Quick Look Report for Semiscale MOD-2C Test S-FS-6. [Simulating PWR transient from SG line break]
Results of a preliminary analysis of the third test performed in the Semiscale MOD-2C Steam Generator Feedwater and Steam Line Break (FS) experiment series are presented. Test S-FS-6 simulated a pressurized water reactor transient initiated by a 100% break in a steam generator bottom feedwater line downstream of the check valve. With the exception of primary pressure, the initial conditions represented the initial conditions used for the C-E System 80 Final Safety Analysis Report (FSAR) Appendix 15B calculations. The transient included an initial 600s period in which only automatic plant protection systems responded to the initiating event. This period was followed by a series of operator actions necessary to stabilize the plant and a subsequent operator controlled natural circulation cooldown and depressurization with upper head void collapse method investigations. The test results provided a measured evaluation of the effectiveness of the automatic responses in minimizing primary system overpressurization and operator actions in stabilizing and recovering the plant. Test data also provided a basis for comparison with other tests in the series of the effects of break size on primary overpressurization and primary-to-secondary heat transfer.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 6402544
- Report Number(s):
- EGG-SEMI-7022; ON: TI86003216
- Country of Publication:
- United States
- Language:
- English
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