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Terakado, Tsuguo; Morimoto, Makoto; Izawa, Osamu; Ishida, Koichi; Hoshino, Katsuaki; Suzuki, Shinya; Ito, Hideaki; Aoki, Hiroshi; Odo, Toshihiro
JNC TN9430 2004-003, 87 Pages, 2004/03
JNC-TN9430-2004-003.pdf:2.86MB
This paper describes the results of Secondary Cooling System main pumps test ,which were done as a part of JOYO MK-3 function test. The function tests were cexcuted to get the operating characteristics of secondary cooling system, after the Intermediate Heat Exchangers, Dump Heat Exchangers, secondary main pump motors, pump speed control board and rheostat were replaced in the MK-3 conversion. These tests are composed of six items. These tests purpose are confirmed in the function of the Main pumps, sodium purification system and argon cover gas pressure control system in Secondary Cooling System. (1) SKS-205-1: flow control test, (2) SKS-205-2: flow coast down characteristics test, (3) SKS-205-3: running operation test, (4) SKS-205-4: pump vibration measurement test, (5) SKS-212: secondary sodium purification system electromagnetic-pump flow control test, (6) SKS-213: argon cover gas pressure in secondary cooling system pressure control test function tests are satisfied the design criteria. We have confirmed the system performance of the main pump, secondary sodium purification system and argon cover gas pressure control system in the Secondary Cooling System after the MK-3 conversion.
Terakado, Tsuguo; Hoshino, Katsuaki; Suzuki, Shinya; Ito, Hideaki; Aoki, Hiroshi; Odo, Toshihiro
JNC TN9410 2004-008, 55 Pages, 2004/03
JNC-TN9410-2004-008.pdf:1.82MB
The automatic control rod operation system was developed to control the JOYO reactor power automatically in all operation modes(critical approach, cooling system heat up, power ascent and power descent), development began in 1989. Prior to applying, we are examined possibility of apply to the automatic control rod operation guide system which developed in MK-2 operation to get the control rod operation guide data in MK-3 performance tests. The main results are as follows: (1).Critical approach mode in control rod operation guide function will be need tuning of fuzzy algorisms structure for changed MK-3 reactor critical point. (2).Cooling system heet up mode, power ascent mode and power descent mode will be supply to good guidance at MK-3 reactor operation. Because, power change rate and cooling system heet up rate same MK-2 reactor operation. (3).Plant operation guide function will be need change, based on MK-3 reactor operation manual. (4).The automatic control rod operation guide system will be need renewal for system maintainability.
; Kawai, Masashi; ; ; ; Okubo, Toshiyuki;
PNC TN9410 94-094, 69 Pages, 1994/03
As the final step of development of a control rod guide system (rod guider), it has been conducted to display information concerning the rod guider operation and the current plant conditions on a CRT in Japanese, to tell information for operators and to predict more accurately the stroke of each control rod to be driven at a reactor power adjustment operation since 1992, in oder to improve a function of man-machine interface of the rod guider. The development of the rod guider was completed with the following good results as expected. (1)The function of man-machine interface of the rod guider was improved to display information on a CRT in Japanese. (2)The voice guidance contributed to obtain higher operational reliability and to lower the load on the operators. (3)The rod guider provided the same function as operation manuals of Joyo because all operation procedures in the manuals were inputted into the rod guider. And the timely operation guides provided by the rod guider evabled non-skilled operators to control the reactor in the same manner as the experienced ones. (4)The difference of the predicted and actual rod stroke to be driven at the reactor power adjustment operation was reduced to less than 
0.2mm by both the existing inverse multiplication method and the experiences gained in the past five reactor power adjustment operations.
; ; ; Usui, Masahiro*; ; ; Terunuma, Seiichi*
PNC TN9410 89-099, 95 Pages, 1989/05
This report described plant operational management during the 7th annual inspection of Experimental Fast Reactor JOYO from September 1988 to January 1989. One of the important purposes of this inspection is to find a rationality inspection method for LMFBR plants. Therefore, almost inspection items with various modifications and preparation for irradiation were completed for about 3.5 months. This is the shortest record on JOYO. The inspection schedule was very tight and complicated, but it was successfully finished in cooperation with members of operation and maintenance section, by adequate operational management and advanced preparation for inspection. Useful operational management techniques for rationality inspection were obtained, through the experience of 7th annual inspection.
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PNC TN9410 88-029, 33 Pages, 1988/03
This report describes incidents which occured in JOYO in FY1983. In FY1983, MK-II characteristic tests were carried out till July, and then JOYO was operated at 100MW from August 9th to September 30th, and from october 12th to December 1st. From December, the 4th annual inspection which contained self-inspection and modification was started. 335 incidents required repair in FY1983, and this request h has increased year by year. We consider that these are owing to increasing average components. Pressure containment vessel atmosphere conditioning system, secondary cooling system, buildings, auxiliary cooling water system and primary cooling system rank higher than other systems. These 5 system occupy large portion than previous years. Although repairing of valves and instruments decreased repairing of buildings, pumps, and motor increased suddenly.
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PNC TN941 85-164, 73 Pages, 1985/11
The auxiliary plant service system consists of three different water cooling systems which remove heat of the components and emergency power supply diesel generators, and adjust atmospheric conditioning of inside and outside of the containment vessel. The whole system had been operated favorably since January 1976 when the functional test was conducted, till March 1980 when cycle 7 at 100MW operation was completed, and the total operating hour reached 79,000 hours. Although there exsisted some discontinuities in operation, the whole plant operation was not affected by taking adequate measures. Developent of corrosion in the water circuit and components in the system, loss of automatic restart function in case of loss of power, and temporal coolant loss due to chocked strainer in diesel generator cooling system were happened. For the respective problems, measures were taken. Water quality control measure as introduction of a counteragent injection system and a filtration facility has been taken place. And an improvement of start circuitly has been conducted to provide reliable and stable operation. Further, more reliable and stable operation is expected through the completion of exchange of the cooling tower and temperature control circuitly, which is scheduled to be provided in 1985.
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PNC TN941 85-27, 206 Pages, 1985/02
The primary overflow system of Experimental Fast Reactor "JOYO" was operated for about 55,000 hours from the in-sodium functional test in February 1976, to the end of 4 the cycle operation at 100 MWt in August 1984. During the period, the overflow system was operated satisfactorily for the purpose. In the beginning of the period, however, it was found that a thermal transient condition exceeds a design limit at overflow return pipe while a process to recover the system after the loss of electric power. In order to prevent unnecessary thermal transient, operation procedure and test results were studied and new operation procedure was established. Although the new procedure satisfies the required conditions, it takes 10 to 16 hours to recover the plant in case of loss of electric power. Therefore, for the efficiency of plant operability, the study should be continued.
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PNC TN941 84-117, 81 Pages, 1984/07
The secondary cooling system of Experimental Fast Reactor "JOYO" has been operated about for 52,000 hours as operation time since the initial sodium charge time in 1976 till the end of Reactor Run 6th 75MW in Dec., 1981. at the same time, the reactor has been operated about for 12,800 hours, the secondary pumps operated about for 40,000 hours and main blowers operated about for 10,000 hours. During the period we acquired some valuable operational experiences such as the motor brush's wear of the secondary main pump (A) and natual wear of main air coolers. But except them we could operate the system without severe problems. The report describes generally the operation and maintenance history of Secondary main pumps, the operation history of the main blowers and the temperature differences two IHX's of the secondary systems.