Simulation of a main steam line break with steam generator tube rupture using trace

Conference · Sun Jul 01 04:00:00 EDT 2012

OSTI ID:22105727

Gallardo, S.; Querol, A.; Verdu, G. ^[1]

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1. Departamento de Ingenieria Quimica Y Nuclear, Universitat Politecnica de Valencia, Camino de Vera s/n, 46022, Valencia (Spain)

A simulation of the OECD/NEA ROSA-2 Project Test 5 was made with the thermal-hydraulic code TRACE5. Test 5 performed in the Large Scale Test Facility (LSTF) reproduced a Main Steam Line Break (MSLB) with a Steam Generator Tube Rupture (SGTR) in a Pressurized Water Reactor (PWR). The result of these simultaneous breaks is a depressurization in the secondary and primary system in loop B because both systems are connected through the SGTR. Good approximation was obtained between TRACE5 results and experimental data. TRACE5 reproduces qualitatively the phenomena that occur in this transient: primary pressure falls after the break, stagnation of the pressure after the opening of the relief valve of the intact steam generator, the pressure falls after the two openings of the PORV and the recovery of the liquid level in the pressurizer after each closure of the PORV. Furthermore, a sensitivity analysis has been performed to know the effect of varying the High Pressure Injection (HPI) flow rate in both loops on the system pressures evolution. (authors)

• Research Organization: American Nuclear Society, Inc., 555 N. Kensington Avenue, La Grange Park, Illinois 60526 (United States)
• OSTI ID: 22105727
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
42 ENGINEERING
APPROXIMATIONS
DEPRESSURIZATION
FLOW RATE
PRESSURE RANGE MEGA PA 10-100
PWR TYPE REACTORS
RELIEF VALVES
RUPTURES
SENSITIVITY ANALYSIS
SIMULATION
STEAM GENERATORS
STEAM LINES
TEST FACILITIES
THERMAL HYDRAULICS
TUBES