Viability of thorium-based nuclear fuel cycle for the next generation nuclear reactor: Issues and prospects

UE Humphrey, MU Khandaker - Renewable and Sustainable Energy …, 2018 - Elsevier
This paper presented a review on the past, present and the future of thorium fuel cycle. The
aim of this study is to evaluate the developments in thorium fuel cycle, looking at the …

[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 …

Superionics: crystal structures and conduction processes

S Hull - Reports on Progress in Physics, 2004 - new.iopscience.iop.org
Superionic conductors are compounds that exhibit exceptionally high values of ionic
conductivity within the solid state. Indeed, their conductivities often reach values of the order …

BISON theory manual the equations behind nuclear fuel analysis

BISON is a finite element-based nuclear fuel performance code applicable to a variety of fuel
forms including light water reactor fuel rods, TRISO particle fuel, and metallic rod and plate …

Uranium

I Grenthe, J Drożdżynński, T Fujino, EC Buck… - The chemistry of the …, 2006 - Springer
By 1911, the atomic weight of uranium had been refined to 238.5 (Gmelin, vol. A2, 1980a).
The natural isotope 235 U was discovered in 1935 by mass spectrometry. The artificial …

[图书][B] Plutonium

DL Clark, SS Hecker, GD Jarvinen, MP Neu - 2006 - Springer
The element plutonium occupies a unique place in the history of chemistry, physics,
technology, and international relations. After the initial discovery based on submicrogram …

Design of SEALER, a very small lead-cooled reactor for commercial power production in off-grid applications

J Wallenius, S Qvist, I Mickus, S Bortot… - … Engineering and Design, 2018 - Elsevier
In this paper, the conceptual design of a small lead-cooled nuclear reactor intended to
replace diesel-power in off-grid applications is presented. In a vessel of dimensions making …

GERMINAL, a fuel performance code of the PLEIADES platform to simulate the in-pile behaviour of mixed oxide fuel pins for sodium-cooled fast reactors

M Lainet, B Michel, JC Dumas, M Pelletier… - Journal of Nuclear …, 2019 - Elsevier
GERMINAL is a fuel performance code developed by the French Commission of Alternative
and Atomic Energies (CEA) to simulate the in-pile behaviour of mixed oxide fuel pins for …

Applicability of CeO2 as a surrogate for PuO2 in a MOX fuel development

HS Kim, CY Joung, BH Lee, JY Oh, YH Koo… - Journal of Nuclear …, 2008 - Elsevier
The applicability of cerium oxide, as a surrogate for plutonium oxide, was evaluated for the
fabrication process of a MOX (mixed oxide) fuel pellet. Sintering behavior, pore former effect …

Presentation of the xM3 Test Case of the P2M Simulation Exercise and Modeling with the Fuel Performance Code ALCYONE

V D'Ambrosi, J Sercombe, S Béjaoui… - Nuclear …, 2024 - Taylor & Francis
This paper presents simulations of the xM3 power ramp with the fuel performance code
ALCYONE performed during an international simulation exercise organized within the …