Critical heat flux enhancement of nuclear fuel cladding with nano-porous oxide film by surface anodization

Abstract

For the last 6 years after fukushima accident, lots of interest and research have been focused on severe accidents on nuclear power plants. Among these, accident-tolerant fuel (ATF) cladding is reduced oxidation reaction between steam and metal. Prevent the generation of hydrogen that caused the hydrogen explosion in fukushima. Thus, in addition to the hydrogen removal equipment such as PAR or Igniter, it also increase the safety of the nuclear power plant. according to this, various ATF cladding techniques have been developed and researched. In previous candidate, it was difficult to apply the technic to real power plant because of the high price and the threat of the integrity of the cladding. In this thesis, the critical heat flux of a cladding which increases oxidation resistance by surface anodization was measured by pool boiling experiments according to the anodization time. In addition, in order to simulate the conditions of actual nuclear power plants, the critical heat flux was measured through experiments in boric acid water condition, proton irradiated condition.