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Maruyama, Akira; Nomura, Shigeo; Kawai, Masashi; Takani, Satoru; Ota, Yoshio; Atsumo, Hideo
Nihon Genshiryoku Gakkai-Shi, 26(4), p.327 - 338, 1984/04
Times Cited Count：5 Percentile：51.32(Nuclear Science & Technology)None
*; *; Atsumo, Hideo
PNC TN241 81-23, 232 Pages, 1981/08
As a part of PNC-USDOE corporation in the field of fast breeder reactor, thermal transient test of 24-inch elbow, made of type 304 stainless steel, was performed at ETEC (Energy Technology Engineering Center). Test results were analysed and evaluated at PNC. Following results were drawn from the test and the relevant stress analysis: (1)Thermal transient test was performed under constant in-plane bending moment and cyclic rapid cooling by nitrogen gas. When the mechanical load was increased step by step, shakedown or ratchetting behavior was observed under or above a certain level of load. For typical points at inner and outer surface of elbow, strain was measured by using high-temperature strain gage. (2)Thermal ratchetting analysis was performed by using FINAS. Coincidence between analysis and test results was obtained for qualitative shake down or ratchetting behaviour. As to increment of displacement or strain per cycle, analytical results were fairly larger than test results. (3)In the case of this test, in which creep effect is negligible, ratchetting load calculated by current high-temperature structural design method (ASME Code Case N-47 and PNC's structural design guide) gives sufficiently concervative value. (4)Thermal ratchetting mechanism of elbow under in-plane bending moment was identified as follows by test and analysis : bending deformation in circumferential direction at elbow side; extensional deformation in longitudinal direction at outer point from the elbow side by 20-degree; compressive deformation in longitudinal direction at inner point from the elbow side by 30-degree. (5)Ratchetting condition can be estimated fairly well and conservatively by taking following parameters in Bree's diagram : x = [(membrane stress) + (bending stress)/(section factor)]/(yield stress), and y = (thermal stress using equivalent linear temperature difference)/(yield stress). (6)Comparing this test with another test for smaller elbow at O-arai Engineering ...
4, 78-6 10)Atsumo, Hideo; *; *
PNC TN241 80-02, 1075 Pages, 1980/03
This report includes the structural materials test results conducted in 1978, such as tensile test, high speed tensile test, creep test, low cycle fatigue test, and relaxation test on structural materials of fast Breeder reactor (FBR). The maximum metal temperatures of the structural materials of prototype FBR components are scheduled 529
C for austenitic stainless steels, and 450C for 2 1/4 Cr - 1Mo steel. Under the elevated temperatures as mentioned above, it is necessary to consider the failure modes additionally such as creep rupture, creep fatigue, and creep buckling in case of the FBR component design, therefore, necessary to get a lot of the structural materials test data related to the additional failure modes, especially on creep fatigue and creep deformation behavior under the elevated temperatures. The FBR structural materials test have been started up since 1977 by Structural Material Group, FBR Development Project, Power Reactor and Nuclear Fuel Development Corporation. The Tests conducted in 1978 are as follows: (1)Strength of Base and Pre-strained Metal of SUS304 and Inconel 718 at Elevated Temperature (Toshiba Corp. Ltd.) (2)Strength Tests of Base Metal and Welded Joint of SUS316 and SUS304 Stainless Steel at Elevated Temperature (Hitachi Ltd.) (3)Low Cycle Fatigue, Creep-Fatigue Tests and Stress Relaxation Tests of SUS304 Stainless Steel (Fuji Electric Co., Ltd.) (4)Creep Test of SUS321 Forging and 2 1/4Cr - 1MO Stee1 Plate (Kawasak1 Heavy Industries, Ltd.) (5)Elevated Temperature Properties of SUS321 Heat Exchanger Tube and Forged Thick Plate for LMFBR(Mitsubishi Heavy Industries, Ltd.) (6)A Study on Notch Effeets on Elevated Low-Cycle Fatigue of 304 Stainless Steel(Mitsubishi Heavy Industries, Ltd.) (7)Strength of 2 1/4 Cr- 1Mo Steel and SUS316 Stainless Steel at Elevated Temperature (Babcock-Hitachi K.K.) (8)The Elevated Temperature Properties of SUS316 Heat Exchanger Tubes and Tube-to-Forged Welded Joints and the ...
