会议专题

Simulation of the Fuel Rod Bundle Test QUENCH-03 Using the Integral Code ASTEC V2

Within the frame of the QUENCH test-program realised by Forschungszentrum Karlsruhe loss of coolant accidents in Light Water Reactors are analysed using an experimental reactor core. Main issue of this test series is the qualitative and quantitative determination of the hydrogen source term. Another issue is to ascertain the behaviour of the bundle with different absorber rod and cladding materials. The QUENCH-03 test was performed January 21st, 1999 with the objective to investigate the behaviour on reflood of PWR fuel rods with little oxidation. The simulation of the high hydrogen production rate due to a partly molten shroud like in QUENCH-03 is a challenge for all Severe Accident codes. Oxidation models of almost all codes do not simulate in detail the extension of oxidation surface due to the break up of the oxidized surfaces and the relocation of the molten shroud. The simulations of QUENCH-03 are performed with the latest version of the integral code ASTEC V2 which is being developed by IRSN (Institut de Radioprotection et de S?reté Nucléaire) in cooperation with GRS (Gesellschaft für Anlagen-und Reaktorsicherheit). The results of this calculations show that during the heat-up and transient phase ASTEC can calculate bundle and shroud temperatures in good agreement to the experimental data, only in the lower heights the temperatures are overestimated. During the quench phase and up to the end of the test the oxidation models PRATER and BEST-FIT calculate qualitative good results, the other oxidation models URBANIC and CATHCART do not calculate high temperatures and escalations, which probably appeared in the experiment. The simulation with correlations corresponding to Leistikow for the lower temperatures and Prater for higher temperatures leads to good results also. The amount of hydrogen reached in the experiment is simulated by the ASTEC oxidation models PRATER and BEST-FIT as well as with the correlations corresponding to Leistikow/Prater, the other models underestimates the amount of hydrogen.

QUENCH-03 ASTEC V2 Oxidation Hydrogen

Philipp Kruse Marco K. Koch

Ruhr-Universit?t Bochum (RUB), Chair of Energy Systems and Energy Economics,Reactor Simulation and S Ruhr-Universit?t Bochum (RUB), Chair of Energy Systems and Energy Economics,Reactor Simulation and S

国际会议

The 8th International Topical Meeting on Nuclear Thermal-Hydraulics,Operation and Safety(第八届反应堆热工水力、运行和安全国际会议 NUTHOS-8)

上海

英文

281-290

2010-10-10(万方平台首次上网日期,不代表论文的发表时间)