Chromatography Column System With Controlled Flow and Temperature for Engineering Scale Application

2009 ◽  
Author(s):  
Sou Watanabe ◽  
Ichiro Goto ◽  
Yuichi Sano ◽  
Yoshikazu Koma
Keyword(s):  
Flow Velocity ◽  
Technology Development ◽  
Liquid Waste ◽  
Test System ◽  
Middle Level ◽  
High Level Liquid Waste ◽  
Energy Agency ◽  
Decay Heat ◽  
Column System ◽  
High Level

Japan Atomic Energy Agency (JAEA) is conducting R&D of the engineering scale extraction chromatography system, which uses silica-based adsorbents impregnated with an extractant for the minor actinides (Am and Cm) recovery from the high level liquid waste generated in the spent FBR fuel reprocessing, as a part of the Fast Reactor Cycle Technology Development (FaCT) project. A bench scale testing system was made and provided for the first step of development. The column of the test system (ID 480 or 200 mmΦ with 650 mm height) was equipped with ports for 6 external sensors at its top, middle and bottom levels for measuring the flow velocity or temperature, and for additional 6 heaters for simulating the decay heat of Am and Cm at the middle level of the column. The flow velocity distribution was almost constant except for the very near at the column wall, and it was almost uniform when the liquid flew from top to bottom direction with 4 cm/min of the velocity. The heaters scarcely influenced on the temperature profile inside the column when the power applied to the heater simulated the decay heat of Am, Cm and FPs. The decay heat generated in the column was transported to the effluents and the temperature inside column was kept almost constant.

Chromatography Column System With Controlled Flow and Temperature for Engineering Scale Application

2010 ◽  
Vol 132 (10) ◽  
Author(s):  
Sou Watanabe ◽  
Ichiro Goto ◽  
Yuichi Sano ◽  
Yoshikazu Koma
Keyword(s):  
Flow Velocity ◽  
Technology Development ◽  
Liquid Waste ◽  
Fission Products ◽  
Test System ◽  
Development Project ◽  
Middle Level ◽  
High Level Liquid Waste ◽  
Energy Agency ◽  
Decay Heat

The Japan Atomic Energy Agency is conducting research and development study on the engineering scale extraction chromatography system, which uses silica-based adsorbents impregnated with an extractant for the minor actinides (Am and Cm) recovery from the high level liquid waste generated in the spent fast breeder reactor (FBR) fuel reprocessing, as a part of the fast reactor cycle technology development project. A bench scale testing system was made and provided for the first step of development. The column of the test system (inside diameter of 480 mm or 200 mm with height of 650 mm) was equipped with ports for six external sensors at its top, middle, and bottom levels for measuring the flow velocity or temperature, and for additional six heaters for simulating the decay heat of Am and Cm at the middle level of the column. The flow velocity distribution was almost constant except for the part that is very near the column wall, and it was almost uniform when the liquid flew from top to bottom direction with 4 cm/min of the velocity. The heaters scarcely influenced the temperature profile inside the column when the power applied to the heater simulated the decay heat of Am, Cm, and fission products (FPs). The decay heat generated in the column was transported to the effluents, and the temperature inside the column was kept almost constant.

scholarly journals Micro-PIXE analysis on adsorbent of extraction chromatography for MA(III) recovery

2016 ◽  
Vol 26 (03n04) ◽  
pp. 73-83
Author(s):  
Y. Takahatake ◽  
S. Watanabe ◽  
H. Kofuji ◽  
M. Takeuchi ◽  
K. Nomura ◽  
...  
Keyword(s):  
Extraction Chromatography ◽  
Packed Column ◽  
Liquid Waste ◽  
Flow Sheet ◽  
Simple Experiment ◽  
High Level Liquid Waste ◽  
Energy Agency ◽  
Pixe Analysis ◽  
Conducting Research ◽  
High Level

Japan Atomic Energy Agency (JAEA) has been conducting research and development of MA(III) recovery from high level liquid waste (HLLW) by extraction chromatography technology for reduction in amount and environmental impact of radioactive waste. The behavior of adsorbed cations inside the adsorbent packed in a column is necessary to be evaluated for improvement of the adsorbent or flow-sheet to achieve targeted MA(III) recovery performance. In this paper, micro-PIXE analysis was carried out on the particles sampled from various positions of the column to reveal the behavior of cations inside the packed column with CMPO/SiO2-P adsorbent using RE(III) as simulated elements of MA(III). Simple experiment and data analysis were shown to be effective to reveal inside of the column, and formation and transportation of the adsorption bands were observed for some cations which are extractable by the CMPO extractant. Some part of Zr(IV) and Mo(VI) were found to remain inside the column without distinct transportation even after the elution operation. Those results will contribute to design more practical MA(III) recovery flow-sheet.

scholarly journals Development of a test system for high level liquid waste partitioning

2015 ◽  
Vol 30 (4) ◽  
pp. 311-317
Author(s):  
Wu Duan ◽  
Jing Chen ◽  
Jian Wang ◽  
Shu Wang ◽  
Xing Wang
Keyword(s):  
Liquid Waste ◽  
Video Camera ◽  
Extraction Process ◽  
Test System ◽  
High Level Liquid Waste ◽  
Sampling System ◽  
System A ◽  
Treatment And Disposal ◽  
High Level ◽  
Hot Test

The partitioning and transmutation strategy has increasingly attracted interest for the safe treatment and disposal of high level liquid waste, in which the partitioning of high level liquid waste is one of the critical technical issues. An improved total partitioning process, including a tri-alkylphosphine oxide process for the removal of actinides, a crown ether strontium extraction process for the removal of strontium, and a calixcrown ether cesium extraction process for the removal of cesium, has been developed to treat Chinese high level liquid waste. A test system containing 72-stage 10-mm-diam annular centrifugal contactors, a remote sampling system, a rotor speed acquisition-monitoring system, a feeding system, and a video camera-surveillance system was successfully developed to carry out the hot test for verifying the improved total partitioning process. The test system has been successfully used in a 160 hour hot test using genuine high level liquid waste. During the hot test, the test system was stable, which demonstrated it was reliable for the hot test of the high level liquid waste partitioning.

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.

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