scholarly journals Efficient masking of corrosion and fission products such as Ni(ii) and Pd(ii) in the presence of the minor actinide Am(iii) using hydrophilic anionic or cationic bis-triazines

2015 ◽  
Vol 51 (44) ◽  
pp. 9189-9192 ◽  
Author(s):  
Frank W. Lewis ◽  
Laurence M. Harwood ◽  
Michael J. Hudson ◽  
Udo Müllich ◽  
Andreas Geist
Keyword(s):  
Nuclear Fuel ◽  
Fission Products ◽  
Minor Actinide ◽  
Used Nuclear Fuel ◽  
Masking Agents

We report the first examples of hydrophilic 3,3′-bis(1,2,4-triazine) ligands and their application as masking agents to suppress the extraction of corrosion and fission products found in used nuclear fuel solutions.

scholarly journals Closed Fuel Cycle and Minor Actinide Multirecycling in a Gas-Cooled Fast Reactor

2009 ◽  
Vol 2009 ◽  
pp. 1-9 ◽  
Author(s):  
W. F. G. van Rooijen ◽  
J. L. Kloosterman
Keyword(s):  
Nuclear Fuel ◽  
Fast Reactor ◽  
Fuel Cycle ◽  
Fission Products ◽  
Nuclear Fuel Cycle ◽  
Future Research ◽  
Minor Actinide ◽  
Closed Fuel Cycle ◽  
Decay Heat ◽  
Closed Nuclear Fuel Cycle

The Generation IV International Forum has identified the Gas-Cooled Fast Reactor (GCFR) as one of the reactor concepts for future deployment. The GCFR targets sustainability, which is achieved by the use of a closed nuclear fuel cycle where only fission products are discharged to a repository; all Heavy Metal isotopes are to be recycled in the reactor. In this paper, an overview is presented of recent results obtained in the study of the closed fuel cycle and the influence of the addition of extra Minor Actinide (MA) isotopes from existing LWR stockpiles. In the presented work, up to 10% of the fuel was homogeneously replaced by an MA-mixture. The results are that addition of MA increases the potential of obtaining a closed fuel cycle. Reactivity coefficients generally decrease with increasing MA content. Addition of MA reduces the reactivity swing and allows very long irradiation intervals up to 10% FIMA with a small reactivity swing. Multirecycling studies show that a 600 MWth GCFR can transmute the MA from several PWRs. By a careful choice of the MA-fraction in the fuel, the reactivity of the fuel can be tuned to obtain a preset multiplication factor at end of cycle. Preliminary decay heat calculations show that the presence of MA in the fuel significantly increases the decay heat for time periods relevant to accidents (104–105s after shutdown). The paper ends with some recommendations for future research in this promising area of the nuclear fuel cycle.

Characterization of FUTURIX-FTA Irradiated Nuclear Fuel Samples

2017 ◽  
Author(s):  
Concettina Andrello ◽  
Daniel Freis ◽  
Rosa Lo Frano ◽  
Dimitri Papaioannou ◽  
Fabienne Delage
Keyword(s):  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Fission Products ◽  
Heat Rate ◽  
Current Status ◽  
High Level Waste ◽  
Minor Actinide ◽  
Spent Fuel ◽  
Post Irradiation ◽  
Irradiation Experiment

The amount of spent fuel and high-level waste already available, and which will be produced by the future NPPs operation, calls for the evaluation of any possible technological solution that could minimize the burden of their disposal: reduction of Minor Actinide (MA) content, in addition to the radiotoxicity and radioactivity, and of the generated thermal load (decay heat). In this context, R&D efforts currently focus on the development of methodologies and technical solutions for Partitioning and Transmutation. MAs and long-lived fission products are in fact the main contributors to the long-term radiotoxicity of spent nuclear fuel, and their transmutation to short-lived fission products, in fast spectrum nuclear reactors, in transmuters or in Accelerator Driven Systems (ADS), by neutron irradiation of dedicated fuels/targets, is a promising and widely investigated option. In order to provide substantial input for the safety assessment of innovative nuclear fuels dedicated to MA transmutation, several irradiation tests are being carried out. In some options, the investigated fuels/targets are uranium free, or of low uranium content, to improve the transmutation performance and contain high concentrations of MA and plutonium compounds. Two molybdenum based CER-MET fuels, called ITU-5 & ITU-6, were prepared at JRC Karlsruhe for the irradiation experiment FUTURIX-FTA (FUel for Transmutation of transURanium elements in phenIX/Fortes Teneurs en Actinide). The experiment performed from 2007 to 2009 in the Phénix reactor, France, in cooperation with CEA. The experiment ended after 235 equivalent full power days (EFPD) at a Linear Heat Rate of circa 130 W/cm and reached burn-ups of 18 %FIHMA and 13 %FIHMA, respectively. Afterwards, the pins were transported to the Hot Cells of JRC Karlsruhe for Post Irradiation Examination. After a short summary describing the fuel preparation and irradiation conditions of the FUTURIX FTA irradiation experiment, the paper will give an overview on the current status and further planning of the Post Irradiation Examinations of ITU-5 & ITU-6 at JRC Karlsruhe. Finally, the results of the characterisations will be discussed and conclusions on the irradiation performance will be drawn. The results of this experiment will help to increase the knowledge and understanding of the irradiation behaviour of metal based transmutation targets and the qualification and validation of models developed to predict fuel safety performance.

Recycling as an option of used nuclear fuel management strategy

2011 ◽  
Vol 241 (4) ◽  
pp. 1238-1242 ◽  
Author(s):  
Tomaž Žagar ◽  
Aleš Buršič ◽  
Jože Špiler ◽  
Dana Kim ◽  
Mustapha Chiguer ◽  
...  
Keyword(s):  
Nuclear Fuel ◽  
Management Strategy ◽  
Fuel Management ◽  
Used Nuclear Fuel
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