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Igawa, Naoki; Taguchi, Tomitsugu; Snead, L. L.*; Kato, Yudai*; Jitsukawa, Shiro; Koyama, Akira*; McLaughlin, J. C.*
Journal of Nuclear Materials, 307-311(Part2), p.1205 - 1209, 2002/12
Times Cited Count：16 Percentile：69.83(Materials Science, Multidisciplinary)no abstracts in English
Kitano, Koji*; Fuketa, Toyoshi; Uetsuka, Hiroshi
JAERI-Research 2001-041, 24 Pages, 2001/08
JAERI-Research-2001-041.pdf:2.75MB
no abstracts in English
Miura, Takayuki*; Kuwano, Hisashi*; Kikuchi, Kenji
Tetsu To Hagane, 87(2), p.31 - 36, 2001/02
no abstracts in English
Kaji, Yoshiyuki; Miwa, Yukio; Tsukada, Takashi; Tsuji, Hirokazu; Nakajima, Hajime
Journal of Nuclear Science and Technology, 37(11), p.949 - 958, 2000/11
no abstracts in English
Tsukimori, Kazuyuki
JNC TN9400 2000-086, 103 Pages, 2000/08
JNC-TN9400-2000-086.pdf:3.67MB
ln order to evaluate the integrity of the floor liner of "MONJU" at sodium leakage accident, nonlinear finite element analyses have been conducted considering the effect of thinning of the liner due to molten salt type corrosion. Modeling by shell elements is appropriate since liner is composed of thin plates, however, it is difficult to deal with the very local strain behaviors. 0n the other hand, modeling by solid elements makes the numerical calculation impractical. If we extract the small part of the liner which includes local discontinuities, it is possible to evaluate local strain behaviors practically by using the solid element analysis model of the part. To realize this approach, the method to generate all the boundary displacements of the part model from the shell element analysis result of total structure is needed. The aims of this study are to develop the method to deal with the incompatibility between shell and solid elements at part model boundary, and to build numerical analysis circumstances including this method to make the detailed nonlinear finite element analyses of the floor liner of "MONJU" possible. Summary of the results is shown below, (1)The problem of the incompatibility between shell and solid elements was solved by introducing weighting function at 'T' and 'L' type corners and the interpolation function of 4-node rectangular plate bending element at the connection between liner plate and frame. (2)Software system was developed by using 'FINAS' and verified. (3)This approach was applied to one of the cases of the floor liner analyses of "MONJU" at sodium leakage accident. The analysis result showed that three-dimensional local strain behavior could be evaluated directly. ln addition, it was confirmed that the result by shell element analysis was conservative in evaluation of strain compared with that by solid element analysis in this case.
Kuroda, Masatoshi*; Yoshioka, Kunihiko*; Yamanaka, Shinsuke*; Anada, Hiroyuki*; Nagase, Fumihisa; Uetsuka, Hiroshi
Journal of Nuclear Science and Technology, 37(8), p.670 - 675, 2000/08
no abstracts in English
; ; Sakamoto, Naoki; *; Akasaka, Naoaki;
JNC TN9400 2000-095, 110 Pages, 2000/07
JNC-TN9400-2000-095.pdf:13.57MB
The effects of high fluence irradiation and swelling on the transient burst properties of austenitic steel fuel claddings; PNC316 and 15Cr-20Ni stcel, which were irradiated as the MONJU type fuel assemblies (MFA-1&MFA-2) in the FFTF reactor, were investigated. The temperature-transient-to-burst tests were conducted on a total of eight irradiation conditions. Fractographic examination and TEM observation were performed in order to evaluate the effect of high dose irradiation on the transient burst property and the relation between failure mechanism and microstructural change during rapid (ramp) heating. The results of the PIE showed that there was no significant effect of irradiation on the transient burst properties of these fuel claddings under the irradiation conditions examined. the results obtained in this study are as follows; (1)The rupture temperature of the irradiated PNC316 fuel cladding of MFA-1 was as same as that of our previous works for the fluence range up to 2.13
10
n/m
. There was no noticeable decrease in rupture temperature with increasing fluence in lower hoop stress region(
100MPa). (2)The rupture temperature of the irradiated 15Cr-20Ni fuel cladding of MFA-2 was almost as same as that of as-received cladding for the hoop stress range up to about 200MPa. The rupture temperature did not decrease significantly with fluence. (3)The rupture temperature of the irradiated PNC316 cladding tested at hoop stress 69MPa, which was the design hoop stress for MONJU fuel, was 1055.6
C. This suggested that the design cladding maximum temperature limit for MONJU (830C) was conservative. (4)There was no obvious relation between rupture temperature, swelling and microstructural change during transient heating under the irradiation conditions examined.
; *; ; ; Aoto, Kazumi;
JNC TN9400 2000-059, 43 Pages, 2000/05
JNC-TN9400-2000-059.pdf:2.08MB
The purpose of this study is to understand the material properties of manufacturable high-purity iron and high-purity iron-based alloy in present technology and to get an applicable prospect for the structural and functional material of the frontier fast reactor. Then the about 10kg high-purity iron and iron-based alloy were melted using a cold-crucible induction melting furnace under the ultra-high vacuum. Subsequent to that, the compatibility between the melted material and the high-temperature sodium environment which is a special feature of the fast reactor and tensile property at room and elevated temperatures were investigated using the melted materials. Also, the creep test using the high-purity 50%Cr-Fe alloy at 550C in air in order to understand the high temperature creep property. ln addition, the material properties such as thermal expansion coefficient, specific heat and electrical resistance were measured and to evaluate the outlook for the structural material for the fast reactor. The following results were obtained based on the property test and evaluation. (1)lt was possible to melt the about 10kg high-purity ingot and high-purity 50%Cr-Fe alloy ingot using a cold-crucible induction melting furnace under the ultra-high vacuum. (2)The tensile tests of the high-purity 50%Cr-Fe alloy were performed at room and elevated temperatures in order to understand the deformation behavior. From the experimental results, it was clear that the high-purity 50%Cr-Fe alloy possesses high strength and good ductility at elevated temperatures. (3)The physical properties (the thermal expansion coefficient and specific heat etc.) were measured using the high-purity 50%Cr-Fe alloy. lt was clear that the thermal expansion coefficient of high-purity 50%Cr-Fe alloy was smaller than that of SUS304. (4)From the corrosion test in liquid sodium, the ordinary-purity iron showed the weight loss after corrosion test. However the high-purity iron showed ...
