PNNL

Abstract

The transient fuel performance code FRAPTRAN 1.4 has been successfully used to model reactivity-initiated accident (RIA) tests performed on three very similar high burnup pressurized water reactor (PWR) rod segments. These segments were taken from rods irradiated for 5 cycles in the Vandellos-2 reactor, and all were clad with ZIRLO™ cladding. Each RIA test was performed under different coolant conditions. The first test, CIP0-1, was performed in the CABRI reactor under 280°C flowing sodium. The second test, VA-1, was performed in the NSRR reactor in a stagnant water capsule at room temperature and atmospheric pressure. The third test, VA-3, was performed in NSRR reactor in a stagnant water capsule at 285°C and elevated pressure. Two of these tests, VA-1 and VA-3 failed and the other test, CIP0-1, did not fail.