Feasibility to convert an advanced PWR from UO2 to a mixed U/ThO2 core – Part I: Parametric studies
Sign Up to like & getrecommendations! Published in 2017 at "Annals of Nuclear Energy"
DOI: 10.1016/j.anucene.2016.12.010
Abstract: Abstract This work presents the neutronics and thermal hydraulics feasibility to convert the UO 2 core of the Westinghouse AP1000 in a (U-Th)O 2 core by performing a parametric study varying the type of geometry… read more here.
Keywords: feasibility convert; convert advanced; geometry; advanced pwr ... See more keywords
Development of a multi-compartment containment code for advanced PWR plant
Sign Up to like & getrecommendations! Published in 2018 at "Nuclear Engineering and Design"
DOI: 10.1016/j.nucengdes.2018.05.001
Abstract: Abstract HPR1000 (Hua-long Pressurized Reactor) Nuclear Power Plant is a type of third generation advanced PWR developed in China. In this study, a home-made multi-compartment containment code, ATHROC (Analysis of Thermal Hydraulic Response Of Containment),… read more here.
Keywords: code; multi compartment; model; compartment containment ... See more keywords
Investigation of the safety features of advanced PWR assembly using SiC, Zr, FeCrAl and SS-310 as cladding materials
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DOI: 10.1038/s41598-021-96954-9
Abstract: In this work, SiC (Silicon carbide), FeCrAl (ferritic), SS-310 (stainless steel 310) and Zirconium are simulated by MCNPX (Monte Carlo N‐Particle eXtended) code as cladding materials in advanced PWR (Pressurized Water Reactor) assembly. A number… read more here.
Keywords: using sic; cladding materials; safety; assembly ... See more keywords