Development of accident tolerant FeCrAl-ODS fuel cladding for BWRs in Japan
K Sakamoto, Y Miura, S Ukai, NH Oono… - Journal of Nuclear …, 2021 - Elsevier
The FeCrAl-oxide dispersion strengthened (ODS) alloy is a promising candidate alloy for the
accident tolerant fuel (ATF) cladding of light water reactors (LWRs) and has been recently …
accident tolerant fuel (ATF) cladding of light water reactors (LWRs) and has been recently …
Phenomenology of BWR fuel assembly degradation
M Kurata, M Barrachin, T Haste… - Journal of Nuclear …, 2018 - Elsevier
Severe accidents occurred at the Fukushima-Daiichi Nuclear Power Station (FDNPS) which
required an immediate re-examination of fuel degradation phenomenology. The present …
required an immediate re-examination of fuel degradation phenomenology. The present …
Improvement of the European thermodynamic database NUCLEA
S Bakardjieva, M Barrachin, S Bechta… - Progress in Nuclear …, 2010 - Elsevier
Modelling of corium behaviour during a severe accident requires knowledge of the phases
present at equilibrium for a given corium composition, temperature and pressure. The …
present at equilibrium for a given corium composition, temperature and pressure. The …
Analysis of safety margin of in-vessel retention for AP1000
YP Zhang, SZ Qiu, GH Su, WX Tian - Nuclear engineering and Design, 2010 - Elsevier
In-vessel retention (IVR) of core melt is a key severe accident management strategy adopted
by most operating nuclear power plants and advanced light water reactors (ALWRs), AP600 …
by most operating nuclear power plants and advanced light water reactors (ALWRs), AP600 …
Corium phase equilibria based on MASCA, METCOR and CORPHAD results
SV Bechta, VS Granovsky, VB Khabensky… - … Engineering and Design, 2008 - Elsevier
Experimental data on component partitioning between suboxidized corium melt and steel in
the in-vessel melt retention (IVR) conditions are compared. The data are produced within the …
the in-vessel melt retention (IVR) conditions are compared. The data are produced within the …
Severe accident management concept of the VVER-1000 and the justification of corium retention in a crucible-type core catcher
VB Khabensky, VS Granovsky, SV Bechta… - Nuclear Engineering …, 2009 - koreascience.kr
First ex-vessel core catcher has been applied to the practical design of NPPs with VVER-
1000 reactors built in China (Tyanvan) and India (Kudankulam) for severe accident …
1000 reactors built in China (Tyanvan) and India (Kudankulam) for severe accident …
Phase Diagram and Metastable Phases in the LaPO4–YPO4–(H2O) System
MO Enikeeva, OV Proskurina, VV Gusarov - Russian Journal of Inorganic …, 2024 - Springer
Phase formation in the LaPO4–YPO4–(H2O) system have been studied under hydrothermal
conditions at T~ 230° C and after heat treatment in air in the temperature range 1000–1400° …
conditions at T~ 230° C and after heat treatment in air in the temperature range 1000–1400° …
Late phase fuel degradation in the Phébus FP tests
M Barrachin, O De Luze, T Haste, G Repetto - Annals of Nuclear Energy, 2013 - Elsevier
The aim of the experimental Phébus FP program was to study the degradation phenomena
and the behaviour of the fission products during the progression of a severe accident. The …
and the behaviour of the fission products during the progression of a severe accident. The …
High-temperature characterization of melted nuclear core materials: Investigating corium properties through the case studies of in-vessel and ex-vessel retention
J Delacroix, C Journeau, P Piluso - Frontiers in Energy Research, 2022 - frontiersin.org
During a severe accident in a nuclear reactor, the molten core—or corium—may be
relocated into the reactor vessel's lower plenum in case of core support plate failure. The …
relocated into the reactor vessel's lower plenum in case of core support plate failure. The …
Structure, stability, and actinide leaching of simulated nuclear fuel debris synthesized from UO2, Zr, and stainless-steel
A Kirishima, D Akiyama, Y Kumagai, R Kusaka… - Journal of Nuclear …, 2022 - Elsevier
To evaluate the chemical structure and stability of nuclear fuel debris comprising UO 2, Zr,
and stainless-steel (SUS) generated during the Fukushima Daiichi Nuclear Power Plant …
and stainless-steel (SUS) generated during the Fukushima Daiichi Nuclear Power Plant …