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Suzuki, Hisanori; Nagayama, Tetsuya; Horigome, Kazushi; Ishibashi, Atsushi; Kitao, Takahiko; Surugaya, Naoki
Nihon Hozen Gakkai Dai-11-Kai Gakujutsu Koenkai Yoshishu, p.214 - 219, 2014/07
The Tokai Reprocessing Plant (TRP) is developing the technology to recover uranium and plutonium from spent nuclear fuel. There is an analytical laboratory which was built in 1978, as one of the most important facilities for process and material control analyses at the TRP. Samples taken from each process are analyzed by various analytical methods using hot cells, glove boxes and hume-hoods. A large number of maintenance work have been so far done and different types of experience have been accumulated. This paper describes our achievements in the maintenance activities at the analytical laboratory at the TRP.
Yamamoto, Masahiko; Ishibashi, Atsushi; Nagayama, Tetsuya; Surugaya, Naoki; Kurosawa, Akira; Hiyama, Toshiaki
JAEA-Technology 2010-040, 28 Pages, 2010/12
JAEA-Technology-2010-040.pdf:0.97MB
Precise analysis of plutonium is necessary for material control and safeguards in nuclear facility. Thus, controlled-potential coulometry, which yields absolute results and high precision, was applied for the determination of plutonium. The coulometry system and sample pretreatment procedures were optimized following ISO12183:2005. Plutonium sample prepared from NBL CRM-126 Pu metal was measured and agreed well with certified value. For spike preparation of isotope dilution mass spectrometry (IDMS), plutonium solution was prepared from MOX powder. Plutonium content was 15.5995 mgPu/g. The uncertainty was calculated by ISO/BIPM Guide to the Expression of Uncertainties in Measurements. The relative expanded uncertainty was 0.023% with confidence interval of 95%. The results were in good agreement with those obtained by IDMS. Thus the proposed coulometry method was successfully applied for the determination of plutonium at the highest level of precision and accuracy.
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PNC TN9410 87-001, 22 Pages, 1987/01
This report presents an operation experience of the auxiliary cooling system from January, 1982 to September, 1986. Outline of the operation experience is following ; (1)There has not been any serious trouble on the primary auxiliary cooling system in the term. Operation time of the primary auxiliary cooling system to remove reactor core residual heat during the reactor shut down outage (refueling outage) was about 3400 hours. The primary auxiliary circulating pump has been automatically started 65 times on the scheduled tests. Total operation time of the primary auxiliary cooling system was about 3900 hours after initial sodium filling of the cooling system. (2)Operation time of the secondary auxiliary cooling system with 100% flow rate was about 34000 hours. The secondary auxiliary circulation pump was tripped 11 times during about 34000 hours operation by; (a)Loss of commercial power and various tests, -10 times (b)High temperature of circulation pump coil, - 1 time. High temperature of circulation pump coil was caused by loss of cooling air with the obstacles in the cooling pump filter in May, 1982. This caused no influence to the plant at that time since the reactor decay heat had been sufficiently cooled down. The secondary auxiliary cooling system has been in no trouble except for the trip by high temperature of circulation pump coil. Total operation time of the secondary cooling system after initial sodium filling of the system was about 73000 hours.
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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.
Yamamoto, Masahiko; Ishibashi, Atsushi; Nagayama, Tetsuya; Surugaya, Naoki; Kurosawa, Akira
no journal, ,
no abstracts in English