Anton Pshenichnikov

Microstructure and mechanical properties of Zircaloy-4 cladding hydrogenated at temperatures typical for loss-of-coolant accident (LOCA) conditions

Anton Pshenichnikov, J. Stuckert, M. Walter · Nuclear Engineering and Design · 2014 · 32 citations · Full text

Natural Sciences, Materials Engineering, Materials Science +16

Features of a control blade degradation observed in situ during severe accident conditions in boiling water reactors

Anton Pshenichnikov, Saishun Yamazaki, D. Bottomley et al. · Journal of Nuclear Science and Technology · 2019 · 23 citations

Engineering, Materials Science, Nuclear Engineering +16

Hydride precipitation, fracture and plasticity mechanisms in pure zirconium and Zircaloy-4 at temperatures typical for the postulated loss-of-coolant accident

Anton Pshenichnikov, J. Stuckert, M. Walter · Nuclear Engineering and Design · 2016 · 22 citations

Natural Sciences, Geology, Materials Science +14

New research programme of JAEA/CLADS to reduce the knowledge gaps revealed after an accident at Fukushima-1: introduction of boiling water reactor mock-up assembly degradation test programme

Anton Pshenichnikov, Masaki Kurata, D. Bottomley et al. · Journal of Nuclear Science and Technology · 2019 · 18 citations

Engineering, Nuclear Engineering, Nuclear Materials +9

Comparison of the observed Fukushima Dai-Ichi Unit 2 debris with simulated debris from the CLADS-MADE-01 control blade degradation test

Anton Pshenichnikov, Yuji Nagae, Masaki Kurata · Journal of Nuclear Science and Technology · 2020 · 16 citations

Engineering, Environmental Sciences, Nuclear Engineering +13