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Senzaki, Masao; ; Mochiji, Toshiro;
IAEA Symposium on Nuclear Fuel Cycle and Reactor, 0 Pages, 1997/06
None
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PNC TN9410 87-025, 277 Pages, 1987/02
Fault tree analysis and reliability analysis were conducted for the advanced reactor shut down system using the curie point magnet, thermo-switch, and articulated rod, in order to preclude ATWS out of DBA. Conclusions are as follows. (1) There is a good chance of customary shut down system having an unavailability of 10
/R
Y. (2) Advanced shut down system will gain an availability of 5 times as before. Safety requirements are shown as, (a) Curie point temperature 
+1.64
TL : nominal curie point temperature. : standard deviation. TL : limiting temperature. (b) Failure rate of thermal switch 10
/hour (c) It is essential to pay attention that articulated rod reduces an availability in the case of excepting the large scale earthquake. (3) Availability improvement of only '2' light be expected because of the temperature rise of coolant boundary.
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PNC TN9410 86-109, 136 Pages, 1986/10
This report describes the result of a seismic analysis for inserting performance of control rod for the 1000MWe large scale LMFBR. In this analysis maximum horizontal seismic displacements between the reactor core and the upper core structure (UCS) are estimated. The coupled model of the reactor structure and reactor building are used for the seismic response analysis. S-R model and Lattice model are used for soil-structure interaction analysis. The design earthquake S
and the simulated earthquake by the mixed phase method are used for the input earthquake. In the results of analysis maximum seismic displacement between the reactor core and the UCS for the S
earthquake is about 13mm, and it makes sure that the results satisfy the permitted value. The time history of the response acceleration at the core support plate is derived for the input data of the core vibration analysis. And digital values of the floor response spectrum at reactor support level are attached in the appendix.
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PNC TN941 85-79, 157 Pages, 1985/05
In-sodium test was carried out for MONJU primary prototype pump, having a new hydrostatic bearing and convection suppressing fin. The test parameters were sodium level in the pump and flow of the seal gas. The test results are summarized as follows. (1)The pump operated satisfactorily on each condition of low sodium level with and without seal gas and normal sodium level without seal gas. This shows the pump has the soundness even in the cases of primary piping broken and the seal gas stopped. (2)It was obtained from the low sodium level test that each time of radial temperature difference for both inner and outer casings was its maximum and stable respectively. (3)It was approved that the maximum radial temperature differences for both inner and outer casings were increased with the time passing and sodium level falling, and also approved that the time which the temperature differences became their maximum were short with sodium level falling. (4)Maximum displacement of outer casing was smaller than the approved value at the lowest sodium level test, so it seems there is no problem on the real pump operation. (5)The test showed that convection suppressing fin was useful why the displacement of the casings were suppressed, because the times of the maximum radial temperature differences of the casings were late and displacement of outer casing was increased slowly. (6)It was approved that the pony motor of the pump was stopped and started again satisfactorily at the lowest sodium level.
