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Aoki, Tadao; Sawada, Makoto; Oshita, Hironori; Matsuno, Yoshiaki*; Kitano, Akihiro; KAMEI, Michiru*
JNC TN4520 2004-001, 350 Pages, 2004/09
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PNC TN9410 94-052, 251 Pages, 1994/01
The structure of the pressure tube rolled joint portion for the ATR Demonstration Reactor is somewhat changed from that for Fugen, in order reduce the residual stress around the portion. Therefore, Constant Temperature Endurance Test and Thermal Cycle Endurance Test have been conducted under the reactor operating conditions except irradiation to examine the rolled joint integrity. (1)Constant Temperature Endurance Test. In fiscal 1988, Constant Temperature Endurance Test have been performed in the Component Test Loop for 2,033 hours under the reactor operating conditions (pressure 75kg/cm, temperature 280C) for the JP-3 specimen (total testing period 4,033 hours) and the JP-4, JP-5 specimens (total testing period 9,533 hours). After the endurance test it was found by the helium leak test that the rolled joint tightness was maintained enough. Therefore, it was confirmed that the reduction of the residual atress at the rolled joint portion which occurred at the initial stage of the operation did not affect the rolled joint tightness. (2)Thermal Cycle Endurance Test. The helium leak test and the ultrasonic flaw detection test were performed before and after Thermal Cycle Endurance Test (the unmber of thermal cycle increaced from 60 times to 140 times in fisical 1988), of which results showed the integrity of the rolled joint tightness and no crack propagation near the rolled joint portion. Therefore, it was confirmed that 140 times thermal cycle which was the design value for the reactor life of 30 years did not affect the rolled joint tightness and the initiation and propagation of a crack even for the specimen with 200 ppm hydrogen.
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Proceedings of International Conference on Fast Reactors and Related Fuel Cycles (FR '91), p.5 - 23, 1991/00
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PNC TN9410 88-117, 54 Pages, 1988/09
This report summarizes the results of research and development of instrumentation equipments for JOYO and MONJU. The equipments have been advanced on the process in MONJU from JOYO. This report describes R&D activities related to JOYO and MONJU, and R&D items for large scale FBR.
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PNC TN942 85-01, 64 Pages, 1985/03
In the case of fast breeder reactors, the in-service inspection of the reactor vessel must be conducted under such severe conditions as relatively high temperature, high radiation dose, and narrow space. Therefore, the heat- and radiation- resistant sensors are required, which also should be compact and flexible for remote handling and installing. Authors reviewed the state of the fiber scopes for the visual in-service examination, and discussed some problems about applicability to FBR conditions. This report presents the technical information obtained from the survey conducted in 1983, and the brief draft of the development plan including some remained problems about application to FBR.
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Hitachi Hyoron, 11 Pages, 1980/10
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PNC TN941 77-144, 69 Pages, 1977/01
With respect to mechanical sodium pump for the primary cooling system of JOYO, mock-up test has been continued on the pump test loop since April 1972, to demonstrate mechanical and hydraulic performance, and reliability for about 16,000 hrs. Material test after endurance test (about 16,000 hours) has been carried out for sodium bearing, seal ring, spring and impeller, The result is as follows. (1)small extent of pitting and slight carburization were observed in the sodium bearing. (2)small scratches which were probably caused during the installation of the inner casing and eyelashes were observed in the seal ring. (3)the increas of spring constant was found in the spring attached to the seal ring. (4)small hole corrosion on the surface, carburization, and Nickel transfer were observed in the impeller.
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3rd International Conference on Liquid Metal Engineering and Technology Production, ,
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Eda, Itsumu*; Omine, Mayumi*; Nemoto, Norimasa*; Shimizu, Tomoko*; Tanaka, Sachiko*; Kashima, Takao*; Ito, Yukari*; Taniyama, Hiroshi*; Kamei, Mitsuru*; Yonezawa, Rika; et al.
no journal, ,
no abstracts in English