scholarly journals Assessment of fission product content of high-level liquid waste supernate on E-Area vault package criteria

1994 ◽  
Author(s):  
D.F. Brown
Keyword(s):  
Fission Product ◽  
Liquid Waste ◽  
High Level Liquid Waste ◽  
High Level

Radiocesium removal from high level liquid waste and immobilisation in sodium silicotitanate for geological disposal

2001 ◽  
Vol 89 (3) ◽  
Author(s):  
T. Tomasberger ◽  
A.C. Veltkamp ◽  
A. S. Booij ◽  
U. W. Scherer
Keyword(s):  
Ion Exchange ◽  
Fission Product ◽  
Liquid Waste ◽  
High Level Liquid Waste ◽  
Geological Disposal ◽  
Inorganic Ion ◽  
Exchange Material ◽  
Leaching Behaviour ◽  
Concentration Factors ◽  
High Level

The isolation of the fission product cesium from high-level alkaline liquid waste is studied with inorganic ion-exchange materials. High separation and concentration factors can be obtained using sodium silicotitanate (CST). The leaching behaviour of cesium from CST was studied in clay porewater and Quinary brine at 90 °C. It is shown that cesium leaching in Quinary brine can be drastically reduced by thermal treatment of cesium loaded CST above 1000 °C. To this end, neutralisation of the ion exchange material before heating is required in order to reduce cesium volatility. It is concluded that CST is a good candidate material for geological disposal of the fission product cesium.

scholarly journals Development of MA separation process with TEHDGA/SiO2-P for an advanced reprocessing

2021 ◽  
Vol 330 (1) ◽  
pp. 237-244
Author(s):  
Yusuke Horiuchi ◽  
Sou Watanabe ◽  
Yuichi Sano ◽  
Masayuki Takeuchi ◽  
Fukuka Kida ◽  
...  
Keyword(s):  
Fission Product ◽  
Distribution Ratio ◽  
Extraction Chromatography ◽  
Packed Column ◽  
Liquid Waste ◽  
Separation Process ◽  
Minor Actinide ◽  
High Level Liquid Waste ◽  
Column Separation ◽  
High Level

AbstractApplicability of tetra2-ehylhexyl diglycolamide (TEHDGA) impregnated adsorbent for minor actinide (MA) recovery from high level liquid waste (HLLW) in extraction chromatography technology was investigated through batch-wise adsorption and column separation experiments. Distribution ratio of representative fission product elements were obtained by the batch-wise experiments, and TEHDGA adsorbent was shown to be preferable to TODGA adsorbent for decontamination of several species. All Ln(III) supplied into the TEHDGA adsorbent packed column was properly eluted from the column, and the applicability of the adsorbent was successfully showed by this study.

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.

Agents and Processes Design for TRU Elements Back Extraction in TRPO Process

2009 ◽  
Author(s):  
Meng Wei ◽  
Xuegang Liu ◽  
Jing Chen
Keyword(s):  
Organic Phase ◽  
Liquid Waste ◽  
Back Extraction ◽  
High Level Liquid Waste ◽  
Trpo Process ◽  
Extraction Processes ◽  
Treatment And Disposal ◽  
High Level ◽  
Disposal Cost

To reduce the long-term risk of the high-level liquid waste (HLLW) and the waste disposal cost, transuranium (TRU) elements should be removed from HLLW. A so-called TRPO process has been developed by Chinese scientists to partition HLLW. In this process, the extractant, trialkyl phosphine oxide (TRPO), is able to extract TRU elements into organic phase completely, which makes the treatment and disposal of raffinate HLLW much easier. However, the treatment of extracted TRU elements in organic phase, in return, becomes new troublesome issue. Generally, there are three promising ways to treat the extracted TRU elements: (1)transmutation; (2)conditioning; (3)recycling U+Pu in Purex-TRPO Integrated Process. In any of the three ways, the back extraction agents and processes play significant roles. In this paper, the investigations on back extraction agents for TRU elements, such as TTHA, DTPA, AHA, HEDPA, DOGA, and carbonates are introduced. The corresponding back extraction processes and experimental results are reviewed.

Extraction chromatography–electrodeposition (EC–ED) process to recover palladium from high-level liquid waste

2017 ◽  
Vol 28 (12) ◽  
Author(s):  
Qing Zou ◽  
Shuai Gu ◽  
Rui-Qin Liu ◽  
Shun-Yan Ning ◽  
Yan-Liang Chen ◽  
...  
Keyword(s):  
Extraction Chromatography ◽  
Liquid Waste ◽  
High Level Liquid Waste ◽  
High Level
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