Progress report for large leak sodium-water reaction study No.1; Large leak sodium-water reaction test report (No.7)

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The study to establish the safe design of LMFBR MONJU's steam generator system against the large leak sodium-water reaction is conducing by Power Reactor & Nuclear Fuel Development Corporation. This report includes seven topics which have been presented to the meetings of Atomic Energy Society of Japan, etc. during 1977. Summaries of these topics are as follow; (1)A computer program SWAC-11 was developed to predict the water leak rate from the ruptured heat transfer tube in the steam generator. The basic equations used and method of numerical calculation were explained. The sensitivity survey calculations for various parameters used in the code and the demonstration calculation of the case of MONJU's evaporator were reported. (2)A computer program SWAC-13 was developed to ptedict the pressure and flow behavior in the secondary cooling system, i.e. the quasistatic pressure build up, sodium/hydrogen gas flow in the SG vessels and secondary sodium circuit, and flow characteristics of pressure relief line and the hydrogen gas reliese into the atmosphere. The modeling, basic equations and the method of numerical calculation of the program were reported, and the applicability to SWAT-3 tests was demonstrated. (3)The reaction vessel drain line of SWAT-3 facility was chocked with sodium-water reaction products after water injection test Run-3. In order to understand the cause of chocking, the investigations of the reaction product and temperature distributions in the drain line, and the chemical analysis and the freezing temperature measurement of the reaction products were performed. Those results were summarized quantitatively in this chapter. (4)In order to make clear the flow characteristic of the pressure relief line, we tried to rearrange the data of two test runs of SWAT-1 rig which were obtained by the various kind of the sensors attached on the relief line. It became clear from those investigations that the sodium/hydrogen-gas two phase flow in the ...