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by ac calorimetryTateiwa, Naoyuki; Haga, Yoshinori; Matsuda, Tatsuma; Ikeda, Shugo; Nakashima, Miho*; Thamizhavel, A.*; Settai, Rikio*; Onuki, Yoshichika
Journal of the Physical Society of Japan, 75(Suppl.), p.174 - 176, 2006/08
We have investigated the physical properties of Heavy Fermion superconductors by the ac calorimetry under high pressure using a thermocouple. The method is powerful tool since the high sensitive measurement of the heat capacity is possible and the precise pressure dependence of transition temperatures such as the superconducting transition can be determined. In this conference, I would like to report our investigations on the heavy fermion superconductors CePtSi, CeNiGe and UIr. We have made pressure phase diagram of these compounds and discuss the relation between the magnetism and superconductivity.
Kimura, Nobuyuki; Tokuhiro, Akira; Kamide, Hideki
JNC TN9400 2000-027, 181 Pages, 2000/02
JNC-TN9400-2000-027.pdf:10.28MB
A quantitative evaluation on thermal striping, in which temperature fluctuation due to convective mixing among jets causes thermal fatigue in structural components, is of importance for reactor safety. ln this study, a water experiment was performed using vertical and parallel triple jets, those are cold jet on center and hot jets on both side. The experimental parameter was discharged velocity of the triple-jet and local temperature and velocity were measured by ultrasound Doppler velocimetry and movable thermocouples. The objective is a quantification of the mixing process in the multiple-jet. Under isovelocity condition, the jets oscillated periodically and mixing among thejets was promoted by periodic oscillation. The periodic oscillation was dependent on the Strouhal number based on the discharged velocity. Under non-isovelocity condition, on the other hand, the jets did not oscillate periodically and mixing among the jets progressed more gentle compared with the case under isovelocity condition. The tempwrature fluctuation could be decomposed into coherent and random components using the phase averaging process. The rate of the coherent component in the temperature fluctuation increased and the rate of random component in temperature fluctuation decreased in proportion as the discharged velocity was increased.
Ito, Takao;
Fusion Engineering and Design, 39-40, p.123 - 128, 1998/00
Times Cited Count：4 Percentile：38.63(Nuclear Science & Technology)no abstracts in English
Shimoyama, Kazuhito; Usami, Masayuki; Miyake, Osamu; ; ; Tanabe, Hiromi
PNC TN9450 97-007, 81 Pages, 1997/03
None
Iwata, Koji; *; *; *; *; *; *
PNC TN9410 97-042, 8 Pages, 1997/03
A design guide for flow-induced vibration of thermometer wells is proposed to prevent the recurrence of the failure of thermometer wells, which was the direct cause of the 1995 sodium leak incident of the secondary main piping of the prototype fast breeder reactor MONJU. As a supplement to the technical standards in force for MONJU, the design guide specifies the methods of evaluation and the design criteria on structural integrity against flow-induced vibration for thermometer wells, which are inserted into pipes of fast breeder reactors. The design guide is a PNC's (Power Reactor and Nuclear Fuel Development Corporation) internal guide for MONJU, which is to be used, with the permission of outside authorities, to confirm the integrity of the existing equipments as well as to make an improved design of thermometer wells. The proposed design guide was prepared by the Special Working Group on Thermometer Design Guide, organized in PNC during the period from May to November, 1996.
PNC TN9410 96-154, 103 Pages, 1996/07
Temperature response test was conducted using the sodium loop facility of structural engineering section to confirm the characteristics of the well-type thermocouples which are used in the main cooling systems of MONJU. FEM analyses were carried out to justify the results obtained from the test in the view point of analytical study. Conclusion are as follows. (1)The same dependency for the time constant of the well-type thermocouples on the flow rate the initial temperature and the range of temperature of sodium was obtained between test and analysis. (2)It is confirmed that the time constant of the well-type thermocouples dose not depend on the film coefficient in the range of flow rate of the test, but it depends on the change rate of sodium temperature. (3)It is confirmed that the dependency of the time constant on temperature is cased by thermophysical properties of the material of the well-type thermocouples. (4)It is found from the parametric analysis of the gap width between sheath and well that the gap width affects the time constant considerably. It is supposed that the maximum delay of the time constant is about 5 to 7 second for the well-type thermocouple which has the maximum tolerance.
