Screening of advanced cladding materials and UN–U3Si5 fuel
TLDR
In this article, the authors evaluated UN-U3Si5 fuel with Kanthal AF or APMT cladding and showed that the UO2-Zr fuel claddings performed similar to the zirconium alloy cladding in terms of safety coefficients.About:
This article is published in Journal of Nuclear Materials.The article was published on 2015-07-01 and is currently open access. It has received 60 citations till now. The article focuses on the topics: Cladding (fiber optics) & Nuclear fuel.read more
Citations
More filters
Journal ArticleDOI
Accident tolerant fuel cladding development: Promise, status, and challenges
TL;DR: A review of the development status for three accident tolerant fuel cladding technologies, namely coated zirconium-based cladding, ferritic alumina-forming alloy cladding and silicon carbide fiber-reinforced SCCM composite, is offered in this paper.
Journal ArticleDOI
A combined APT and SANS investigation of α′ phase precipitation in neutron-irradiated model FeCrAl alloys ☆
Samuel A. Briggs,Philip D. Edmondson,Kenneth C. Littrell,Yukinori Yamamoto,Richard H. Howard,Charles R. Daily,Kurt A. Terrani,Kumar Sridharan,Kevin G. Field +8 more
TL;DR: In this article, small angle neutron scattering techniques were coupled with atom probe tomography to assess the composition and morphology of the resulting α-phase precipitates, and the precipitate morphology evolution with dose exhibited a transient coarsening regime akin to previously observed behavior in aged Fe-Cr alloys.
Journal ArticleDOI
Enhanced thermal conductivity accident tolerant fuels for improved reactor safety – A comprehensive review
Wei Zhou,Wenzhong Zhou +1 more
TL;DR: In this paper, the authors investigated the performance of UO 2 -BeO composite fuel and showed that it is a good candidate to fabricate enhanced thermal conductivity fuels together with uO 2.
Journal ArticleDOI
Comparison of steady and transient flow boiling critical heat flux for FeCrAl accident tolerant fuel cladding alloy, Zircaloy, and Inconel
Soon K. Lee,Maolong Liu,Nicholas R. Brown,Kurt A. Terrani,Edward D. Blandford,Heng Ban,Colby Jensen,Youho Lee +7 more
TL;DR: In this paper, the surface thermal economy parameter ( ρ c p 3 / 2 k ) is proposed as an explanation for the observed CHF differences; this parameter is related to material's ability to avoid an irreversible dry spot formation.
Journal ArticleDOI
Neutronic Analysis on Potential Accident Tolerant Fuel-Cladding Combination U3Si2-FeCrAl
Shengli Chen,Cenxi Yuan +1 more
TL;DR: In this article, a potential accident tolerant fuel (ATF) consisting of U3Si2 fuel and FeCrAl cladding is investigated for neutronic performance, and the proposed fuel-cladding combination has less reactivity variation during its service lifetime.
References
More filters
Journal ArticleDOI
The Serpent Monte Carlo code: Status, development and applications in 2013
TL;DR: The Serpent Monte Carlo reactor physics burnup calculation code has been developed at VTT Technical Research Centre of Finland since 2004, and is currently used in over 100 universities and research organizations around the world.
Journal ArticleDOI
Advanced Oxidation Resistant Iron-Based Alloys for LWR Fuel Cladding
TL;DR: In this article, an application of advanced oxidation-resistant iron alloys as light water reactor fuel cladding is proposed, based on specific limitations associated with zirconium alloys.
Journal ArticleDOI
Neutronic analysis of candidate accident-tolerant cladding concepts in pressurized water reactors
TL;DR: In this article, the neutronics of alternate cladding materials in a pressurized water reactor (PWR) environment were analyzed and the associated neutronics penalty/advantage, changes in reactivity coefficients, and spectral variations once a transition in the cladding was made.
Journal ArticleDOI
Material property correlations for uranium mononitride
TL;DR: The experimental data for the lattice parameter (a), density (p), and mean linear thermal expansion coefficient (α) of uranium mononitride (UN) have been collected and reviewed.
Journal ArticleDOI
Material property correlations for uranium mononitride: IV. Thermodynamic properties
TL;DR: In this article, the experimental data for the specific heat, enthalpy, entropy, Gibbs free energy, and the free energy function (FEF), nitrogen and uranium vapor pressures (PN2,U), and melting point (Tm) of uranium mononitride (UN) were collected and reviewed.