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Yoshida, Eiichi; Hirakawa, Yasushi; Kuroko, Koichi*; Yoshida, Eiichi
JNC TN9400 2003-049, 119 Pages, 2003/06
A lead-bismuth eutectic (PbBi alloy) is one of candidates for an intermediate heat transport medium used in a steam generator of future sodium cooled fast reactor. This experimental study has been carried out to investigate the reaction phenomena and the basic physical properties of reaction products of the PbBi alloy and sodium (Na), when the PbBi alloy leaks to the sodium circuit system.
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PNC TN9450 96-002, 173 Pages, 1996/01
In order to advancement in materials strength standard on elevated temperature design guide of the FBRs and evaluation method of materials strength behavior, this report are presented about the creep properties of FBR grade 316 (Abbreviation 316FR), based on the R&D results obtained through the activities of material tests. Contents of the data sheet are as follows; (1)Material : 316FR (Weld Joint, Weld Metal) (2)Test environment : In air (3)Test temperature : 550C650C (4)Test method : According to JIS and FBR Metallic Materials Test Method (5)Number of deta : 71 points
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PNC TN9450 96-001, 70 Pages, 1996/01
In order to advancement in materials strength standard on elevated temperature design guide of the FBRs and evaluation method of materials strength behavior, this report are presented about the tensile properties of FBR grade 316 (Abbreviation 316FR), based on the R&D results obtained through the activities of material tests. Contents of the data sheet are as follows; (1)Material : 316FR (Weld Joint , Weld Metal) (2)Test temperature : R.T650C (3)Test method : According to JIS and FBR Metalic Materials Test Method (4)Number of data : 40 points