Aoto, Kazumi; ; ; ; ; Hirakawa, Yasushi
PNC TN9410 97-076, 29 Pages, 1996/06
This report describes the check of the thermocouple well at the inlet of the intermediate heat exchanger (IHX) of C-loop of the secondary heat tansfer system of the prototype fast breeder reactor Monju, regarding the sodium leak accident of the thermocouple well at the outlet of the IHX of the same loop of the secondary heat transfer system of the same plant Monju. Various tests and inspections were performed to check damages at the part with rapid diameter change of the thermocouple well where stress concentration may occur, and to get the information about the integrity of the welded part between the thermocouple well and the attachment. The thermocouple well, the rapid diameter change part, larger and smaller part, respectively, of the thermocouple well, and welded part between the thermocouple well and the attachments were examined as written below. (1)Accurate measurement of the dimension. (2)Vibration test by tapping the thermocouple well. (3)Non destructive testing at some points. (4)Chemical composition analysis. (5)Microscopic observation of metalogical structure. (6)Detailed observation around the rapid diameter change part. (7)Hardness test. (8)Research on corrosion at the clearance. (9)Structure strength test of the thermocouple well. (10)Bending test of the thermocouple's sheath at high temperature.
Ara, Katsuyuki
Hihakai Kensa, 45(3), p.189 - 194, 1996/00
no abstracts in English
pellets and thermocouple re-instrumentation to fuel rod; Saito, Junichi; ; Endo, Yasuichi; ; Nakagawa, Tetsuya; ; Kawamata, Kazuo; ; Kawamura, Hiroshi; et al.
JAERI-Tech 95-037, 87 Pages, 1995/07
no abstracts in English
; Ara, Katsuyuki
Keisoku To Seigyo, 33(12), p.1070 - 1075, 1994/12
no abstracts in English
Ara, Katsuyuki; Katagiri, Masaki; ; *
Keisoku To Seigyo, 33(8), p.700 - 707, 1994/08
no abstracts in English
; Ara, Katsuyuki
Journal of Nuclear Science and Technology, 31(6), p.609 - 616, 1994/06
Times Cited Count：1 Percentile：17.86(Nuclear Science & Technology)no abstracts in English
Ara, Katsuyuki; Katagiri, Masaki; ; *; K.P.Termaat*; T.Johnsen*
Nihon Genshiryoku Gakkai-Shi, 35(11), p.999 - 1014, 1993/11
Times Cited Count：1 Percentile：18.76(Nuclear Science & Technology)no abstracts in English
; ; ; Oyamada, Rokuro; Saito, Minoru
Proc. of 4th Asian Symp. on Research Reactors, 10 Pages, 1993/00
no abstracts in English
Yanagisawa, Kazuaki; Soyama, Kazuhiko; Ichikawa, Hiroki; ; Hoshino, Osamu; ; ; ; Kanazawa, Hiroyuki; Kimura, Yasuhiko; et al.
JAERI-M 91-114, 67 Pages, 1991/08
no abstracts in English
*
PNC TN9410 90-103, 126 Pages, 1990/07
Thermal transient strength tests of a Welded Vessel Model is carring out in Therma1 Transient Strength Test Facility for Structures. The objective of this test is to grasp the thermal transient strength of fast breeder reactor's components and to develop a life estimation method for creep fatigue failure. The model is designed and fabricated in order to grasp the thermal creep-fatigue life of SUS304 and modified SUS316 under the noteworthy typical stress distribution encountered in the structures design of Fast Breeder Reactors. This report shows the results of thermal stress analysis and creep-fatigue damage evaluation of the model. The analytical model was divided the test model into five portions, namely a inlet nozzle, an upper vessel, a lower vessel, an outlet nozzle and an inner shell ring. Thermal transient condition used in the analysis is the same that used in design of the model.
Ara, Katsuyuki; ; ; *; *
FAPIG, 0(125), p.19 - 27, 1990/07
no abstracts in English
; ; ; *
Journal of Nuclear Science and Technology, 24(6), p.480 - 489, 1987/06
Times Cited Count：2 Percentile：29.75(Nuclear Science & Technology)no abstracts in English
