scholarly journals Solvent Extraction in the Treatment of Acidic High-Level Liquid Waste: Where Do We Stand?

1999 ◽  
pp. 20-50 ◽  
Author(s):  
E. Philip Horwitz ◽  
Wallace W. Schulz
Keyword(s):  
Solvent Extraction ◽  
Liquid Waste ◽  
High Level Liquid Waste ◽  
High Level

Cooperation Solidification of Cesium and Strontium

2012 ◽  
Vol 482-484 ◽  
pp. 58-61 ◽  
Author(s):  
Ming Fen Wen ◽  
Bo Yu ◽  
Min Luo ◽  
Jing Chen
Keyword(s):  
Solvent Extraction ◽  
Molecular Sieve ◽  
Liquid Waste ◽  
Fission Products ◽  
Radioactive Cesium ◽  
Energy Technology ◽  
High Level Liquid Waste ◽  
New Energy ◽  
Extraction Processes ◽  
High Level

The presence of long-lived radionuclides is a challenge to the management of high level liquid waste (HLLW). Separation of minor acitinides and long-lived fission products from the HLLW by partitioning process has the potential of significantly decreasing the costs of the immobilization and disposal of the radioactive waste by minimizing waste volumes. Several solvent extraction processes have been developed and demonstrated at the Institute of Nuclear and New Energy Technology (INET) for the separation of transuranic elements, 90Sr and 137Cs. In this work, using modified zeolite molecular sieve as a sorbent carrier, four kinds of solidification were prepared by soakage- absorption- calcination methods. It was found that the sample (HZCS-75) calcinated at 750°C was formed pollucite, a zeolite mineral, which will provide an option to immobilize the radioactive cesium and strontium.

Solids Formation Behavior of Simulated High-Level Liquid Waste During Long-Term Storage

2010 ◽  
Author(s):  
Jin Chen ◽  
Xuegang Liu ◽  
Yanchao Zhang ◽  
Qian’ge He ◽  
Jianchen Wang
Keyword(s):  
Solvent Extraction ◽  
Liquid Waste ◽  
Chemical Separation ◽  
Ion Concentration ◽  
Spent Fuel ◽  
High Level Liquid Waste ◽  
Long Term Storage ◽  
High Level ◽  
Term Storage

High-level liquid waste (HLLW) generated from reprocessing process contains actinides, lanthanides, fission products (FP) and a significant amount of nitrate ion. The partitioning and transmutation concept has been introduced for reducing the long-term hazards of HLLW. Several chemical separation processes mainly based on solvent extraction methods have been proposed to treat HLLW. However, solids consisting mainly Mo and Zr are known to form in HLLW during its long-term storage, Solid formations influence the composition of HLLW and the downstream solvent extraction process. To understand the precipitation behavior and stability of HLLW during its long-term storage, simulated HLLW (prepared as raffinate solution from LWR spent fuel reprocessing, 1AW solution) was prepared. Preliminary studies on solid formation behaviors with regard to the precipitation formation during refluxing and aging (representing a long-term storage) were carried out. Precipitation kinetics of major FPs such as Zr, Mo, Ru, rare earth elements, and etc. have been studied; The effect of phosphate ion concentration and temperature on solids formation were also experimentally examined. The formation conditions and the mechanism of solids were discussed.

Recovery of molybdenum by solvent extraction from simulated high level liquid waste

2019 ◽  
Vol 321 (3) ◽  
pp. 1027-1034 ◽  
Author(s):  
Santosh S. Chikkamath ◽  
Dinesh M. Patil ◽  
Anand S. Kabadagi ◽  
Vaidehi S. Tripathi ◽  
Aishwarya S. Kar ◽  
...  
Keyword(s):  
Solvent Extraction ◽  
Liquid Waste ◽  
High Level Liquid Waste ◽  
High Level

Separation of palladium from high level liquid waste of PUREX origin by solvent extraction and precipitation methods using oximes

Desalination ◽  
2008 ◽  
Vol 232 (1-3) ◽  
pp. 26-36 ◽  
Author(s):  
A. Dakshinamoorthy ◽  
P.S. Dhami ◽  
P.W. Naik ◽  
N.L. Dudwadkar ◽  
S.K. Munshi ◽  
...  
Keyword(s):  
Solvent Extraction ◽  
Liquid Waste ◽  
High Level Liquid Waste ◽  
High Level

scholarly journals Vitrification of HLW Produced by Uranium/Molybdenum Fuel Reprocessing in COGEMA’s Cold Crucible Melter

2003 ◽  
Author(s):  
R. Do Quang ◽  
V. Petitjean ◽  
F. Hollebecque ◽  
O. Pinet ◽  
T. Flament ◽  
...  
Keyword(s):  
Atomic Energy Commission ◽  
Liquid Waste ◽  
Glass Layer ◽  
Cold Crucible ◽  
High Level Liquid Waste ◽  
Process Waste ◽  
Glass Formulation ◽  
High Level ◽  
Fuel Reprocessing ◽  
High Frequency Induction

The performance of the vitrification process currently used in the La Hague commercial reprocessing plants has been continuously improved during more than ten years of operation. In parallel COGEMA (industrial Operator), the French Atomic Energy Commission (CEA) and SGN (respectively COGEMA’s R&D provider and Engineering) have developed the cold crucible melter vitrification technology to obtain greater operating flexibility, increased plant availability and further reduction of secondary waste generated during operations. The cold crucible is a compact water-cooled melter in which the radioactive waste and the glass additives are melted by direct high frequency induction. The cooling of the melter produces a soldified glass layer that protects the melter’s inner wall from corrosion. Because the heat is transferred directly to the melt, high operating temperatures can be achieved with no impact on the melter itself. COGEMA plans to implement the cold crucible technology to vitrify high level liquid waste from reprocessed spent U-Mo-Sn-Al fuel (used in gas cooled reactor). The cold crucible was selected for the vitrification of this particularly hard-to-process waste stream because it could not be reasonably processed in the standard hot induction melters currently used at the La Hague vitrification facilities: the waste has a high molybdenum content which makes it very corrosive and also requires a special high temperature glass formulation to obtain sufficiently high waste loading factors (12% in molybednum). A special glass formulation has been developed by the CEA and has been qualified through lab and pilot testing to meet standard waste acceptance criteria for final disposal of the U-Mo waste. The process and the associated technologies have been also being qualified on a full-scale prototype at the CEA pilot facility in Marcoule. Engineering study has been integrated in parallel in order to take into account that the Cold Crucible should be installed remotely in one of the R7 vitrification cell. This paper will present the results obtained in the framework of these qualification programs.

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