Yamanaka, Shinsuke*; Uno, Masayoshi*; Kurosaki, Ken*; ; Namekawa, Takashi
JNC TY9400 2000-011, 41 Pages, 2000/03
JNC-TY9400-2000-011.pdf:1.28MB
no abstracts in English
Sato, Toshinori; Taniguchi, Wataru; Fujita, Tomoo; Hasegawa, Hiroshi
JNC TN7400 99-011, 36 Pages, 1999/12
In order to understand the general thermal and mechanical properties of rock masses and initial stress of rock at depth, data were compiled from the published literature in Japan and collected from investigations carried out at Kamaishi mine and Tono mine. Statistical examinations derived the ranges, means and medians of the mechanical properties for the different rock types. It was confirmed that the correlations between the mechanical properties were in agreement with correlations determined previously in other similar surveys. The unconfined compressive strength of Neogene sedimentary rocks showed a tendency to increase with increasing depth (
500 m). An examination of the measured initial stress data collected through literature surveys showed that the vertical stress can be approximated by the extent of gravitational loading at a particular point. There is an approximately linear relationship between the average stress in a horizontal plane and the depth. The lateral pressure coefficient tends to have a high value and large range at shallow depths, but tends towards 
1 with increasing depth.
Ota, Kunio; Nakano, Katsushi; Metcalfe, R.; Ikeda, Koki; ; Amano, Kenji; Takeuchi, Shinji; Hama, Katsuhiro; Matsui, Hiroya
JNC TN7410 99-007, 44 Pages, 1999/08
; Ara, Katsuyuki;
Proc. of 9th Int. Symp. on Reactor Dosimetry, 0, p.785 - 792, 1998/00
no abstracts in English
Wakai, Eiichi; Hishinuma, Akimichi; Sawai, Tomotsugu; Kato, Yasushi*; Isozaki, Seiichi*; Takaki, Seiichi*; Abiko, Kenji*
Physica Status Solidi (A), 160(2), p.441 - 448, 1997/00
Times Cited Count：15 Percentile：66.71(Materials Science, Multidisciplinary)no abstracts in English
Sawai, Tomotsugu; Fukai, Katsumaro; Hishinuma, Akimichi
Microstructures and Functions of Materials (ICMFM 96), 0, p.257 - 260, 1996/00
no abstracts in English
Ara, Katsuyuki;
Nihon Oyo Jiki Gakkai-Shi, 20(3), p.743 - 749, 1996/00
no abstracts in English
Udagawa, Akira; Yudate, Kozo*; Kudo, Hisaaki; Sasuga, Tsuneo; Morino, Yoshiki*; Seguchi, Tadao
JAERI-Tech 95-007, 25 Pages, 1995/02
no abstracts in English
; *; *
Journal of Nuclear Science and Technology, 31(11), p.1214 - 1221, 1994/11
Times Cited Count：12 Percentile：71.36(Nuclear Science & Technology)no abstracts in English
; *; ; Yoshida, Eiichi;
PNC TN9410 94-261, 143 Pages, 1994/06
In this study, tensile, creep and relaxation test in air were performed in order to examine the mechanical properties of Mod.9Cr-1Mo steel which is a candidate material for once throuth type steam generator of large scale fast breeder reactor. Tested materials were plate(12mmt) simulating heat exchenger tube and heat exchenger tube of Mod.9Cr-1Mo steel and 9Cr-2Mo steel was also tested as reference material. Results obtained are summarized as follows. (1)Tensile properties (a)Ultimate tensile strength and 0.2% yield strength of Mod.9Cr-1Mo steels were higher than the tentative Su and Sy values of the design allowable stress in the test temperature below 600C. (b)Ultimate tensile strength of Mod.9Cr-1Mo steels plate and tube were higher than that of 9Cr-2Mo Steels. (3)The difference in ultimate tensile strength and 0.2% yield strength between steel plate and tube could not be found in these tests. (2)Creep properties (a)Creep rupture strength of Mod.9Cr-1Mo steel plate and tube was higher than the tentative S
value of the design creep-rupture stress intensity at 500600C, and this tendency is significant in the range of longer rupture time. (b)For the relation between steady creep rate and creep rupture time, steady creep rates obtained in this study coincided well with the 
of tentative creep strain equation. (c)Creep rupture strength of Mod.9Cr-1Mo steel plate and tube was higher than that of 9Cr-2Mo steel. (3)Relaxation properties (a)In the strain range of 0.10.5%, stress rapidly relaxed during the short hold time, and stress relaxation tended to be saturate beyond 50hours. These relaxation stresses became large in higher temperature and higher strain level. (b)Stress relaxation behavior was predicted approximately by tentative creep equation of Mod.9Cr-1Mo steel. The analysis of these test results is continued to develop of evaluation method of material strength.
K.Humer*; H.W.Weber*; E.K.Tschegg*; Egusa, Shigenori; R.C.Birtcher*; H.Gerstenberg*
Advances in Cryogenic Engineering Materials, Vol.40, p.1015 - 1024, 1994/00
no abstracts in English
