Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Tamii, Atsushi*; Pellegri, L.*; S
derstrm, P.-A.*; Allard, D.*; Goriely, S.*; Inakura, Tsunenori*; Khan, E.*; Kido, Eiji*; Kimura, Masaaki*; Litvinova, E.*; et al.
European Physical Journal A, 59(9), p.208_1 - 208_21, 2023/09
Times Cited Count：1 Percentile：0.02(Physics, Nuclear)no abstracts in English
Toyoda, Shin*; Inoue, Kazuhiko*; Yamaguchi, Ichiro*; Hoshi, Masaharu*; Hirota, Seiko*; Oka, Toshitaka; Shimazaki, Tatsuya*; Mizuno, Hideyuki*; Tani, Atsushi*; Yasuda, Hiroshi*; et al.
Radiation Protection Dosimetry, 199(14), p.1557 - 1564, 2023/09
Times Cited Count：0 Percentile：0.01(Environmental Sciences)Interlaboratory comparison studies are important for radiation dosimetry in order to demonstrate how the technique is universally available. The set of standard samples are examined in each participating laboratory in the present study. After a set of standard samples together with the samples with unknown doses, which were prepared in the same laboratory as the standard samples, are measured at a participating laboratory, those samples are sent to another participating laboratory for next measurement. There is some small difference observed in the sensitivity (the slope of the dose response line) of the standard samples while the differences in the obtained doses for the samples with unknown doses are rather systematic, implying that the difference is mostly due to the samples but not to measurements.
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 TJ9164 94-006, 133 Pages, 1994/03
This report gives an applicability of SWAT-3 facility and contents of the reconstruction in order to confirm a DBL (Design Basis Leak) for the demonstration reactor SG. (1).Test Cndition and test case. Evaluation of the wall temperature for adjacent heat transfer tubes under the sodium-water reaction event was performed. (a)As the effect of tube rupture due to overheating, failure of upper part of the helical coil was severer than one of the lower part. (b)The wall temperature depends on the water side condition. (c)Reference test condition, whici is water leak rale about 1 kg/s, failure of upper part of the helical coil and 30% partial load, was selected. A total of ten test cases were decided. (2).System and Components Design. (a)Large leak sodium-water reaction analyses including water injection rate analysis and quasi-steady pressure analysis were performed. The maximum water leak rate of 1 DEG was 7.2 kg/s and the water leak rate at the quasi-steady state was 3.1 kg/s. The maximum pressure was 18.1kg/cm
a at the piping between the reaction vessel and IHX, the pressure was within the design condition of SWAT-3 facility. (b)Based on the results of the large leak sodium-water reaction analyses, a reaction vessel, water heaters and a dump tank were designed and their design specification were clarified. The reaction vessel was a scale of one third of the demonstration reactor SG and it was designed to be able to conduct the water injection test twice with one test unit. (c)A system and piping diagram, and many kinds of list (Piping list, Valve list, instrumentlist) were made up. (3).Reconstruction scope and arrangement plan. The reconstruction scope and a layout for the components and piping were clarfied and the arrange ment plans were made up. (4)Reconstruction period. The recoastruction period and man power for the design, fabrication, inspection and installation were studied and the reconstruction schedule was made up.
Inoue, Tatsuya; Taniyama, Hiroshi
PNC TG033 82-01(6), 23 Pages, 1982/02
Recently most Japanese nuclear plants have examined the appropriateness and correctness of the piping design by field insitu vibration testing.
Nakano, Makoto*; Furukawa, Kiyoshi; Ito, Yoshio; Inoue, Tatsuya; Matsuno, Yoshiaki
PNC TG033 82-01(1), 26 Pages, 1982/01
The preliminary design of experimental fast reactor JOYO was started in 1965. After thid design, three steps of conceptual designs are carried out, and main parameters were fixed during these steps. This paper describes the operatin experiences which contain functional test beore criticality, initial criticality and low power testing, power ascension tests to 50 MWt operation, power ascension tests to 75 MWt and 75 MWt operation.
*; *; *; *; *; *; *
PNC TN941 80-59VOL2, 164 Pages, 1980/04
PNC-TN941-80-59VOL2.pdf:9.03MB
None
*; *; *; *; *; *; *
PNC TN941 80-59VOL1, 121 Pages, 1980/04
PNC-TN941-80-59VOL1.pdf:6.05MB
During the annual 1979 inspection of the JOYO experimental fast reactor, local leak tests were performed prior to the integrated leak rate test of the containment vessel itself. These tests, performed from the end of August to the beginning of December, were conducted to determine the leakage of the containment penetrations and auxiliary systems. The results of the tests were acceptable. [total leak rate of B test results 7.451
10
2.57110
(%/day)] [total leak rate of C test results 4.023102.77310(%/day)] This document describes the methods, procedures and results of these local leak tests. The results of past test are also described.
*; Enomoto, Toshihiko*; *; *; *; *; *
PNC TN943 80-01, 70 Pages, 1980/03
In December 1979, the integrated leak rate test (ILRT) of the JOYO reactor pressure containment vessel was conducted, as part of the JOYO annual inspection, to confirm the leaktightness of the containment vessel. The test was tbe second ILRT perfomed since initial sodium fill (the first ILRT was carried out in February, 1978). As a result of the test, leak rates of 0.034 0.021 %/day by the absolute pressure method and of 0.0390.006 %/day by the reference chamber method were obtained. These leak rates were almost the same as those obtained in the first test which were 0.0360.011 %/day and 0.036 0.008 %/day, respectively. After combining results from local leak tests and correcting for measuring errors, and the compensated leak rate was found to be well within the leak rate limit of 1.90 %/day which was established by the safety criteria of the containment. These test results demonstrate that the JOYO containment vessel manitains the leaktightness which is required for the functional integrity of the containment in an accidental condition. The successful completion of both the first and second ILRT showed that the test methods and procedures used for leak tests of the JOYO Liquid Metal Fast Reactor are accurate and practical.
*; *; *; *; *
PNC TN952 74-01, 36 Pages, 1974/01
Helium leak detecting method has been used to test integrity of JOYO sodium components in many applications. This report is concerned with technical concepts of Helium leak test achieved by experiences in construction. This document contains the following contents; fundamentals of Helium leak test, testing method in applications, typical examples on failed tests and useful experimental data.
Matsumoto, Yoshinobu*; Inoue, Masao*; Nagaishi, Ryuji; Suzuki, Tatsuya*; Ogawa, Toru
no journal, ,
no abstracts in English
