nuclear fuel
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2022 ◽  
Vol 145 ◽  
pp. 104122
Author(s):  
Laura J. Bonales ◽  
Nieves Rodríguez-Villagra ◽  
Iván Sánchez-García ◽  
Oscar R. Montoro

2022 ◽  
Vol 166 ◽  
pp. 108731
Author(s):  
Qin-qin Ma ◽  
Ji Que ◽  
Qi-fa Gao ◽  
Li-juan Deng ◽  
Hai-feng Yang ◽  
...  

2022 ◽  
pp. 29-36
Author(s):  
G. A. Vityuk ◽  
V. A. Vityuk ◽  
A. D. Vurim ◽  
R. Y. Kelcingazina ◽  
B. Y. Bekmagambetova

The article is devoted to an issue of estimating the impurity gas amount in nuclear fuel in the aspect of the distracting contribution from released gases to the total pressure inside ampoule of the device in the simulating a severe accident with core melting. The paper presents a method based on measuring the pressure and temperature of gas in a closed values of the fuel elements during the fuel melting. The correctness of the developed methodology is confirmed by the results of experiments on the melting of fuel in a pulsed graphite reactor IGR with the implementation of a controlled neutron pulse.


2022 ◽  
Author(s):  
Rahul Agarwal ◽  
Rama Mohana Rao Dumpala ◽  
Manoj Kumar Sharma ◽  
Donald M Noronha ◽  
Jayashree S Gamare ◽  
...  

Recovery of Plutonium from aqueous carbonate waste solutions generated during reprocessing of spent nuclear fuel is a key concern for sustainable nuclear energy programmes and remediation of radioactive waste. Reported...


2022 ◽  
Vol 29 (1) ◽  
Author(s):  
Alexander Scott Ditter ◽  
Danil E. Smiles ◽  
Daniel Lussier ◽  
Alison B. Altman ◽  
Mukesh Bachhav ◽  
...  

Soft X-ray spectromicroscopy at the O K-edge, U N 4,5-edges and Ce M 4,5-edges has been performed on focused ion beam sections of spent nuclear fuel for the first time, yielding chemical information on the sub-micrometer scale. To analyze these data, a modification to non-negative matrix factorization (NMF) was developed, in which the data are no longer required to be non-negative, but the non-negativity of the spectral components and fit coefficients is largely preserved. The modified NMF method was utilized at the O K-edge to distinguish between two components, one present in the bulk of the sample similar to UO2 and one present at the interface of the sample which is a hyperstoichiometric UO2+x species. The species maps are consistent with a model of a thin layer of UO2+x over the entire sample, which is likely explained by oxidation after focused ion beam (FIB) sectioning. In addition to the uranium oxide bulk of the sample, Ce measurements were also performed to investigate the oxidation state of that fission product, which is the subject of considerable interest. Analysis of the Ce spectra shows that Ce is in a predominantly trivalent state, with a possible contribution from tetravalent Ce. Atom probe analysis was performed to provide confirmation of the presence and localization of Ce in the spent fuel.


2022 ◽  
Vol 8 ◽  
pp. 1
Author(s):  
Heddy Barale ◽  
Camille Laguerre ◽  
Paul Sabatini ◽  
Fanny Courtin ◽  
Kévin Tirel ◽  
...  

Scenario simulations are the main tool for studying the impact of a nuclear reactor fleet on the related fuel cycle facilities. This equilibrium preliminary study aims to present the functionalities of a new tool and to show the wide variety of reactors/cycles/strategies that can be studied in steady state conditions and validated with more details thanks to dynamic code. Different types of scenario simulation tools have been developed at CEA over the years, this study focuses on dynamic and equilibrium codes. Dynamic fuel cycle simulation code models the ingoing and outgoing material flow in all the facilities of a nuclear reactor fleet and their evolutions through the different nuclear processes over a given period of time. Equilibrium fuel cycle simulation code models advanced nuclear fuel cycles in equilibrium conditions, i.e. in conditions which stabilize selected nuclear inventories such as spent nuclear fuel constituents, plutonium or some minor actinides. The principle of this work is to analyze different nuclear reactors (PWR, AMR) and several fuel types (UOX, MOX, ERU, MIX) to simulate advanced nuclear fleet with partial and fully plutonium and uranium multi-recycling strategies at equilibrium. At this first stage, selected results are compared with COSI6 simulations in order to evaluate the precision of this new tool, showing a significant general agreement.


2022 ◽  
Vol 8 ◽  
pp. 2
Author(s):  
Andrei A. Andrianov ◽  
Olga N. Andrianova ◽  
Ilya S. Kuptsov ◽  
Leonid I. Svetlichny ◽  
Tatyana V. Utianskaya

The paper presents the results of a case study on evaluating performance and sustainability metrics for Russian nuclear energy deployment scenarios with thermal and sodium-cooled fast reactors in a closed nuclear fuel cycle. Ten possible scenarios are considered which differ in the shares of thermal and sodium-cooled fast reactors, including options involving the use of mixed uranium-plutonium oxide fuel in thermal reactors. The evolution of the following performance and sustainability metrics is estimated for the period from 2020 to 2100 based on the considered assumptions: annual and cumulative uranium consumption, needs for uranium enrichment capacities, fuel fabrication and reprocessing capacities, spent fuel stocks, radioactive wastes, amounts of plutonium in the nuclear fuel cycle, amounts of accumulated depleted uranium, and the levelised electricity generation cost. The results show that the sustainability of the Russian nuclear energy system can be significantly enhanced through the intensive deployment of sodium-cooled fast reactors and the transition to a closed nuclear fuel cycle. The authors have highlighted some issues for further considerations, which will lead to more rigorous conclusions regarding the preferred options for the development of the national nuclear energy system.


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