[HTML][HTML] A review of fuel performance modelling

P Van Uffelen, J Hales, W Li, G Rossiter… - Journal of Nuclear …, 2019 - Elsevier
Dr. Paul Van Uffelen graduated from the Vrije Universiteit Brussel (Belgium) and the Ecole
Nationale Supérieure Polytechnique de Grenoble (France) with a master degree in …

[HTML][HTML] The core design of a Small Modular Pressurised Water Reactor for commercial marine propulsion

A Peakman, H Owen, T Abram - Progress in Nuclear Energy, 2019 - Elsevier
If international agreements regarding the need to significantly reduce greenhouse gas
emissions are to be met then there is a high probability that the shipping industry will have to …

[HTML][HTML] A study on the corrosion behaviour of stainless steel 08Cr18Ni10Ti in supercritical water

M Šípová, D Marušáková, C Aparicio, J Procházka… - Corrosion …, 2023 - Elsevier
Abstract Austenitic stainless steel 08Cr18Ni10Ti is widely used in WWER reactor. Therefore,
it was considered one of the prospective materials for supercritical water-cooled reactors. In …

Abnormal interfacial bonding mechanisms of multi-material additive-manufactured tungsten–stainless steel sandwich structure

C Wei, H Gu, Y Gu, L Liu, Y Huang… - … Journal of Extreme …, 2022 - iopscience.iop.org
Tungsten (W) and stainless steel (SS) are well known for the high melting point and good
corrosion resistance respectively. Bimetallic W–SS structures would offer potential …

[HTML][HTML] Towards simulations of fuel rod behaviour during severe accidents by coupling TRANSURANUS with SCIANTIX and MFPR-F

G Zullo, D Pizzocri, L Luzzi, F Kremer, R Dubourg… - Annals of Nuclear …, 2023 - Elsevier
Among the applications of the multiscale modelling approach in nuclear fuel rod
performance, the coupling of integral thermo-mechanical fuel performance codes with lower …

Analysis of fuel rod behavior during loss-of-coolant accidents using the BISON code: Cladding modeling developments and simulation of separate-effects experiments

G Pastore, RL Williamson, RJ Gardner… - Journal of Nuclear …, 2021 - Elsevier
BISON is a finite-element based, multidimensional fuel performance code developed at
Idaho National Laboratory. In this paper, we present BISON modeling developments for …

[HTML][HTML] Coupled irradiation-thermal-mechanical analysis of the solid-state core in a heat pipe cooled reactor

Y Ma, J Liu, H Yu, C Tian, S Huang, J Deng… - Nuclear Engineering …, 2022 - Elsevier
The solid-state core of a heat pipe cooled reactor operates at high temperatures over 1000 K
with thermal and irradiation-induced expansion during burnup. The expansion changes the …

[HTML][HTML] Modelling and assessment of thermal conductivity and melting behaviour of MOX fuel for fast reactor applications

A Magni, T Barani, A Del Nevo, D Pizzocri… - Journal of Nuclear …, 2020 - Elsevier
Thermal conductivity and melting temperature of nuclear fuel are essential for analysing its
performance under irradiation, since they determine the fuel temperature profile and the …

Pellet-clad interaction behavior in zirconium alloy fuel cladding

MHA Piro, D Sunderland, S Livingstone… - Comprehensive …, 2020 - inl.elsevierpure.com
Abstract Pellet-Clad Interaction (PCI) in zirconium alloy cladding has been a long-standing
concern in the context of nuclear fuel reliability. Mitigation measures have constrained …

[HTML][HTML] Performance analysis and helium behaviour of Am-bearing fuel pins for irradiation in the MYRRHA reactor

L Luzzi, A Magni, S Billiet, M Di Gennaro… - … Engineering and Design, 2024 - Elsevier
Minor actinides are the main contributors to medium-and long-term radiotoxicity and heat
production in spent nuclear fuels. Research efforts are currently ongoing to explore different …