A study of different cases of VVER reactor core flooding in a large break loss of coolant accident.

Autor: Bezrukov, Yury Alekseevich, Schekoldin, Vladimir Ivanovitc, Zaitsev, Sergey Ivanovich, Churkin, Andrey Nikolaevich, Lisenkov, Evgeny Aleksandrovich
Předmět:
Zdroj: EPJ Nuclear Sciences & Technologies; 2016, Vol. 2, p1-11, 11p
Abstrakt: The paper covers the results of VVER core reflooding studies in fuel assembly (FA) mockup of 126 fuel rod simulators with axial power peaking. The experiments were performed for two types of flooding. The first type is top flooding of the empty (steamed) FA mockup. The second type is bottom flooding of the FA mockup with level of boiling water. The test parameters are as follows: the range of the supplied power to the bundle is from 40 to 320 kW, the cooling water flow rate is from 0.04 to 1.1 kg/s, the maximum temperature of the fuel rod simulator is 800 °C and the linear heat flux is from 0.1 to 1.0 kW/m. The test results were used for computer code validation. [ABSTRACT FROM AUTHOR]
Databáze: Complementary Index