121 MARKETING COMPANYBusiness Directories,Company Directories

Company Name: Corporate Name:	121 MARKETING COMPANY
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Company Address:	34 Blue Jay Dr,MIDWAY CITY,CA,USA
ZIP Code: Postal Code:	92655
Telephone Number:	7142419241 (+1-714-241-9241)
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USA SIC Code(Standard Industrial Classification Code):	5999
USA SIC Description:	Marketing NEC
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The Plutonium Uranium Extraction Process (PUREX) separates plutonium . . .
At SRS, nuclear material streams are processed through a first (solvent extraction) cycle to rapidly separate fission products from Pu and U, followed by separation of Pu (and or Np) and U
PUREX - Wikipedia
PUREX is the de facto standard aqueous nuclear reprocessing method for the recovery of uranium and plutonium from used nuclear fuel (spent nuclear fuel, or irradiated nuclear fuel)
Standard and advanced separation: PUREX processes for . . . - ScienceDirect
The U-Pu partitioning is accomplished by using conditions conducive to the reduction of Pu (IV) to the virtually inextractable Pu (III) oxidation state, effectively back-extracting plutonium from the loaded organic
Demonstration of the UREX Solvent Extraction Process with Dresden . . .
The Plutonium and Uranium Extraction (PUREX) process is a mature solvent extraction process for irradiated nuclear fuel that was designed to recover plutonium (Pu) and U
PUREX – RECYCLING METHOD - Foreningen Atomkraft Ja Tak
When the solution is mixed with TBP, stable complex compounds are formed whereby uranium (U) and plutonium (Pu) are absorbed and separated from the fission products (Fp)
(PDF) Recent Developments in the Purex Process for Nuclear Fuel . . .
The separation of plutonium (Pu) from spent nuclear fuel was achieved by effectively adjusting the oxidation state of Pu from +IV to +III in the plutonium uranium reduction extraction (PUREX)
Standard and advanced separation: PUREX processes for nuclear fuel . . .
The U-Pu partitioning is accomplished by using condi-tions conducive to the reduction of Pu(IV) to the virtually inextractable Pu(III) oxidation state, effectively back-extracting plutonium from the loaded organic
Uranium (U) and plutonium (Pu) separation technology in Purex process
This process uses the reducing agent 1BX and the supplementary extractant 1BS in the 1B tank to reduce Pu (IV) in the 1BF feed liquid to Pu (Ⅲ), so that the plutonium enters the water phase and
Used Nuclear Fuel Reprocessing - ICLN
To separate plutonium from uranium, a reductant is added to the aqueous stream, reducing Pu(IV) to Pu(III), which is not soluble in the organic solvent and partitions to the aqueous phase while U(VI) remains in the solvent
Purex Process - an overview | ScienceDirect Topics
The good extractability of nitrate complexes of UO 2 2 + and Pu 4+ coupled with the inextractability of fission products by TBP forms the main principle of the Purex process As Pu3+ is weakly extracted, further separation of uranium from plutonium is achieved by reducing Pu 4+ to Pu 3+, in which state it is stripped from the organic phase