An analysis of the semiscale MOD-2C S-NH-3 test using the TRAC-PF1 computer program

Technical Report · Sun Mar 01 04:00:00 EST 1987

OSTI ID:6557856

Driskell, W E; Kullberg, C M

A calculation was performed using the TRAC-PF1/MOD1 computer program to simulate a small break, loss-of-coolant experiment where the high-pressure injection was not used to mitigate the fuel rod temperature excursion. This experiment, designated the S-NH-3 Test, simulated a 0.5% cold-leg break in a PWR and was one of a series of tests, conducted in the Semiscale Mod-2C test facility. The primary purpose for doing the calculation was to evaluate the capability of the TRAC-PF1 code to calculate the thermal-hydraulic response observed in the experiment. The evaluation employs the comparison of selected code-calculated system responses with the test data. Conclusions and recommendations on improving the quality of the calculation are included.

• Research Organization: EG and G Idaho, Inc., Idaho Falls (USA); Nuclear Regulatory Commission, Washington, DC (USA). Div. of Accident Evaluation
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 6557856
• Report Number(s): NUREG/CR-4845; EGG-2496; ON: TI87008900
• Country of Publication: United States
• Language: English

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