Hirano, Masaatsu; Kohashi, Kazuyuki*; Yuhara, Shinichi*; Nakasuji, Takashi; Atsumo, Hideo
PNC TN951 77-03, 35 Pages, 1977/08
Strain controlled fatigue tests with triangular waveform in sodium and in air at 550
were conducted by use of the fatigue test facilities in sodium for the purpose of establishing the fatigue testing technique and clarifying the fatigue behavior in sodium. The results obtained are summarized as follows. The fatigue test technique in high temperature sodium involving the calibration method of the elongation of a specimen and push-pull rod was established. The fatigue life of SUS304 stainless steel in sodium at 550 was longer than that in air at the same temperature, at the same strain rate of 1
10
sec
and that of ASME fatigue design curve. Particularly, this tendency was larger as the strain range become lower.
Kano, Shigeki; Koakutsu, Toru; Hasegawa, Naruo; Nakayama, Koichi; Nakasuji, Takashi; Atsumo, Hideo
PNC TN941 77-111, 95 Pages, 1977/06
A corrosion test of hard facing material has been conducted in 600C sodium for 2000 hrs. Test pieces were Co base alloys, Ni base alloys and carbides which were provided for tribology studies in sodium. These materials were compared with SUS304, SUS316 and another corrosion and heat resisting alloys by simultaneous exposure. Analysis methods after exposure were as follows: surface roughness, hardness, corrosion rate, surface morphology and metallurgical structure which have influence on friction and self-welding behavior. The results obtained are as follows: (1)Stellitew alloys: Part of test pieces showed weight gain. Change of surface roughness was minute. Structural change was not observed in the surface vicinity of sodium contact. However, hardness increase was observed. (2)Ni base hard facing materials such as Colmonoy alloys: Corrosion rates were high and hardness was reduced. A degraded layer of 10
m through 40m was observed on the surface of Colmonoy alloys and their surface roughness increased. (3)Inconel alloys: Corrosion rates were double those of stainless steels. A degraded layer of 1m through 4m was observed on the surface. Change in surface roughness was minute. (4)Corrosion and heat resisting alloys: Corrosion rates showed one to two times greater than those of stainless steels. Change in surface roughness was minute. No change in surface layer was observed. However, precipitates were observed in the metallurgical structures of some alloy types. (5)Carbides: Large increase of surface roughness was observed. LC-1C exhibited stripping from substratum. LW-1N40 indicated wide variation in corrosion rates. (6)Other materials: SUS316 produced a sigma phase at the grain boundary of sodium surface contact.
*; *; *; *; Atsumo, Hideo
PNC TN941 77-51, 190 Pages, 1977/01
Probe-type eddy-current flow and temperature sensors have been developed for in-core monitors of prototype fast breeder reactor "MONJU". The MK-II sensor (11.0mm O.D. 130mm long, magnetic core) has a central primary coil and two identical coils placed symmetrically about the primary, and is installed in a stainless-steel guide tube. It is capable of monitoring sodium flow and temperature at a time by means of vector differencing and vector summing of secondary coil signals respectively. In-sodium tests were carried out under conditions in the Sodium Instrument Test Loop. [Sodium temperature : 300 550 C] [Sodium flow velocity : O 3 m/s] [Exciting frequency : 20 1000 Hz] Test results are as follows. (1)The performane as a flow sensor : The output/flow characteristic was linear up to 3 m/s, and has high sensitivity as much as 1.34 mV/m/s at 75 Hz. The temperature dependency of flow output signal were reduced to 1% (400 500 C) with a temperature compensation circuit. (2)The performance as a temperature sensor : Temperature detecting sensitivity was 48.5V/C at 75 Hz, and linearity was fairly well in the Temperature range, 300 500 C. (3)It was shown that both flow and temperature outputs are useful for detecting gas bubbles in sodium. (4)It became clear that the top shape of a guide tube has not an important effect on the flow output signal, after testing conic, spherical, ellipsoidal, cylindrical guide tubes and spherical one with fins. Some basic problems, such as the potential of detecting subassembly flow blockage and/or gas bubbles in sodium, were discussed in order to apply this sensor to in-core instrumentation of LMGBR.
