Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
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
to 10
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
C to 650C 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
cycle regions was obtained. (2)The high-cycle fatigue strength of 1.0 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 cycle regions.
Odaka, Susumu; Kato, Shoichi; Yoshida, Eiichi; Kawakami, Tomohiro*; Suzuki, Takaichi*; Kawashima, Seiichi*; Ishigami, Katsuo*
JNC TN9450 2005-001, 196 Pages, 2005/03
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.
Kato, Shoichi; Yoshida, Eiichi; Ishigami, Katsuo*; Yaguchi, Katsumi*
JNC TN9400 2003-108, 92 Pages, 2004/02
JNC-TN9400-2003-108.pdf:36.44MB
A high Cr-Mo steel is a candidate for structural materials of future advanced fast reactors, because of good thermal properties and high creep strength. In this study, creep, creep-fatigue and corrosion tests were carried out to confirm the long-term extrapolation of sodium environmental, effects on the mechanical properties of HCM12A (2001). The exposure to sodium was conducted using a sodium test apparatus constituted by austenitic steels. For the conditions of in-sodium test, the sodium temperature was 550 deg-C and the oxygen concentration in sodium was below 2 ppm. The creep and creep-fatigue strength data in sodium, and in the carburized sodium were within the scattered range of those in air under the same conditions. It is considered that the creep damage in the bulk of the material was dominant. The creep and creep-fatigue life calculated using the usual rule for air showed good agreement with the sodium experimental results. The maximum corrosion rate of HCM12A (2001) was 0.4 micro-m/year at 550 deg-C, and it was almost same as SUS304 and Mod.9Cr-1Mo steels. Corrosion allowance of HCM12A (2001), therefore, can be estimated conservatively by the equation defined in "the elevated temperature structural design guide of prototype fast reactor".
; Yoshida, Eiichi; Ishigami, Katsuo*; Takamori, Yuji*
JNC TN9400 2003-006, 37 Pages, 2003/02
JNC-TN9400-2003-006.pdf:55.39MB
A high Cr-Mo steel is candidate for a structural materials of future FBR, because of good thermal properties and high creep strength. In this study, fatigue tests were carried out the long-term extrapolation of sodium environmental effects on the mechanical properties of HCM12A (2001-FBR). The exposure to sodium was conducted using a sodium test loop constituted by austenitic steels. For the conditions of in-sodium fatigue test, the sodium temperature was 550C, the oxygen concentration in sodium was about 1ppm and sodium flow rate on the surface of specimen was 1m/second. As results, the low-cycle fatigue lives in sodium were longer than those of in air, which is the same as results of 2
1/4Cr-1Mo steel and Mod.9Cr-1Mo steel, and no strength reduction could be detected. It was considered that the increase of fatigue life in sodium was mainly based on the extension of crack initiation life caused by restrained oxidation of specimen surface. The fatigue life in sodium calculated using usual rule showed good agreement with experimental results.