High Power Natural Circulation (Loss of Feed Water). Simulation with TRACE5 5.0
The purpose of this work is to provide an overview of the results obtained in the simulation of a Pressurized Water Reactor (PWR) high-power natural circulation due to failure of scram during a Loss-Of-Feed Water (LOFW) transient under the assumption of total failure of High Pressure Injection System (HPIS), with actuation of Auxiliary Feed Water (AFW), in the Large Scale Test Facility (LSTF) via the thermal-hydraulic code TRACE5. The work is developed in the frame of OECD/NEA ROSA Project Test 3-2 (TR-LF-13 in JAEA). Auxiliar Feed Water was actuated when the steam generator (SG) secondary-side collapsed liquid level decreased to a determined value, providing a continuous primary-to-secondary heat removal. The primary and secondary pressures were maintained almost constant by cycle opening of pressurizer Power-Operated Relief Valve (PORV) and SG relief valves till the end of the test. A detailed model has been developed with TRACE5 following these assumptions. Results of the simulation are compared with the experimental in several graphs (primary pressure, secondary pressures, primary mass flow rates, vessel collapsed liquid levels, etc), observing an acceptable general behavior in the entire transient. In conclusion, these provide a useful development in the assessment for the predictability of thermal-hydraulic computer codes, specifically for TRACE5.
TRACE5 5.0 Thermal hydraulic simulation ROSA High Power Natural Circulation Anticipated Transient Without Scram
S. Gallardo V. Abella G. Verdú
Departamento de Ingeniería Química y Nuclear. Universidad Politécnica de Valencia. Camino de Vera s/n, Valencia (Spain)
国际会议
上海
英文
1999-2011
2010-10-10（万方平台首次上网日期，不代表论文的发表时间）