Simplified Chinese TRPO Process to Extract and Recover Transuranium Elements from High‐Level Liquid Waste

2004 ◽  
Vol 22 (2) ◽  
pp. 163-173 ◽  
Author(s):  
Xuegang Liu ◽  
Junfu Liang ◽  
Jingming Xu
Keyword(s):  
Liquid Waste ◽  
High Level Liquid Waste ◽  
Transuranium Elements ◽  
Simplified Chinese ◽  
Trpo Process ◽  
High Level

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.

Hot test of partitioning strontium from high-level liquid waste (HLLW) by dicyclohexano-18crown-6 (DCH18C6)

2001 ◽  
Vol 89 (3) ◽  
Author(s):  
W. Jianchen ◽  
S. Chongli
Keyword(s):  
Crown Ether ◽  
Liquid Waste ◽  
Current Mode ◽  
Feed Solution ◽  
High Level Liquid Waste ◽  
Trpo Process ◽  
Centrifugal Contactor ◽  
High Level ◽  
Counter Current ◽  
Hot Test

The crown ether strontium extraction(CESE) process for partitioning strontium from HLLW was studied. A hot test was carried out in a counter current mode with genuine HLLW by using a miniature centrifugal contactor set. 0.1 mol/L DCH18C6 in 1-octanol was used as extractant. The feed solution was the HLLW raffinate of TRPO process after removing TRU elements. Acidity of the feed was 1.45 mol/L HNO

scholarly journals Recovery of Transuranium Elements from Real High-Level Liquid Waste by Pyropartitioning Process

2011 ◽  
Vol 48 (2) ◽  
pp. 303-314 ◽  
Author(s):  
Koichi UOZUMI ◽  
Masatoshi IIZUKA ◽  
Masaki KURATA ◽  
Tadashi INOUE ◽  
Tadafumi KOYAMA ◽  
...  
Keyword(s):  
Liquid Waste ◽  
High Level Liquid Waste ◽  
Transuranium Elements ◽  
High Level

Denitration of simulated high-level liquid waste by formic acid for the connection of PUREX process with TRPO process

2017 ◽  
Vol 314 (1) ◽  
pp. 221-229 ◽  
Author(s):  
Wenbing Li ◽  
Wuhua Duan ◽  
Taoxiang Sun ◽  
Changjian Liu ◽  
Jianchen Wang ◽  
...  
Keyword(s):  
Formic Acid ◽  
Liquid Waste ◽  
Purex Process ◽  
High Level Liquid Waste ◽  
Trpo Process ◽  
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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