature of 400℃ and a normal operating pressure of 150℃.
Kg/cm 2 , internal volume 5, and the fuselage is made of SuS316.
Autoclave 2 is a sample chamber, with a regular operating temperature of 500℃, a pressure of 110Kg/cm 2 , an internal volume of 5, and a body of
SuS316 is lined with Inconel 600 (product name),
Furthermore, the lid plate is also made of Inconel 600 (product name).
Equipped with high temperature and high pressure.
オートクレーブ２は常に一定の水蒸気圧をオー
トクレーブ１から受けることができる。 The autoclave 2 can always receive constant water vapor pressure from the autoclave 1.
また、７，８はオートクレーブ内温度を計測す
る為に挿入された温度計であり、９，１０はオー
トクレーブを昇温する際、脱気をおこなう脱気機
構であり、１１，１２は安全弁である。 In addition, 7 and 8 are thermometers inserted to measure the temperature inside the autoclave, 9 and 10 are deaeration mechanisms that perform deaeration when heating the autoclave, and 11 and 12 are safety valves. .
さらに１３はバルブ、１４は水素放出機構であ
る。 Furthermore, 13 is a valve, and 14 is a hydrogen release mechanism.
次に上記装置の動作について説明する。試験関
始にあたつてバルブ１５，１６，１７，１８およ
びポンプ１９によつてオートクレーブ内は排気さ
れる。 Next, the operation of the above device will be explained. At the beginning of the test, the inside of the autoclave is evacuated by valves 15, 16, 17, 18 and pump 19.
水蒸気源である水は脱イオン水及び蒸留水をオ
ートクレーブ１のみに注入しバルブ３，４は閉じ
たままオートクレーブ１の昇温を開始する。脱気
は例えば150℃から開始し、オートクレーブ１の
温度をコントロールすることによりオートクレー
ブ１の水蒸気圧を一定に保持する。例えば250℃
では飽和水蒸気圧41Kg／cm2、300℃で88Kg／cm2、
315℃で168Kg／cm2である。 As the water vapor source, deionized water and distilled water are injected only into the autoclave 1, and the temperature of the autoclave 1 is started to increase while the valves 3 and 4 are closed. Degassing starts at, for example, 150° C., and the water vapor pressure in the autoclave 1 is kept constant by controlling the temperature of the autoclave 1. For example 250℃
Then, the saturated water vapor pressure is 41Kg/cm 2 , 88Kg/cm 2 at 300℃,
It is 168Kg/ cm2 at 315℃.
オートクレーブ２は試料をステンレスあるいは
Ni基合金のワイヤにて吊下し、昇温初期には真
空ポンプ１９で排気をしながら昇温をし、オート
クレーブ２が200℃を超えた時点でバルブ３，４
により徐々に水蒸気をオートクレーブ２に供給、
複数個の蒸気放出の後、オートクレーブ２を更に
昇温し500℃110Kg／cm2に設定することにより腐蝕
試験を関始した。 Autoclave 2 uses stainless steel or
Suspended by a Ni-based alloy wire, the temperature is raised while evacuating with a vacuum pump 19 at the initial stage of temperature rise, and when the temperature of the autoclave 2 exceeds 200°C, valves 3 and 4
gradually supply steam to autoclave 2,
After releasing several steams, the temperature of autoclave 2 was further raised to 500° C. and 110 kg/cm 2 to begin a corrosion test.
