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*; *; Fukumura, Nobuo*; *; *; *; *
PNC TN1410 91-063, 239 Pages, 1991/08
no abstracts in English
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Nuclear Engineering and Design, 106(2), p.163 - 178, 1988/02
Times Cited Count：2 Percentile：31.31(Nuclear Science & Technology)None
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Nuclear Engineering and Design, 103(2), p.151 - 164, 1987/08
Times Cited Count：9 Percentile：66.63(Nuclear Science & Technology)None
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PNC TN941 85-69, 201 Pages, 1985/04
Doppler reactivity has been calculated with uniform temperature within fuel rod for reactor design. Therefore, actual temperature distribution is close to parabolic, depending on the central and surface temperature, because the dependence of PuO
-UO conductivity with the temperature and nonuniformity of heat generation within the fuel rod affect the temperature distribution in opposite sense. Doppler broadening effect is considered mainly due to resonance absorption in 
U on the surface of fuel rod. In the present study, doppler reactivity effect due to nonuniform temperature within fuel rod was investigated by the RABBLE/WIMS-ATR code. We considered several temperature distributions in the cases of normal operation, transient and LOCA for a 36-rod cluster cell. The following results are summarized. (1)It is necessary to divide the fuel rod into about 10 concentric-annular sub-regions at equal intervals for calculations with nonuniform temperatures. (2)Doppler reactivities calculated with nonuniform temperatures in the cases of normal operation and transient are reduced by about 5% in comparison with ones calculated with uniform temperatures. In the case of LOCA, doppler reactivities calculated with nonuniform temperatures are about 6% larger than ones calculated with uniform temparatures.
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PNC TN943 85-06, 19 Pages, 1985/01
A remote-controlled in-service inspection device has been developed for inspecting pressure tubes of the Fugen, which is a heavy water moderated and boiling light water cooled pressure-tube type reactor. The equipment is capable of performing three kinds of inspections ultrasonic flaw detection; measurement of inside diameter; and visual inspection of the internal surface. To reduce the radiation exposure of inspectors, the three kinds of detectors, with their associated electronics and drive mechanisms for vertical and rotating movements, are housed in the inspection tool assembly, which can be mounted on or removed from the pressure tubes by a refueling machine through remote control operation. The ultrasonic technique has been adopted for measurement of the internal diameter in order to shorten the inspection time. Detectors, TV camera, and electronic components used in the inspection tool assembly were selected on the basis of irradiation test results. Before inspection of the Fugen reactor, the total system was tested on a mock-up pressure tube to confirm its functions, performance, durability and reliability. Test results are; (1)The ultrasonic flaw detector can detect an artificial flaw of 2.0mm in lengthg, 0.1 mm in width and 0.1 mm in depth with S/N=7dB; (2)The inside diameter measurement system can measure the inside diameter, ranging from 117,5mm to 119.5mm, to an accuracy of 
20
m; (3)An artificial flaw of 2.0mm in length, 0.1 mm in width and O.1mm in depth can be observed by the internal surface observation system. The equipment was used for the inspection of ten pressure tubes of the Fugen reactor during the May 1984 annual inspection. No degradation of the performance of the equipment was observed even after 55 hours of inspection under a maximum dose rate of 2.5
10
R/h. Based on these results, the functions and performance of the equipment in practical use were fully confirmed.
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PNC TN941 82-246VOL1, 92 Pages, 1982/11
PNC-TN941-82-246VOL1.pdf:3.39MB
The Component Test Loop (CTL) has been operated for several kinds of tests under mechanical and thermal conditions similar to reactor "Fugen". Its water chemistry has been controlled by all-volatile-treatment (AVT) for inhibiting corrosion of the loop components and piping which is composed of carbon steel. The CTL has a schedule of performing corrosion tests of main components and materials used in "Fugen". For these tests, the CTL is required to simulate water chemistry of the real reactors and to operate under neutral water condition. However, there is no experience of operating carbon steel boilers with neutral water treatment (NWT) in Japan. Therefore, preliminary tests were done to examine the possibility of NWT operation of the CTL and to make clear what kinds of apparatus to be added to the loop. Test results are as follows. (1)Throughout a period of steady state operation of the CTL with neutral water treatment, the following water chemistry was obtained at the inlet of a test section; electrical conductivity: 0.3S/cm, disolved oxygen: 150ppb, PH: 6.25, total iron: 2.5ppb, total cupper: 15-20ppb, SiO: 25ppb, organie impurity (UV value): 0.005. These values are totally close to those of the primary coolant of reactor "Fugen", and indicates that the CTL can be operated under a water condition simulating "Fugen". (2)The total iron content of 2.5 ppb under neutral water conditions is 1/4 to 1/2 times as low as that under AVT water conditions, and indicates neutral water treatment is excellent anti-corrosive treatment for carbon steel pipings. (3)It was found that cupper, SiO and organic impurities had been accumulated in the CTL through the past 10 years. Where these impurities come from and how to remove them from the loop are discussed. (4)Corrosion tests of iron, cupper and its alloy specimens showed cupper and its alloy are much corrosive than iron under the neutral water condition. 0bservation and analysis of inner surfaces ...
