Abstract
The important factors of future nuclear reactors are efficiency of nuclear fuel, minimization of nuclear wastes, advancement of nuclear safety and high nuclear proliferation resistance. We investigate one of these innovative water reactors; Fast Spectrum Light Water Reactor (FLWR) . It has unique construction for the reactor core but the fuel cladding material will be exposed in high internal pressure, axial load and complex temperature distribution. Therefore, we conducted a specially designed fatigue-creep test that simulated several parameters (thermal distribution, temperature variation, internal pressure variation and binding stress) to evaluate an applicability of fuel cladding material for FLWR. Zircalloy-2 which is common cladding material was used for the test. Test result was confirmed to compare the deformation value between tested and calculated. The result showed the evaluation method could control several parameters simultaneously and the deformation value after the test coincided to the calculated value. This method is sufficient to evaluate thermal deformation characteristics for FLWR.
