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JAEA Reports

High-Cycle Fatigue Properties of Structural Materials for FBR (2)High-Cycle Fatigue tests of 316FR Steel at Elevated Temperature[Interim Report]

Odaka, Susumu; Kato, Shoichi; Yoshida, Eiichi; Ishigami, Katsuo*

JNC TN9400 2005-021, 37 Pages, 2005/05

JNC-TN9400-2005-021.pdf:2.66MB

In liquid cooled Fast Breeder Reactors (LMFBRs), temperature fluctuation due to fluid mixing induce high-cycle fatigue damages on structural materials. Such cyclic thermal stress is estimated to repeat approximately 10$$^{8}$$ to 10$$^{9}$$ cycles during a plant. Therefore, it is essential to investigate the fatigue property in a very-high cycle region. In the study, high-cycle fatigue tests at 550$$^{circ}$$C to 650$$^{circ}$$C under strain control were carried out on the 316FR steel. The intermediate result obtained until now is shown below. (1)New examination technology was developed, high temperature fatigue tests were performed on the repetition frequency of 10-60Hz, and the high cycle fatigue fracture data of 1.0$$^{7}$$ cycle regions was obtained. (2)The high-cycle fatigue strength of 1.0$$^{7}$$ cycle regions was longer than the life calculated by simple extrapolation from average fatigue failure formula of material strength standard (DDS) for a design. Moreover, these lives were conservative also in comparison with the fatigue failure formula by KOM-MSS WG. (3)Although the significant influence of the frequency on a fatigue life was not observed in the range from 0.1 Hz to 60Hz, the influence of temperature was recognized.(4)The fish eye fracture was observed in the high-cycle fatigue failure test specimen of 1.0$$^{7}$$ cycle regions.

JAEA Reports

Material test data of 316FR Steel (IX)

Odaka, Susumu; Kato, Shoichi; Yoshida, Eiichi; Kawakami, Tomohiro*; Suzuki, Takaichi*; Kawashima, Seiichi*; Ishigami, Katsuo*

JNC TN9450 2005-001, 196 Pages, 2005/03

JNC-TN9450-2005-001.pdf:6.7MB

Material test of 316FR steel, which was used for structure material of fast breeder reactor (FBR) has been preformed in New Technology Development Group. In this report, the result of test obtained up to this time was collected. Many valuable data that long time test more than 40000 hours including sodium environment test data in this report will be use for material examination of FBR in the future.Contents of the data sheet are as follows; (1) Material: 316FR Steel, (2) Test environment: In air,in sodium, (3) Test emperature: Room temperature to 800, (4) Test method: According to JIS and FBR metallic materials test manual (Revised edition), (5) Number of data:Tensile tests 234, Creep tests 408, Fatigue tests 201, Creep-fatigue tests 47, Relaxation tests 6,Total 896 This report consists of the printouts fromthe structural material data processing system, SMAT.

JAEA Reports

FBR Metallic Materials Test Manual(English Version) (Manual)

Odaka, Susumu; Kato, Shoichi; Yoshida, Eiichi

JNC TN9520 2003-001, 118 Pages, 2003/06

JNC-TN9520-2003-001.pdf:7.94MB

For the development of the fast breeder reactor, this manual describes the method of in-air and in-sodium material tests and the method of organization the data. This Previous manual has revised in accordance with the revision of Japanese Industrial Standard (JIS)and the conversion to the international unit. The test methods of domestic committees such as the VAMAS (Versailles Prject on Advanced Materials and Standards) workshop were also referred. The material test technologies accumulated in this group until now were also incorporated. This English version was prepared in order to provide more engineers with the FBR metallic materials test manual.

JAEA Reports

Material test data of 2.25Cr-1Mo Steel and Mod.9Cr-1Mo Steel (Set of data)

Odaka, Susumu; ; Yoshida, Eiichi; *; *; *; *

JNC TN9450 2003-004, 147 Pages, 2003/06

JNC-TN9450-2003-004.pdf:6.67MB

Matenal tests of 2.25Cr-1Mo Steel and Mod. 9Cr-1Mo Steel, which were used for structure material of fast breeder reactor (FBR) have been preformed in New Technology Development Group. In this report, the result of test obtained up to this time was collected. Many valuable data from long time test for more than 100000 hours including sodium environment test data in this report will be used for material examination of FBR in the future. It creates, in order for for ASME Code Committee to report this time. Contents of the data sheet are as follows; (1)Material: 2.25Cr-1Mo Steel and Mod.9Cr-1Mo Stee1 (2)Test environment: In air (3)Kind: Base metal (4)Heat treatment: Normalizing-tempering and stress relieving (5)Test temperature: 2.25Cr-1Mo Steel From 220 to 800deg Mod.9Cr-1Mo steel From 290 to 800deg (6)Test method: According to JIS and FBR Metallic Materials Test Manual (English version) (5)Number of data : 2.25Cr-1Mo Steel Creep tests 132 Fatigue tests 182 Creep-fatigue tests 66 Mod 9Cr-1Mo steel Creep tests 185 Fatigue tests 192 Creep-fatigue tests 27 Total 784 This report consists of the printouts from (the structural material data processing system,SMAT).

JAEA Reports

Material test data of SUS304 steel (III)

Odaka, Susumu; Kato, Shoichi; Kawakami, Tomohiro*; Suzuki, Takaichi*; Takamori, Yuji*

JNC TN9450 2003-002, 962 Pages, 2003/03

JNC-TN9450-2003-002.pdf:35.27MB

Material test of SUS304 steel, which was used for structure material of fast breeder reactor (FBR) has been preformed in New Technology Development Group. In this report, the result of test obtained up to this time was collected. Many valuable data that long time test more than 100000 hours including sodium environment test data in this report will be use for material examination of FBR in the future. Contents of the data sheet are as follows; (1) Material: SUS304 Steel, (2) Test environment: In air, in sodium, (3) Test temperature: Room temperature to 800$$^{circ}$$C, (4) Test method: According to JIS and FBR metallic materials test manual (revised edition), (5) Number of data : Tensile tests 1,185 Creep tests 1,044 Fatigue tests 1,037 Creep-fatigue tests 263 Total 3,529 This report consists of the printouts from -the structural material data Processing system, SMAT-.

Patent

ひずみ制御型超高サイクル疲労試験方法および疲労試験装置

小高 進; 吉田 英一; 加藤 章一

小嶺 徳晃*; 石上 勝夫*

JP, 2005-087548  Patent licensing information  Patent publication (In Japanese)

【課題】超高サイクル疲労試験を短時間で実施することができるひずみ制御型超高サイクル疲労試験方法および疲労試験装置を提供する。 【解決手段】試験条件として、少なくとも試験片1の標点間の全ひずみ範囲Δεtおよび制御速度Fを設定する第1工程と、試験片の標点間の全ひずみ範囲の設定値に相当する非接触式変位計20の目標制御範囲ΔLTを求める第2工程と、制御速度Fで且つ非接触式変位計の計測値の振幅が上記目標制御範囲ΔLTで一定となるように試験片に繰返し荷重を作用させて、非接触式変位計によるひずみ制御下で疲労試験を行う第3工程とを有する。第2工程では、接触式ひずみ計10が追従可能なひずみ速度で試験片に繰返し荷重を作用させたときの接触式ひずみ計の計測値と、非接触式変位計の計測値とを取得し、それら計測値から両者の相関関係を求めて、当該相関関係に基づいて、上記目標制御範囲ΔLTを求める。

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