Transient analyses for China initiative Accelerator Driven System using the extended BELLA code

G Wang, J Wallenius, R Yu, W Jiang, L Zhang… - Annals of Nuclear …, 2023 - Elsevier
Abstract China initiative Accelerator Driven System (CiADS) is a 10 MW lead–bismuth
eutectic (LBE) cooled subcritical reactor loaded with UO 2 fuels in the first phase, which is …

[HTML][HTML] Proton irradiation-induced cracking and microstructural defects in UN and (U, Zr) N composite fuels

E Charatsidou, M Giamouridou, A Fazi, G Nagy… - Journal of …, 2024 - Elsevier
Proton irradiation with a primary ion energy of 2 MeV was used to simulate radiation
damage in UN and (U, Zr) N fuel pellets. The pellets, nominally at room temperature, were …

[HTML][HTML] Hydrodynamic design of the Separate Effect test facility for Flow-Accelerated Corrosion and Erosion (SEFACE) studies in liquid lead

KW Wong, I Mickus, N Torkelson, S Vasudevan… - … Engineering and Design, 2024 - Elsevier
Flow-accelerated corrosion and erosion (FACE) phenomena can be crucial for performance
of structural elements in heavy liquid metal (HLM) cooled reactor systems. Existing …

[HTML][HTML] Performance and safety evaluation of a< 10 wt% 235U enriched small lead-cooled fast reactor

F Dehlin, EP Abril, J Wallenius - Annals of Nuclear Energy, 2025 - Elsevier
We present the conceptual core design of a small lead-cooled fast reactor, for which a
critical configuration has been achieved with a uranium enrichment of 9.9 wt%. This is a …

Cladding fatigue analysis under frequent beam trips for China initiative Accelerator Driven System

G Wang, J Wallenius, Y Yang, X Su, X Li, D Yun… - Nuclear Engineering and …, 2024 - Elsevier
Abstract China initiative Accelerator Driven System (CiADS) is a 10 MW lead–bismuth
eutectic (LBE) cooled subcritical reactor, which is designed to demonstrate the engineering …

[HTML][HTML] Activation analysis of the lead coolant in SUNRISE-LFR

F Dehlin, J Wallenius - Nuclear Engineering and Design, 2023 - Elsevier
A lumped, zero-dimensional, mass transport model is combined with a depletion matrix
solver to study the influence of coolant circulation on radionuclide build-up in a small lead …

Towards multi-physics description of fuel behaviour for accidental conditions

A Pérez, J Wallenius, M Di Gennaro, L Luzzi, A Magni… - 2023 - re.public.polimi.it
In the present document, the development of well-structured multi-physics simulation
environments to complement fuel performance analysis is presented. The simulation …

Simulation of radiation damage in uranium nitride

I Andersson Neretnieks, J Planck - 2024 - diva-portal.org
During the development of new small modular gen IV nuclear reactors, promising nuclear
fuels such as uranium nitride (UN) are investigated. Radiation damage and its effects on the …

SSRT of 10-4 FeCrAl in LBE and Pb to Characterize Liquid Metal Embrittlement Effects

D Stein - 2022 - diva-portal.org
In this work the susceptibility of Fe-10Cr-4Al steel to liquid metal embitterment (LME) in low
oxygen environment was investigated. slow strain rate testing (SSRT) were conducted on 10 …

Sensibilité d'un alliage FeCrMnNi à la fragilisation par l'eutectique plomb-bismuth liquide

J Salgado Giampaoli, I Proriol Serre… - 2023 - lilloa.univ-lille.fr
Les réacteurs rapides refroidis au plomb liquide (LFR) et les ADS (accelerator driven
system) utilisent du plomb liquide ou l'eutectique plomb-bismuth (ePbBi) comme fluide …