Kano, Shigeki; Nakayama, Koichi; Hasegawa, Naruo; Koakutsu, Toru; Namekawa, Masaru; Nakasuji, Takashi; Atsumo, Hideo
PNC TN941 77-179TR, 48 Pages, 1977/01
Kano, Shigeki; Nakayama, Koichi; Hasegawa, Naruo; Koakutsu, Toru; Nakasuji, Takashi; Namekawa, Masaru; Atsumo, Hideo
PNC TN941 77-179, 48 Pages, 1977/01
PNC-TN941-77-179.pdf:2.55MBPNC-TN941-77-179TR.pdf:2.29MB
A series of experiments have been carried out to develop and screen friction and wear resistant materials used for sliding components of a sodium cooled reactor. Preceding studies 
clarified the short-term friction and wear characteristics of various materials in 450C sodium. A present study relates to clarify friction and wear behavior in argon environment, where a part of sliding components are located, and compare test data in room temperature argon with those in 450do sodium. The results obtained are as follows: (1)Static friction coefficients (s) in argon were almost lower than 0.2. They were apt to be lower than those in sodium. (2)Kinetic friction coefficients (k) in argon varied with load. The difference of k in argon and sodium depended on material combination. (3)Wear rates were remarkably high in argon. Wear rates of Colmonoy and Stellite were not detected in sodium, but were detected in argon. (4)Sliding surface was more roughened in argon, and hardness of sliding surface was almost lower in argon than in sodium. (5)There is the significant difference between friction and wear characteristics argon and those in sodium. Then, it is difficult that in-sodium behavior is estimated with in-argon data. (6)The above-mentioned difference in room temperature argon and 450C sodium will be greater when the test is carried out in higher temperature argon.
*; Nakasuji, Takashi; Atsumo, Hideo; Kohashi, Kazuyuki*; *
PNC TN951 76-15, , 1976/11
no abstracts in English
Yuhara, Shinichi*; Kano, Shigeki; Owada, Tetsuro*; Atsumo, Hideo
PNC TN951 76-07, 67 Pages, 1976/07
Kano, Shigeki; *; Nakayama, Koichi; Hasegawa, Naruo; Koakutsu, Toru; Atsumo, Hideo; Nakasuji, Takashi
PNC TN941 76-81, 25 Pages, 1976/07
A series of experiments in sodium environment have been carried out to develop and screen the friction and wear resistant materials used for sliding components of the sodium cooled reactor. The present study relates to the friction and wear characteristics of nickel-basealloy "Colmonoy" and cobalt-base alloy "Stellite" with respect to temperature, load, sliding velocity, sliding mode and sodium flushing. Also several experiments were carried out in argon and atmospheric environments, and they were compared with those in sodium. The results obtained were as follows : (1)As the sodium temperature is raised, the kinetic friction coefficient (
) of Stellite alloy becomes higher, but that of colmonoy alloy remains constant or is rather lower. The of Collmonoy alloy becomes lower by 540C sodium flushing. (2)Both static friction coefficient (
) and of Colmonoy alloy are lower than those of Stellite alloy in sodium environment. (3)The dependence of and upon the load is low in sodium environment. In argon the dependence of upon the load is not found, while varies according to the load. (4)The friction behavior is influenced by sliding mode. The in oscillating sliding is higher than that in one-directional continuous sliding. Also the sliding surface in oscillating sliding is more roughened. (5)The dependence of upon the sliding velocity is not found in sodium environment except for that in low velocity area. (6)The kinetic friction coefficient is apt to be higher in argon than in sodium. Also the wear rate is much higher in argon.
*; *; Takeda, Kunio; *; Atsumo, Hideo
PNC TN941 76-59, 24 Pages, 1976/06
Three permanent magnet type small-size sodium flow meters which were installed in General Purpose Sodium Test Loop have been used in sodium for about ten thousand hours. Based on the data obtained in this periods, the characteristics of these flow meters were checked about the effect of sodium tamperature and elapsed time. Flowing results were obtained. (1)Good linearity was observed between output voltage and flow rate. (2)The output voltage of these flow meters were from 77% to 92% of the designed value. (3)The output voltage decreased as sodium temperature increased and the rate was nearly equal to the calculated value (-0.009 %/C). (4)Output voltage decrease with elapsed time was not observed.
