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JAEA Reports

Experimental fast reactor "JOYO" operation report; Operation experience of auxiliary core cooling system

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PNC TN9410 87-001, 22 Pages, 1987/01

PNC-TN9410-87-001.pdf:6.71MB

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.

JAEA Reports

Experimental fast reactor "JOYO" operation report; Operation results of primary overflow system

*; ; *; *; *; *; *

PNC TN941 85-27, 206 Pages, 1985/02

PNC-TN941-85-27.pdf:5.37MB

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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