試料はジルコニウム合金より成る例えばチヤン
ネルボツクスと同様な方法で加工熱処理をうけた
小誌験片あるいはまたチヤンネルボツクスの端か
ら切り出した小試験片の試料で、これを例えば温
度475〜525℃、圧力90〜120Kg／cm2、保持された
高温高圧水蒸気のオートクレーブ内に例えば５〜
25時間保持した後、試料を観察してノデユラーコ
ロージヨン感受性を判定する。第２図はジルカロ
イ−４の試料を温度500℃、圧力105Kg／cm2で５時
間放置した際の上記試験により得られた試料の50
倍の顕微鏡写真でａは試料表面に直径0.6mm程度
のノデユラーコロージヨンが発生し肉眼で白色斑
点が確認された試料、ｂは試料としてZr−２％
Nbを用い、他は同様の試験を行つたものであり、
ノデユラーコロージヨンが発生しなかつた試料で
ある。また、上記高温高圧水蒸気試験を行なつた
場合の試料の重量増を第３図に示す。なお図中横
軸に腐蝕時間、縦軸に腐蝕増量をとり、曲線ａは
第２図ａに対応し、ノデユラーコロージヨンが発
生したものであり、10時間を超えてから剥落が生
じ増量の測定が困難で記載していない。曲線ｂは
第２図ｂに対応し前述の５時間の試験ではノデユ
ラーコロージヨンが発生せず、さらに25時間、74
時間後でもノデユラーの発生はなかつた。この結
果から明らかな如く本発明によればノデユラーコ
ロージヨンの感受性判断が可能となることが確認
されたことになる。なお、上記加速試験でノデユ
ラーコロージヨンが発生した試料を更に長時間、
上記高温高圧水蒸気に保持させるとノデユラーコ
ロージヨンは集合し極端なものは盛り上り剥落減
肉した。 The sample is a small specimen made of zirconium alloy that has been heat-treated in the same manner as a channel box, or a small specimen cut from the edge of a channel box. ~120Kg/cm 2 , for example, 5 ~
After holding for 25 hours, the samples are observed to determine susceptibility to nodular corrosion. Figure 2 shows the results of the above test when a sample of Zircaloy-4 was left at a temperature of 500℃ and a pressure of 105Kg/ cm2 for 5 hours.
In the micrographs magnified, a shows a sample in which nodular corrosion with a diameter of about 0.6 mm has occurred on the sample surface and white spots are visible to the naked eye, and b shows a sample containing Zr-2%.
Nb was used, but other similar tests were conducted,
This is a sample in which nodular corrosion did not occur. Further, FIG. 3 shows the weight increase of the sample when the above-mentioned high-temperature, high-pressure steam test was conducted. In the figure, the horizontal axis shows the corrosion time, and the vertical axis shows the corrosion weight gain. Curve a corresponds to Figure 2 a, and indicates that nodular corrosion has occurred, and flaking occurs after 10 hours, resulting in weight gain. Difficult to measure and not listed. Curve b corresponds to FIG.
Even after hours, there was no occurrence of nodules. As is clear from these results, it has been confirmed that the present invention makes it possible to determine the susceptibility of nodular corrosion. In addition, the sample in which nodular corrosion occurred in the above accelerated test was subjected to an even longer test.
When kept in the above-mentioned high-temperature, high-pressure steam, the nodular corrosions aggregated, and in extreme cases they bulged, peeled off, and thinned.
この時、ジルコニウム合金と水蒸気の反応は
Zr＋2H2O＝ZrO2＋2H2
でZrが酸化するにしたがい圧力計６の圧力は不
変のまま水蒸気の量が減少し水素の量が増加す
る。また本発明に係る試験装置でオートクレーブ
を蒸気発生室と試料室とを分離したのは試料の表
面積・腐蝕の程度により消費される水蒸気の量が
異なり常に一定の水蒸気を維持できない為に試験
結果が大幅にばらつくことを防止したものであ
る。 At this time, the reaction between the zirconium alloy and water vapor is Zr + 2H 2 O = ZrO 2 + 2H 2 , and as Zr oxidizes, the amount of water vapor decreases and the amount of hydrogen increases while the pressure on the pressure gauge 6 remains unchanged. In addition, the reason why the autoclave is separated into the steam generation chamber and the sample chamber in the test apparatus according to the present invention is because the amount of water vapor consumed varies depending on the surface area of the sample and the degree of corrosion, and it is not possible to maintain a constant amount of water vapor at all times. This prevents large variations.
更にオートクレーブ２には、バルブ１３を介し
て水素放出機構１４が設けてあり、上記反応によ
り発生した水素と例えばパラジウム塊により水素
のみを外部に放出している。水素放出機構はパラ
ジウム塊のみによらず例えば水素ゲツター、ある
いは水素所蔵金属を使用して水素を捕獲しても良
い。 Further, the autoclave 2 is provided with a hydrogen release mechanism 14 via a valve 13, which releases only the hydrogen generated by the above reaction and hydrogen from, for example, a palladium block to the outside. The hydrogen release mechanism does not rely solely on the palladium ingot, but may also capture hydrogen using, for example, a hydrogen getter or a hydrogen-storing metal.
