Hafnium(IV) complexation with oxalate at variable temperatures

2017 ◽  
Vol 105 (5) ◽  
Author(s):  
Mitchell T. Friend ◽  
Nathalie A. Wall
Keyword(s):  
Solvent Extraction ◽  
Fission Product ◽  
Nuclear Fuel ◽  
Aqueous Phase ◽  
Spent Nuclear Fuel ◽  
Fission Products ◽  
Extraction Technique ◽  
Complexing Agents ◽  
Solvent Extraction Technique

AbstractAppropriate management of fission products in the reprocessing of spent nuclear fuel (SNF) is crucial in developing advanced reprocessing schemes. The addition of aqueous phase complexing agents can prevent the co-extraction of these fission products. A solvent extraction technique was used to study the complexation of Hf(IV) – an analog to fission product Zr(IV) – with oxalate at 15, 25, and 35°C in 1 M HClO

scholarly journals New trends in the reprocessing of spent nuclear fuel. Separation of minor actinides by solvent extraction

2016 ◽  
Vol 71 (1) ◽  
pp. 123
Author(s):  
Jerzy Narbutt
Keyword(s):  
Solvent Extraction ◽  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Fission Products ◽  
Natural Uranium ◽  
Heterocyclic Ligands ◽  
High Level Nuclear Waste ◽  
Extraction Processes ◽  
High Level

<p>Recycling of actinides from spent nuclear fuel by their selective separation followed by transmutation in fast reactors will optimize the use of natural uranium resources and minimize the long-term hazard from high-level nuclear waste. This paper describes solvent extraction processes recently developed, aimed at the separation of americium from lanthanide fission products as well as from curium present in the waste. Depicted are novel poly-N-heterocyclic ligands used as selective extractants of actinide ions from nitric acid solutions or as actinide-selective hydrophilic stripping agents.</p>

Study of nitrate complex formation with trivalent Pm, Eu, Am and Cm using a solvent extraction technique

2004 ◽  
Vol 92 (12) ◽  
Author(s):  
Sofie Andersson ◽  
C. Ekberg ◽  
J-O. Liljenzin ◽  
M. Nilsson ◽  
G. Skarnemark
Keyword(s):  
Solvent Extraction ◽  
Complex Formation ◽  
Nuclear Fuel ◽  
Stability Constants ◽  
Spent Nuclear Fuel ◽  
Aqueous Media ◽  
Separation Process ◽  
Nitrate Complex ◽  
The Stability ◽  
Solvent Extraction Technique

SummaryThe separation of actinides and lanthanides is an important question in the treatment of spent nuclear fuel in the transmutation concept. To find an efficient and well functioning separation process it is necessary to study the chemistry of the elements in the two groups in different aqueous media. The stability constants of the nitrate complex formation with Pm, Eu, Am and Cm were determined using solvent extraction. The extraction was studied using the synergistic system of 2,6-bis-(benzoxazolyl)-4-dodecyloxylpyridine and 2-bromodecanoic acid in

scholarly journals Treatment of Spent Nuclear Fuel for Separation, Immobilization and Disposal of Heat Generating High Level Fission Products, Caesium and Strontium

2017 ◽  
Vol 30 (1) ◽  
pp. 37-42
Author(s):  
Md Akhlak Bin Aziz ◽  
Afrin Ahsan ◽  
Md Monsurul Islam Khan ◽  
Zahid Hasan Mahmood
Keyword(s):  
Fission Product ◽  
Nuclear Fuel ◽  
Nuclear Waste ◽  
Chemical Engineering ◽  
Spent Nuclear Fuel ◽  
Fission Products ◽  
Extraction Process ◽  
Safe Disposal ◽  
Synthetic Rock ◽  
High Level

Separation of heat generating, high level fission product caesium and strontium from spent nuclear fuel boosts the capacity of waste repositories by as much as fifty times. For efficient use of already scarce repositories, separation of such fission products is mandatory. Separations of caesium and strontium using Chlorinated Cobalt Dicarbollide (CCD), PEG (Polyethylene Glycol), UNEX process and by Calixarenes or Fission Product Extraction Process (FPEX) were discussed. The UNEX method was then proposed as the most feasible method option. Following separation, nuclear waste immobilization techniques for such high-level fission product were discussed. The techniques included usage of concrete, glass and synthetic rock. Among them synthetic rock was identified as the most suitable one for immobilization of high-level nuclear waste. Finally, a safe disposal system with necessary required geology was shown for safe disposal of the waste.Journal of Chemical Engineering, Vol. 30, No. 1, 2017: 37-42

Extraction of β-Sitosterol from Jatropha Seed Oil

2011 ◽  
Vol 233-235 ◽  
pp. 1210-1213 ◽  
Author(s):  
Shu Yu Liu ◽  
Hao Lu ◽  
Li Jie Sun ◽  
Xin Guo
Keyword(s):  
Solvent Extraction ◽  
Hydrochloric Acid ◽  
Zinc Chloride ◽  
Seed Oil ◽  
Extraction Technique ◽  
Power Ratio ◽  
Optimum Conditions ◽  
Jatropha Seed ◽  
Solvent Extraction Technique

Solvent extraction technique was applied for the extraction of β-Sitosterol from jatropha seed oil．The optimum conditions for the lab scale extraction were obtained at 30ml solvent, 0.05g magnesium power, ratio of hydrochloric acid to zinc chloride of 1/1.75 (ml/g) and tetrahydrofuran as a solvent. Under the optical conditions, the yield of β-sitosterol was up to 3.27mg/g.

Conceptual Study of Neutron Physics of Nuclear Fuel Cycle for Ceramic Fast Reactor

2021 ◽  
Author(s):  
Xuesong Yan ◽  
Yaling Zhang ◽  
Yucui Gao ◽  
Lei Yang
Keyword(s):  
High Temperature ◽  
Nuclear Fuel ◽  
Fast Reactor ◽  
Spent Nuclear Fuel ◽  
Fuel Cycle ◽  
Fission Products ◽  
Nuclear Fuel Cycle ◽  
Purification Method ◽  
Neutron Physics ◽  
Conceptual Study

Abstract To make the nuclear fuel cycle more economical and convenient, as well as prevent nuclear proliferation, the conceptual study of a simple high-temperature dry reprocessing of spent nuclear fuel (SNF) for a ceramic fast reactor is proposed in this paper. This simple high-temperature dry (HT-dry) reprocessing includes the Atomics International Reduction Oxidation (AIROX) process and purification method for rare-earth elements. After removing the part of fission products from SNF by a HT-dry reprocessing without fine separation, the remaining nuclides and some uranium are fabricated into fresh fuel which can be used back to the ceramic fast reactor. Based on the ceramic coolant fast reactor, we studied neutron physics of nuclear fuel cycle which consists operation of ceramic reactor, removing part of fission products from SNF and preparation of fresh fuels for many time. The parameters of the study include effective multiplication factor (Keff), beam density, and nuclide mass for different ways to remove the fission products from SNF. With the increase in burnup time, the trend of increasing 239Pu gradually slows down, and the trend of 235U gradually decreases and become balanced. For multiple removal of part of fission products in the nuclear fuel cycle, the higher the removal, the larger the initial Keff.

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