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Takahashi, Yoshikazu; Suwa, Tomone; Nabara, Yoshihiro; Ozeki, Hidemasa; Hemmi, Tsutomu; Nunoya, Yoshihiko; Isono, Takaaki; Matsui, Kunihiro; Kawano, Katsumi; Oshikiri, Masayuki; et al.
IEEE Transactions on Applied Superconductivity, 25(3), p.4200904_1 - 4200904_4, 2015/06
Times Cited Count:3 Percentile:20.32(Engineering, Electrical & Electronic)The Japan Atomic Energy Agency (JAEA) is responsible for procuring all amounts of Central Solenoid (CS) Conductors for ITER, including CS jacket sections. The conductor is cable-in-conduit conductor (CICC) with a central spiral. A total of 576 NbSn strands and 288 copper strands are cabled around the central spiral. The maximum operating current is 40 kA at magnetic field of 13 T. CS jacket section is circular in square type tube made of JK2LB, which is high manganese stainless steel with boron added. Unit length of jacket sections is 7 m and 6,300 sections will be manufactured and inspected. Outer/inner dimension and weight are 51.3/35.3 mm and around 90 kg, respectively. Eddy Current Test (ECT) and Phased Array Ultrasonic Test (PAUT) were developed for non-destructive examination. The defects on inner and outer surfaces can be detected by ECT. The defects inside jacket section can be detected by PAUT. These technology and the inspected results are reported in this paper.
Nabara, Yoshihiro; Suwa, Tomone; Takahashi, Yoshikazu; Hemmi, Tsutomu; Kajitani, Hideki; Ozeki, Hidemasa; Sakurai, Takeru; Iguchi, Masahide; Nunoya, Yoshihiko; Isono, Takaaki; et al.
IEEE Transactions on Applied Superconductivity, 25(3), p.4200305_1 - 4200305_5, 2015/06
Times Cited Count:0 Percentile:0(Engineering, Electrical & Electronic)Makuuchi, Keizo; Tagawa, Seiichi*; Kashiwagi, Masayuki*; Kamada, Toshimitsu*; Sekiguchi, Masayuki*; Hosobuchi, Kazunari*; Tominaga, Hiroshi*; Ooka, Norikazu
Journal of Nuclear Science and Technology, 39(9), p.1002 - 1007, 2002/09
Times Cited Count:6 Percentile:39.58(Nuclear Science & Technology)no abstracts in English
*; Endo, Masayuki*; Sekiguchi, Yoshiyuki*
PNC TN941 80-06, 83 Pages, 1980/01
This report describes the results of the power coefficient test (NT-34) that was planned and performed as a part of the power-up testing of the Experimental Fast Reactor "JOYO". The purpose of this test is to measure the reactivity chauge against the power increase (power coefficient) by measuring the reactor thermal power and excess reactivity at steps of the power ascension procedure. This testing was made from July through August in 1978, and the followings were confirmed. (1)The power coefficient was negative in all power range through 50MW rated power, and could be fitted with good reproducibility as follows. Power coefficient f (%K/K/MW) = -5.93 10P-6.05 (10. P: Reactor thermal Power (MW) for 11MW ≦ P ≦ 53MW. The power coefficient was linear against the powar and became less negative with range 10MW (-6.610%K/K/MW) through 50MW (-9.010 %K/K/MW). (2)The experimental error was from +4.6% to -9.7%, and the dominant parts were the systematic errors. Particularly, the maximum error was derived from the difference of the thermal expansion between the extension pipes of the control rods and the reactor vessel. The error range was biased to the negative direction because the control rod worth used in this testing was seemed to be a few percent larger than the real worth by reasons of the change of the shadowiug effect, the change of the core fuel arrangement and the burn-up of control rods. (3)There was no significant difference between the results of the power ascent and descent. The reactor attained enough equilibrium of reactivity and thermal condition within about 20 minutes.
*; Endo, Masayuki*; *; *; *; Sekiguchi, Yoshiyuki*
PNC TN941 79-179, 198 Pages, 1979/10
This report describes the results of the thermal power calibration test (PT-11) that was planned and performed as part of the power-up testing of the Experimental Fast Reactor "JOYO". The purpose of this test is to calibrate the Power Range Monitors (PRM) and Intermediate Range Monitors (IRM) by measuring the reactor thermal power at several levels from low power through the rated power of 50 MWt. The reactor thermal power was determined by measuring the inlet and outlet temperature and the flow rate of the primary main coolant. After this procedure, PRM and IRM were adjusted to coincide with the reactor thermal power by regulating the electronic amplifiers. Thes testing was made from April through August 1978, and followings were confirmed. (1)The PRM indicators show good linearity with the reactor thermal power. (2)The PRM indicators overlap with the IRM indicators over more than three decades. (3)The PRM indicators changes depending on the operating histry of the reactor. The PRM indicators is lower than the reactor thermal power immediately after start-up. Then that increases gradually and comes to stable in about one week after start-up. The maximum drifting value is about 6 per cent.
Hirose, Tadashi*; Endo, Masayuki*; Nanashima, Takeshi*; Doi, Motoo*; Enomoto, Toshihiko*; Suzuki, Yukio*; Sekiguchi, Yoshiyuki*; Yamamoto, Hisashi*
PNC TN941 79-91, 81 Pages, 1978/12
This system is used to remove reactor decay heat in cases where the main cooling system is inoperable for unexpected reasons, a lower than normal sodium level exists in the R/V or during in-service inspection in the R/V. The purpose of this test is to verify that the design heat removal rate (2.6MWt) can be achieved by the Auxiliary cooling system. With the sodium level lowered below main cooling system outlet nozzles and the coolant temperature (DHX outlet temperature) controlled at 250 C, the reactor power was increased first to approx. 1MW (1.16 MWt actual) and then to 2 MW (2.16 MWt actual) to provide the "decay heat". At both steps, steady-state conditions were verified and test data were recorded, from which the heat removal rate at design conditions was calculated. (Testing was terminated after the second step to maintain the calculated distortion of the partially-filled R/V within prescribed limits.) Test Results : At the second test condition (reactor power = 2.16 MWt) the R/V inlet Na temperature of 267 C corresponded to a 72% open DHX inlet vane setting. Extraporating this to the design condition (R/V inlet temperature = 370C), a 100% DHX vane opening would permit the removal of 3.1 MWt decay heat.
Okada, Tomoyuki*; Iizuka, Masahide*; Hase, Yoshihiro; Nozawa, Shigeki; Narumi, Issei; Sekiguchi, Masayuki*
no journal, ,
no abstracts in English
Takatsuki, Satoshi*; Tsutsumi, Tomoaki*; Matsuda, Rieko*; Okano, Masahito*; Kameya, Hiromi*; Todoriki, Setsuko*; Kikuchi, Masahiro; Goto, Hirofumi*; Sekiguchi, Masayuki*; Hara, Hideyuki*; et al.
no journal, ,
no abstracts in English
Suwa, Tomone; Nabara, Yoshihiro; Takahashi, Yoshikazu; Oshikiri, Masayuki; Tsutsumi, Fumiaki; Shibutani, Kazuyuki*; Sekiguchi, Nobuo*; Matsuda, Hidemitsu*
no journal, ,
no abstracts in English