nuclear fuels
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Author(s):  
Samuel Moxon ◽  
Jonathan Skelton ◽  
Joshua Simon Tse ◽  
Joseph Flitcroft ◽  
Atsushi Togo ◽  
...  

Thorium dioxide (ThO2) is a promising alternative to mixed-oxide nuclear fuels due to its longer fuel cycle and resistance to proliferation. Understanding the thermal properties, in particular the thermal conductivity,...


2021 ◽  
Vol 557 ◽  
pp. 153246
Author(s):  
Jonathan Johnson A. ◽  
Ryan Wilkerson ◽  
Stephen DiPietro ◽  
Gregory B. Thompson
Keyword(s):  

2021 ◽  
Vol 556 ◽  
pp. 153154
Author(s):  
T. Vidal ◽  
L. Gallais ◽  
J. Faucheux ◽  
H. Capdevila ◽  
J. Sercombe ◽  
...  

Materials ◽  
2021 ◽  
Vol 14 (20) ◽  
pp. 6160
Author(s):  
Philip Kegler ◽  
Martina Klinkenberg ◽  
Andrey Bukaemskiy ◽  
Gabriel L. Murphy ◽  
Guido Deissmann ◽  
...  

Cr-doped UO2 as a modern nuclear fuel type has been demonstrated to increase the in-reactor fuel performance compared to conventional nuclear fuels. Little is known about the long-term stability of spent Cr-doped UO2 nuclear fuels in a deep geological disposal facility. The investigation of suitable model materials in a step wise bottom-up approach can provide insights into the corrosion behavior of spent Cr-doped nuclear fuels. Here, we present new wet chemical approaches providing the basis for such model systems, namely co-precipitation and wet coating. Both were successfully tested and optimized, based on detailed analyses of all synthesis steps and parameters: Cr-doping method, thermal treatment, reduction of U3O8 to UO2, green body production, and pellet sintering. Both methods enable the production of suitable model systems with a similar microstructure and density as a reference sample from AREVA. In comparison with results from the classical powder route, similar trends upon grain size and lattice parameter were determined. The results of this investigation highlight the significance of subtly different synthesis routes on the properties of Cr-doped UO2 ceramics. They enable a reproducible tailor-made well-defined microstructure, a homogeneous doping, for example, with lanthanides or alpha sources, the introduction of metallic particles, and a dust-free preparation.


Materials ◽  
2021 ◽  
Vol 14 (19) ◽  
pp. 5568
Author(s):  
Sanjib Chowdhury ◽  
Dario Manara ◽  
Oliver Dieste-Blanco ◽  
Davide Robba ◽  
António Pereira Gonçalves

Nanograined nuclear materials are expected to have a better performance as spallation targets and nuclear fuels than conventional materials, but many basic properties of these materials are still unknown. The present work aims to contribute to their better understanding by studying the effect of grain size on the melting and solid–solid transitions of nanograined UC2−y. We laser-heated 4 nm–10 nm grain size samples with UC2−y as the main phase (but containing graphite and UO2 as impurities) under inert gas to temperatures above 3000 K, and their behavior was studied by thermal radiance spectroscopy. The UC2−y solidification point (2713(30) K) and α-UC2 to β-UC2 solid–solid transition temperature (2038(10) K) were observed to remain unchanged when compared to bulk crystalline materials with micrometer grain sizes. After melting, the composite grain size persisted at the nanoscale, from around 10 nm to 20 nm, pointing to an effective role of carbon in preventing the rapid diffusion of uranium and grain growth.


2021 ◽  
Vol 28 ◽  
pp. e00278
Author(s):  
Andrea Paulillo ◽  
Jonathan M. Dodds ◽  
Stephen J. Palethorpe ◽  
Paola Lettieri

Author(s):  
Sung-Wook Kim ◽  
Seung Youb Han ◽  
Junhyuk Jang ◽  
Min Ku Jeon ◽  
Eun-Young Choi

Water ◽  
2021 ◽  
Vol 13 (11) ◽  
pp. 1607
Author(s):  
Mariano Venturini ◽  
Ariana Rossen ◽  
Patricia Silva Paulo

To produce nuclear fuels, it is necessary to convert uranium′s ore into UO2-ceramic grade, using several quantities of kerosene, methanol, nitric acid, ammonia, and, in low level, tributyl phosphate (TBP). Thus, the effluent generated by nuclear industries is one of the most toxic since it contains high concentrations of dangerous compounds. This paper explores biological parameters on real nuclear wastewater by the Monod model in an ORP controlled predicting the specific ammonia oxidation. Thermodynamic parameters were established using the Nernst equation to monitor Oxiders/Reductors relationship to obtain a correlation of these parameters to controlling and monitoring; that would allow technical operators to have better control of the nitrification process. The real nuclear effluent is formed by a mixture of two different lines of discharges, one composed of a high load of nitrogen, around 11,000 mg/L (N-NH4+-N-NO3−) and 600 mg/L Uranium, a second one, proceeds from uranium purification, containing TBP and COD that have to be removed. Bioprocesses were operated on real wastewater samples over 120 days under controlled ORP, as described by Nernst equations, which proved to be a robust tool to operate nitrification for larger periods with a very high load of nitrogen, uranium, and COD.


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