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; Yoshida, Eiichi; Aoto, Kazumi
JNC TN9400 2000-042, 112 Pages, 2000/03
JNC-TN9400-2000-042.pdf:8.55MB
A sodium-water reaction drove from the single tube break in steam generator of FBR might overheat labor tubes rapidly under internal pressure loadings. lf the temperature of tube wall becomes too high, it has to be evaluated that the stress of tube does not exceed the material strength limit to prevent the propagation of tube rupture. This study clarified the tensile and creep properties of Mod.9Cr-1Mo steel at ultra-high temperature which will be used in evaluation of the tube burst by sodium-water reaction. The strain rates for tensile test are from 10%/min to 10%/sec, and creep-rupture time is maximum 277sec. The range of test temperature is 700
C to 1300C. The main results obtained were as follows; (1)The evaluation data on the relationship between tensile strength and strain rate and creep-rupture strength in shorter time on Mod.9Cr-1Mo steel were acquired. (2)Short-term mechanical properties of Mod.9Cr-1Mo steel were evaluated based on the results of tensile and creep-rupture tests up to 1300C. As a result of the evaluation, recommended equation of creep-rupture strength in the short-term was proposed. (3)Tensile and creep-rupture strength of Mod.9Cr-1Mo steel tube showed the value which was higher than the 2 1/4Cr-1Mo steel, and it was proven to have the superior properties.
Shimoyama, Kazuhito; Hamada, Hirotsugu; Tanabe, Hiromi; Usami, Masayuki
PNC TN9410 93-212, 134 Pages, 1993/09
A one-through unit type steam generator (SG) having the Mod.9Cr-1MO Steel for its heat transfer tube is considered to be promising for the development of large FBR SGs. Wastage data of the tube material was already obtained for the micro-/small leak region as formerly reported. Therefore, intermediate leak wastage tests were conducted in the range from 10 g/s to around 200 g/s by using the SWAT-1 test facility and the test results are summarized as follows: (1)The wastage resistivity of the Mod.9Cr-1Mo steel is between that of 2.25Cr-1Mo steel and austenitic stainless steel; namely, the Mod.9Cr-1Mo steel has about half the of wastage rate of the 2.25Cr-1Mo steel. An experimental wastage formula in the intermediate leak region was derived from the test data. (2)Almost all of the wastage profile of target tubes was toroidal type and it became about half the cross section area of the 2.25Cr-1Mo steel. An experimental formula on initial leak diameters versus equivalent secondary failure diameters was derived in the intermediate leak region. These test results would be applied to failure propagation analysis code LBAP which is to be used for the design of a one-through unit type SG.
; Kawasaki, Hirotsugu; Aoto, Kazumi; Yoshida, Eiichi; ;
PNC TN9410 92-089, 61 Pages, 1992/03
The allowable strain range 
of Mod.9Cr-1Mo (NT) steel has been substituted by that for 2-1/4Cr-1Mo (NT) steel in last version of material strength standard in 1989. Because of the a small amount of fatigue test data on Mod.9Cr-1Mo (NT) steel, it is difficult to determine the best fit curve and allowable strain range of Mod.9Cr-1Mo (NT) steel can be evaluated conservatively by the values of 2-1/4Cr-1Mo (NT) steel. Low-cycle fatigue tests by various strain rates and the high-cycle fatigue tests were carried out to determine the new best fit fatigue life equation of this material. In this report, the fatigue life equation of Mod.9Cr-1Mo (NT) steel is and the interim new version of allowable strain range is proposed. The obtained results are as follows, (1)In the best fit fatigue life equation of Mod.9Cr-1Mo (NT) steel the effects by both of the temperature and low strain rate should be considerd. As the analytical methods to consider these dependency in the fatigue life equation, the correlation to the fatigue properties of 2-1/4Cr-1Mo (NT) steel is examined. Some data fitting methods based on the fatigue equation for 2-1/4Cr-1Mo (NT) steel are tried and compared. One of these methods could give a good prediction for the fatigue properties of the Mod.9Cr-1Mo (NT) steel up to high cycle range. (2)The interim standard of allowable strain ranges A , B and C (for strain rate of 10
, 10
and 10
s 
) for Mod.9Cr-1Mo (NT) steel could be proposed by the new best fit fatigue life equation. (3)The proposed allowable strain range at 375C was compared to the present design fatiuge curve of low alloy steel of MITI Notice No501, and it was clarified that the fatigue strength of Mod.9Cr-1Mo steel was too higher. The design fatigue curve for Mod.9Cr-1Mo (NT) steel will be revised to higher design value (twice for starin range at l0
cycles) than the present design fatigue curve of low alloy steel.
*
PNC TN9410 90-094, 80 Pages, 1990/06
It is needed for FBR design to know physical properties of the structural materials that will be used for FBR-reactor vessels, -steam generators, and -pipes. In this report, six types of steels that are noted as the structural materials for next steps of FBR are taken up. The six types of steels are as follows ; [SUS 304] [SUS 316 (conventional)] [FBR grade SUS316] [SUS321] [2.25Cr-1Mo steel] [Mod.9Cr-1Mo steel (ASTM A387-91).] Physical properties of the steels are measured on rolled plates made by mills. The measured physical properties are as follows ; [Specific gravity] [Specific heat] [Thermal conductivity] [Thermal expansion] [Young's modulus] [Poisson's ratio.] And also the same kinds of physical properties of S.R. (Stess Relieving) heat treated 2.25Cr-1Mo and Mod.9Cr-1Mo steel plates are measured. Measurement of the physical properties of forgings, pipes, and weld metals of selected types of steels of them will be also carried out in 1990 and all summarized data that will contain the results of this report will be used to determin the criteria design values of the physical properties for the next steps of FBR. (Caution) This report only shows the measurement results of the physical properties of the rolled steel plates but doesn't give the design standards of the physical properties for the next steps of FBR.
*; *; Kano, Shigeki; *; *; *; *
PNC TN9410 89-096, 105 Pages, 1989/05
A series of high temperature fracture toughness tests of 9Cr type steel was put in practice on a three-year scheme in 1988, In this experimental study, Mod.9Cr-1Mo steel, 9Cr-2Mo steel and TEMPALOY SW-9(9Cr-1Mo-Nb-V) steel are tested, and fracture toughness (J
) of base metal (As-received, SR-treated, Aged) and weldment (weld metal, HAZ) of these three types of steel are investigated. In a first year, fracture toughness tests of base metal (As-received, SR-treated) of Mod.9Cr-1Mo steel were carried out at RT, 400C, 500C, 550C and 600C, respectively. In this report, the test results in the first year are shown. Fracture toughness tests were performed using R-curve method and unloading compliance method according to ASTM E813. The fracture toughness value was the lowest at 400C. Even at 400C, however, Mod.9Cr-1Mo steel showed enough high fracture toughness (J
350kJ/m
), In the fracture toughness test, tearing modurous T
was also measured.