Abstract:
INR-Pitesti TRIGA research reactor is basically a pool type reactor with a special design in order to fulfill the requirements for material testing, power reactor fuel and nuclear safety studies. The dual-core concept involves the operation of a TRIGA-SSR high-flux, steady-state research and material testing reactor at one end of a large pool, and the independent operation of an annular-core pulsing reactor (TRIGA-ACPR) at the other end of the pool. The safety evaluation involved a several design basis accidents. The first scenario address the failure of a single fuel pin classing (due to material deficiencies) with the consequent release of fission products. For training purposes, and to exercise our ability to conduct Level-3 PSA studies, a severe accident scenario involving 14-MW INR-TRIGA research reactor has been developed. In this scenario is assumed that a large part of the reactor hall roof or a heavy object escaped from the crane hook is dropped over the 14-MW TRIGA-SSR core, resulting in mechanical damage of the core. The evaluation of the radiological consequences considers both early and late consequences.