An Investigation of the Survivability of Fuel-Rod Claddings during the First Stage of the Maximum Design Basis Accident at a Nuclear Power Station with a VVER Reactor

摘要

The survivability of single tubular cpecimens of fuel-rod claddings made of El 10 and E635 alloys is experimentally investigated in the range of maximum temperature peaks 760-1450℃ and pressure differences of 1-12 MPa across the cladding under conditions of the maximum rates of heating (61-227 K/s) and cooling (6-276 K/s) typical of the first stage of the maximum design basis accident at an nuclear power station with a VVER reactor. The extent to which the experimental conditions simulate the standard conditions is analyzed.