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; ; *; Yamaguchi, Akira
JNC TN9400 2000-109, 96 Pages, 2000/11
JNC-TN9400-2000-109.pdf:9.56MB
Numerical calculations were carried out for a free surface sloshing, a thermal stratification, a thermal striping, and a natural convection as key phenomena of in-vessel thermohydraulics in future fast reactor systems with various fluids as coolants. This numerical work was initiaied based on a recognition that the fundamental characteristics of the phenomena have been unsolved quantitatively in the use of various coolants. From the analysis for the phenomena, the following results were obtained. [Free Surface Sloshing phenomena] (1)Ther is no remarkable difference betweeen liquid sodium and luquid Pb-Bi in characteristics of internal flows and free surface charatristics based on Fr number. (2)the AQUA-VOF code has a potentiall enough to evaluate gas entrainment behavior from the free surface including the internal flow characteristics. [thermal Stratification Phenomena] (1)On-set position of thermal entainment process due to dynamic vortex flows was moved to downstream direction with decreasing of Ri number. 0n the other hand, the position in the case of C0
gas was shifted to upstream side with decreasing of Ri number. (2)Destruction speed of the thermal stratyification interface was dependent on thermal diffusivity as fluid properties. therefor it was concluded that an elimination method is necessary for the interface generated in C0 gas. [thermal Striping Phenomena] (1)Large amplitudes of fluid temperature fluctuations was reached to down stream area in the use of CO gas, due to larger fluid viscosity and smaller thermal diffusivity, compared with liquid sodium and liquid Pb-Bi cases. (2)To simulate thermal striping conditions such as amplitude and frequency of the fluid temperature fluctuations, it isnecessary for coincidences of Re number for the amplitude and of velocity value for the frequency, in various coolants. [Natural Convection Phenomena] (1)Fundamental behavior of the natural convection in various coolant follows buoyant jet ....
; *
JNC TN9450 2000-002, 335 Pages, 1999/10
JNC-TN9450-2000-002.pdf:21.65MB
This report summarizes the material test dala of SUS304 welded joints. Numbers of the data are as follows: [Tensile tests 71 (Post-irradiation: 39, others: 32) [Creep tests 77 (Post-irradiation: 20, others: 57) [Fatigue tests 50 (Post-irradiation: 0) [Creep-fatigue tests 14 (Post-irradiation: 0) This report consists of the printouts from "the structural material data processing system".
; *
JNC TN9450 2000-001, 1370 Pages, 1999/10
JNC-TN9450-2000-001.pdf:117.18MB
This report summarizes the material test data of SUS304. Numbers of the data are as follows. (1)Tensile tests 738 (Post-irradiation: 250, others: 488) (2)Creep tests 434 (Post-irradiation: 89, others: 345) (3)Fatigue tests 612 (Post-irradiation: 60, others: 552) (4)Creep-fatigue tests 200 (Post-irradiation: 40, others: 160) This report consists of the printouts from "the structural material data processing system".
*; *; *; *
PNC TJ9601 96-003, 38 Pages, 1996/03
In this study, for the purpose of development of a nondestructive detection technique of creep-fatigue damage in Type 316FR stainless steel for fast reactors, application study of electrochemical methods and the Induced Current Potential Drop(ICFPD) was done. Applicability of electrochemical methods to evaluation of grain boundary precipitates which, provide preferred site for cavities was investigated. Anodic polarization curves were measured both in 1N KOH solution and in 1N HSO
+KSCN solution. An anodic current peak that, corresponds to preferential dissolution of the grain boundary precipitates was observed in the measurements using in the KOH solutlon. It was suggested that evolution of the grain boundary precipitates which should be associated with creep-fatigue damage can be evaluated by the electrochemical method using KOH solution. The results of reactivation ratio of the material in 1N HSO+KSCN solution, which is recognized as the sensitive indicator of Cr-depletion, suggested a correlation between the reactivation ratio and creep-fatigue damage. Clear differences between the as-received material and the creep-fatigue damaged sample were found in ICFPD results. Although more detailed investigation is required to make a conclusion, it was expected that potential drop can reflect creep-fatigue damage in the microstructure, e.g. precipitates cavities, surface cracks. Based on the preliminaly result, the ICFPD technique may be expected to provide a quantitative monitoring capability of creep-fatigue damage.
Kaji, Yoshiyuki; Ioka, Ikuo;
The 3rd JSME/ASME Joint Int. Conf. on Nuclear Engineering (ICONE),Vol. 1, 0, p.363 - 368, 1995/00
no abstracts in English
; Hada, Kazuhiko; Koikegami, Hajime*; *
Nihon Genshiryoku Gakkai-Shi, 33(5), p.475 - 481, 1991/05
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)no abstracts in English
Atsuryoku Gijutsu, 29(3), p.177 - 181, 1991/00
no abstracts in English
Kikuchi, Kenji; Tsuji, Hirokazu; Nishiguchi, Isoharu
Zairyo, 37(412), p.94 - 100, 1988/00
no abstracts in English
; *; ; ; *
Nihon Zairyo Kyodo Gakkai-Shi, 21(2), p.69 - 86, 1986/00
no abstracts in English
Okamoto, Masayuki*; Nakayama, Yuta*; Ogawa, Fumio*; Hashidate, Ryuta; Hiyoshi, Noritake*; Wakai, Takashi; Ito, Takamoto*
no journal, ,
no abstracts in English
Ogawa, Fumio*; Imagawa, Yuya; Hashidate, Ryuta; Hiyoshi, Noritake*; Ito, Takamoto*
no journal, ,
In recent years, the demand for environmental protection has led to a trend toward shorter startup and shutdown intervals in thermal power plants. In fast breeder reactors (FBRs), more stringent operating environments (temperature and sodium environment) are also being considered. Modified 9Cr-1Mo steel is used in thermal power plants and fast breeder reactors because of its excellent mechanical properties at high temperatures. In actual machines, Modified 9Cr-1Mo steel is used in a creep-fatigue type with complex stress conditions, which may cause more damage than the uniaxial condition, so it is necessary to measure the multiaxial creep-fatigue life and establish a life evaluation method. In this study, axial and torsional multiaxial creep-fatigue tests were conducted in 550
C air to accumulate property data and to evaluate the life. The results will be described later, but the strain rate and retention time dependence showed peculiarities different from those in the past. Next, the strain energy corresponding to the hysteresis loop area between stress and strain was calculated to evaluate the life, and the same energy was theorized to compare the actual and theoretical life. Specifically, a new life evaluation method based on strain energy was studied, which can evaluate the peculiar strain rate, retention time dependence, and multiaxial state observed in the proportional loading test.
Ogawa, Fumio*; Imagawa, Yuya; Hashidate, Ryuta; Wakai, Takashi; Hiyoshi, Noritake*; Ito, Takamoto*
no journal, ,
Multiaxial creep-fatigue tests in tension and torsion were performed on Mod.9Cr-1Mo steel at 550C. Specificity was observed with respect to strain rate and retention time dependence, indicating that creep-fatigue life is governed by the maximum stress and the degree of stress relaxation. The hysteresis energy was calculated and the lifetime was organized considering the effect of non-proportional loading. Specifically, the mechanism of hysteresis onset was examined, and the energy formulation was made considering the hardening index and relaxation stress. Although the life evaluation has been organized with coefficients of 2.9 and 2.2, this study was conducted with the goal of first organizing the life evaluation with a coefficient of 2.
