Abstract After the Fukushima-Daiichi event, there has been notable progress in develo**
accident-tolerant fuel (ATF) cladding designs to improve light-water reactor (LWR) safety …

Chloride-induced stress corrosion cracking (CISCC) is a critical threat to stainless steel (SS)
spent nuclear fuel (SNF) and radioactive materials storage canisters currently in service …

Silicon microchannels with microporous decorated sidewalls were applied to enhance water
flow boiling heat transfer, especially the critical heat flux (CHF). In experiments, a CHF of …

We present the results of experimental investigations aimed at evaluating the thermal–
hydraulic performance of chromium-coated zircaloy, ie, one of the most promising accident …

We elucidate the separate effect of a thin Cr coating deposited by physical vapor deposition
(PVD) on the subcooled flow boiling performance of zircaloy-4. First, we run flow boiling …

First of a kind high spatial and temporal resolution temperature measurements of
Pressurized Water Reactor and Boiling Water Reactor simulated fuel pins (high heat flux …

TiAlSiN coatings are deposited on zircaloy-4 by multi-arc ion plating at 50 A, 60 A and 70 A,
respectively. The macro-morphology, micro-morphology, chemical composition and phases …

Thermal–hydraulics (TH) experiments have been on the progress to evaluate boiling heat
transfer characteristics of accident tolerant fuel (ATF) candidates for further supporting the …

The APMT FeCrAl alloy is a cladding candidate for the accident-tolerant fuel (ATF) systems
in light water reactors (LWRs) due to its ability to form a protective Al 2 O 3 film on the …

Abstract Studying Zr (Cr, Fe) 2 Laves phase oxidation is vital for deepening our
understanding of the oxidation mechanism of accident tolerant fuel (ATF) Cr-coated Zr and …