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PNC TN952 82-02, 118 Pages, 1982/02
This report is a users' manual of a thermohydraulic computer code 'HAPI-II' for the pressure tube type HWR, FUGEN. The prediction of channel coolant flow distribution is important for the evaluation of thermal design margin (MCPR). This prediction is more important than LWRs, for the pressure tube type reactors like the FUGEN in which inlet and outlet pipes are longer and have more complex shapes. Therefore, a number of hydraulic tests using full scale test facilities have been carried out at PNC O-arai Engineering Center, much valuable data have been obtained for fuel assemblies, pipes, and bends. On the basis of these data, a 'HAPI' code has been developed. It is comfirmed that the 'HAPI-II' code has an accuracy of 4% on the recirculation flow rate and of 7% on the core flow distribution compared with actually measured data in FUGEN reactor for all operating conditions. This program is written in FORTRAN language and its size is 500 Kbyte, computing time is approximately 1 minute for a half core of FUGEN Reactor.
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PNC TN952 80-15, 138 Pages, 1980/11
The removal of decay heat from a pressure tube type reactor at a loss of power accident (LOPA) or a total black out (TBO) depends on natural circulation with low water level. In this case, the information on the natural circulation rate is one of the important items to estimate the ability of core cooling. This report is a users' manual of a computer code "NASCH" which calculates the steady natural circulation rate for a single channel loop. This code can deal with the natural circulation in not only the HTL loop but also HWR. The validity of this code is confirmed by comparison between the calculated results and the HTL data. The program is written in Fortran and its size is 160 Kbyte.
*; *; *; Fukuda, Kenji*; ; *
PNC TN941 78-13VOL1, 266 Pages, 1978/01
PNC-TN941-78-13VOL1.pdf:18.12MB
Nuclear characteristics of 54-pin fuel assembly for commercial FUGEN were studied from the view points of reactor safety and fuel-cycle economy. Coolant void reactivity and power coefficient for the analysis of reactor safety, and burnup and fuel-cycle indicator for evaluating fuel-cycle cost were investigated in reference to lattice pitch, uranium and plutonium enrichment. From the present study, the following results are summarized. (1)Uranium and plutonium fuel can be used in a wide range of enrichment. (2)Natural uranium or low enriched uranium (
1wt% 
U) fuel mixed plutonium shows the best nuclear characteristics. (3)Nuclear characteristics are improved by more introduction of plutonium in consideration of local peaking factor and power mismatch.
Kitahara, Tanemichi; ; ; ; ; ; ;
Journal of Nuclear Science and Technology, 13(3), p.111 - 118, 1976/03
Times Cited Count：7no abstracts in English
; ; Kitahara, Tanemichi;
JAERI-M 6200, 22 Pages, 1975/08
no abstracts in English
Kitahara, Tanemichi; ; ; ; ; ; ; ;
JAERI-M 5962, 34 Pages, 1975/01
no abstracts in English
Kitahara, Tanemichi; ;
Journal of Nuclear Science and Technology, 5(11), p.596 - 598, 1968/00
no abstracts in English
JRR-2 Control Office; Kambara, Toyozo; Shoda, Katsuhiko; Hirata, Yutaka; Shoji, Tsutomu; Kohayakawa, Toru; Morozumi, Minoru; Kambayashi, Yuichiro; Shitomi, Hajimu; Kokanezawa, Takashi; et al.
JAERI 1027, 57 Pages, 1962/09
no abstracts in English
Kambara, Toyozo; Shoda, Katsuhiko; Hirata, Yutaka; Shoji, Tsutomu; Haginoya, Kinichi; Kohayakawa, Toru; Yamaki, Jikei; Yokota, Mitsuo; Horiki, Oichiro; Yuhara, Shunichi; et al.
JAERI 1023, 120 Pages, 1962/09
no abstracts in English
JRR-2 Operations Office; Kambara, Toyozo; Shoda, Katsuhiko; Hirata, Yutaka; Shoji, Tsutomu; Haginoya, Kinichi; Kohayakawa, Toru; Yamaki, Jikei; Yokota, Mitsuo; Horiki, Oichiro; et al.
JAERI 1024, 79 Pages, 1962/08
no abstracts in English
