ASSESSMENT OF FISSION GAS RELEASE FROM FUEL RODS OF QINSHAN NUCLEAR POWER PLANT

M. Szuta

Institute of Atomic Energy, 05-400 Otwock/Swierk, Poland


The code for assessment of gas-leaking fuel elements number for a VVER-440 reactor has been adopted to the Qinshan Nuclear Power Plant. A brief description of the code is given along with a modification necessary to treat the fuel. Promising results of calculation has been obtained for the explanation of the fission gas release from the fuel rods of Qinshan NPP type tested at the Institute of Atomic Energy of China.