Takeda, Kunio*; Ito, Kazumoto*; Mizutani, Tomonori*; Wada, Juichi*; Takani, Satoru*; Atsumo, Hideo*
PNC TN951 76-04, 64 Pages, 1976/03
The solubility of oxygen in liquid sodium was determined by vacuum distillation. Oxygen concentration was controlled by a cold trap in a dynamic sodium loop, and sodium was sampled from an expansion tank by dipping cup method and analysed by on line vacuum distillation method. A least-squares fit of the 37 experimental data over the range from 150 to 250C of cold trap temperature yielded a correlating equation of log S = 6.118-(2383/T) where S= wt ppm of oxygen in sodium assumed to be Na
O. T = absolute temperature (K) The heat of solution 
H of NaO in liquid sodium was calculated from this equation to be 10902 cal/mole. The reproducibility of results was obtained at equilibrium temperature of 150, 200, and 250C with a standard deviation of 1.2, 1.8, and 4.1 ppm, respectively. The oxygen analysis results with cold trapping sodium from various sodium test loops in Oarai Engineering Center almost correspond with the solubility curve of this work.
Cr-1Mo SteelS.Kanoh*; K.Nakay*; S.Mizob*; M.Namek*; Atsumo, Hideo*
PNC TN951 75-15, 53 Pages, 1976/03
A series wear tests in sodium have been carried out to develop and screen friction and wear resistant materials for sliding components of the sodium cooled reactor. The present study was carried out on various combinations of Stellite No.1, colmonoy No.6, Inconel 718, Hastelloy C and 2 1/4Cr-1Mo Steel. The tests yielded the following results. (1) Colmonoy No.6 was the only material that descreased in hardness after tested. The higher the temperature was, the lower became the static friction coefficient (s) of Colmonoy No.6 alone. (2) The kinetic friction coefficient (k) of Stellite No.1 vs. Stellite No.1 was as high as 0.5, but it became lower (0.12) in case the mating material was Colmonoy No.6. The k-value of Colmonoy No.6 vs. Colmonoy No.6 was as low as 0.2. These material combinations scacerly wore. (3) The k-value of Inconel 718 vs. Inconel 718 was as low as 0.3, but this combination wore under load more than 300kg. (4) The k-value of Hastelloy C vs. Hast
Mizobuchi, Shotaro*; Kano, Shigeki; Nakayama, Koichi; Namekawa, Masaru; Atsumo, Hideo
PNC TN951 75-14, 77 Pages, 1976/02
We have been conducting a series of self-welding and friction tests for the material selection of the contacting and sliding parts used in a fast breeder reactor. In the present study, we tested some candidate materials for duct pads of the fuel-assembly in high temperature sodium and argon, and made the evaluation of these materials. The following results were obtained: (1) tellite No.6 showed the stablefrictional behavior in 280 sodium, but incresed the frictional coefficient and flushing effect in 540 sodium. (2) Colmonoy No.6 showed the stable frictional coefficient 0f 0.30.4 under a heavy load (500 kg) or in high temperature sodium. (3) Chromecarbide materials showed the different frictional behavior according to the methods for finishing of the test surface. Frictional coefficient of the grinder-finish-ed chrome-carbide exceeded q.o, and indicated a greater flushing effect in 540 sodium. (4) hard chrome plating showed an unstable frictional behavior, the fric
*; Nakayama, Koichi; Kano, Shigeki; Nakasuji, Takashi; Atsumo, Hideo
PNC TN941 76-32, 79 Pages, 1976/02
A series of friction and self-welding tests have been conducted for material selection of many contacting and sliding parts used in a fast breeder reactor, and the present experiment was investigated with respect to the variation of frictional behavior due to the difference of the principal composition such as nickel, cobalt contained in various Colmonoy alloys (No.2, 4, 6) and Stellite alloys (No.1, 6, 12). The following results were obtained through these experiments. (l)The difference of the basic composition such as Nickel or Cobalt showed the different frictional behavior. For instance, the behaviors cobalt basic materials dependedon sodium temperature and nickel basic materials showed a stable behavior of friction. (2)Hard facing materials combined with Type 316 SS indicated higher frictional coefficient than the same combination of hard facing materials, and they showed the tendency to easily gall. (3)Colmonoy No.2 and No.4 of nickel basic materials showed the stable and low frictional coefficient of 0.3, but it showed the increasing static coefficient of friction in sodium. Also, hard facing materials showed higher self-weldability when combined with Type 316 SS.