［発明の効果］
チヤンネルボツクスあるいは燃料被覆管は高価
なジルコニウム合金を使用しており、また更に原
子炉炉心という特殊な場所に運んで使用されるも
のである。したがつて本発明によるノデユラーコ
ロージヨンの簡単な感受性試験を炉外で短時間に
行なえることは経済面、安全の面から著しい効果
がある。[Effects of the Invention] The channel box or fuel cladding tube uses an expensive zirconium alloy, and is further transported to a special location such as the nuclear reactor core for use. Therefore, the ability to carry out a simple susceptibility test for nodular collage according to the present invention outside the furnace in a short time has significant economic and safety benefits.
第１図は本発明に係る試験装置の概略構成図、
第２図ａ，ｂは、本発明に係る試験方法により得
られた試料の顕微鏡写真、第３図は試料の腐蝕増
量を示す図である。
１……オートクレーブ（蒸気発生室）、２……
オートクレーブ（試料室）、３，４……バルブ、
５，６……圧力計、１４……水素放出機構。
FIG. 1 is a schematic configuration diagram of a test device according to the present invention,
FIGS. 2a and 2b are micrographs of a sample obtained by the test method according to the present invention, and FIG. 3 is a diagram showing the corrosion weight increase of the sample. 1... Autoclave (steam generation chamber), 2...
Autoclave (sample chamber), 3, 4... valve,
5, 6...Pressure gauge, 14...Hydrogen release mechanism.
Claims (1)
の感受性を判定するに際し、試料を温度475〜525
℃、圧力90〜120Kg／cm2の水蒸気中に５時間以上
放置した後、試料表面を観察して判定するジルコ
ニウム合金のノデユラーコロージヨン感受性試験
方法。 ２ ジルコニウム合金試料の保持部を内部に有す
る耐熱圧力容器である試料室と、この試料室内に
生ずる水素を放出させる水素放出機構と、前記試
料室にバルブを介して高温、高圧蒸気を供給する
蒸気発生室とを具備したことを特徴とするジルコ
ニウム合金のノデユラーコロージヨンの感受性試
験装置。[Claims] 1. When determining the sensitivity of nodular corrosion of zirconium alloy, a sample is heated to a temperature of 475 to 525.
A nodular corrosion susceptibility test method for zirconium alloys, in which the sample surface is observed and determined after being left in water vapor at a temperature of 90 to 120 Kg/cm 2 for 5 hours or more. 2. A sample chamber which is a heat-resistant pressure vessel having a zirconium alloy sample holding part therein, a hydrogen release mechanism for releasing hydrogen generated in this sample chamber, and a steam supplying high-temperature, high-pressure steam to the sample chamber via a valve. A susceptibility testing device for nodular corrosion of zirconium alloy, characterized in that it is equipped with a generation chamber.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP9566380A JPS5720644A (en) | 1980-07-15 | 1980-07-15 | Method and device for testing nodular corrosion sensitivity of zirconium alloy |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP9566380A JPS5720644A (en) | 1980-07-15 | 1980-07-15 | Method and device for testing nodular corrosion sensitivity of zirconium alloy |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS5720644A JPS5720644A (en) | 1982-02-03 |
| JPH0114532B2 true JPH0114532B2 (en) | 1989-03-13 |
Family
ID=14143728
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP9566380A Granted JPS5720644A (en) | 1980-07-15 | 1980-07-15 | Method and device for testing nodular corrosion sensitivity of zirconium alloy |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS5720644A (en) |
Families Citing this family (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB2132345B (en) * | 1982-12-15 | 1986-07-30 | Gen Electric | Method of determining corrosion properties of zirconium alloys |
| JPS59170767A (en) * | 1983-03-17 | 1984-09-27 | Toshiba Corp | Method for testing sensitivity of hafnium and hafnium alloy to nodular corrosion |
| JPS60350A (en) * | 1983-06-17 | 1985-01-05 | Ngk Insulators Ltd | Testing method of ceramic |
| US5991352A (en) * | 1998-03-30 | 1999-11-23 | General Electric Company | Method for determining corrosion susceptibility of nuclear fuel cladding to nodular corrosion |
| US6949857B2 (en) | 2003-03-14 | 2005-09-27 | Visteon Global Technologies, Inc. | Stator of a rotary electric machine having stacked core teeth |
-
1980
- 1980-07-15 JP JP9566380A patent/JPS5720644A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS5720644A (en) | 1982-02-03 |
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