The thermodynamic properties of the f-elements and their compounds. Part 2. The lanthanide and actinide oxides

RJM Konings, O Beneš, A Kovács, D Manara… - Journal of Physical …, 2014 - pubs.aip.org
A comprehensive review of the thermodynamic properties of the oxide compounds of the
lanthanide and actinide elements is presented. The available literature data for the solid …

Fabrication and thermophysical properties of UO2-UB2 and UO2-UB4 composites sintered via spark plasma sintering

E Kardoulaki, DM Frazer, JT White, U Carvajal… - Journal of Nuclear …, 2021 - Elsevier
Uranium dioxide (UO 2) composites with uranium diboride (UB 2) and uranium tetraboride
(UB 4) have been proposed as advanced fuel candidates due to their high thermal …

Analytical determination of thermal conductivity of W–UO2 and W–UN CERMET nuclear fuels

JA Webb, I Charit - Journal of nuclear materials, 2012 - Elsevier
The thermal conductivity of tungsten based CERMET fuels containing UO2 and UN fuel
particles are determined as a function of particle geometry, stabilizer fraction and fuel …

Solid-liquid phase equilibria of Fe-Cr-Al alloys and spinels

JW Mcmurray, R Hu, SV Ushakov, D Shin… - Journal of Nuclear …, 2017 - Elsevier
Ferritic FeCrAl alloys are candidate accident tolerant cladding materials. There is a paucity
of data concerning the melting behavior for FeCrAl and its oxides. Analysis tools have …

Modeling of fission gas diffusion and release for doped

V Kocevski, MWD Cooper, DA Andersson - Journal of Nuclear Materials, 2023 - Elsevier
Uranium dioxide (Image 2) is the primary nuclear fuel in light water reactors, and its excess
neutronic reactivity can be controlled by adding burnable absorbers, such as Image 1. This …

[HTML][HTML] LEU+ loaded APR1400 using accident tolerant fuel cladding for 24-month two-batch fuel management scheme

H Khalefih, T Oh, Y Jeong, Y Kim - Nuclear Engineering and Technology, 2023 - Elsevier
In thiswork, a 24-month two-batch fuel management strategy for the APR1400 using LEU+
has been investigated, where enrichments of 5.9 and 5.2 w/o are utilized in lieu of the …

Thermodynamic reassessment of U–Gd–O system

JW McMurray, D Shin, BW Slone… - Journal of Nuclear …, 2014 - Elsevier
The CALPHAD approach is used to describe the thermodynamic properties and phase
relations in the U− Gd− O system. A compound energy formalism (CEF) model is developed …

UO2-Eu2O3 compound fuel fabrication via spark plasma sintering

EK Papynov, OO Shichalin, IY Buravlev… - Journal of Alloys and …, 2021 - Elsevier
UO 2-based nuclear fuel containing integral fuel burnable absorbers (IFBA) is an
economically and technically efficient solution for optimization of nuclear power reactors …

UO2–Y2O3 ceramic nuclear fuel: SPS fabrication, physico-chemical investigation and neutron absorption evaluation

EK Papynov, OO Shichalin, IY Buravlev… - Journal of Alloys and …, 2021 - Elsevier
The paper studies spark plasma sintering of UO 2-based ceramics nuclear fuel obtained
from a mixture of pristine urania with 2 and 8 wt% of Y 2 O 3 (integral fuel burnable …

Ceramics in the nuclear fuel cycle

SC Middleburgh, WE Lee, MJD Rushton - Advanced Ceramics for Energy …, 2020 - Elsevier
Ceramics have played a vital role in the rise of nuclear power since its inception in the mid-
20th century. Their development and improved understanding are still driving improvements …