Published September 1992 | Version v1
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Posttest analysis of MIST Test 3109AA using TRAC-PF1/MOD1

Description

This document discusses a posttest calculation and analysis of Multi-loop Integral System Test (MIST) 3109AA as the nominal test for the MIST program. It is a test of a small-break loss-of-coolant accident (SBLOCA) with a scaled 10-cm2 break in the B1 cold leg. The test exhibited the major post-SBLOCA phenomena, as expected, including depressurization to saturation, intermittent and interrupted loop flow, boiler-condenser mode cooling, refill, and postrefill cooldown. Full high-pressure injection and auxiliary feedwater were available, reactor coolant pumps were not available, and reactor-vessel vent valves and guard heaters were automatically controlled. Constant level control in the steam-generator secondaries was used after steam-generator secondary refill and symmetric steam-generator pressure control was used. We performed the calculation using TRAC-PF1/MODI. Agreement between test data and the calculation was generally reasonable. All major trends and phenomena were correctly predicted. It is believed that the correct conclusions about trends and phenomena will be reached if the code is used in similar applications

Availability note (English)

MF available from INIS under the Report Number; OSTI as TI93003212; NTIS; INIS; GPO.

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Additional details

Publishing Information

Imprint Pagination
71 p.
Report number
NUREG/CR--5887

Optional Information

Contract/Grant/Project number
Contract W-7405-ENG-36
Funding organization
Nuclear Regulatory Commission, Washington, DC (United States).
Secondary number(s)
LA-UR--89-2158.