Recent R&D studies related to coprocessing of spent nuclear fuel using N,N-Dihexyloctanamide

Separation Science and Technology

Volumn 44, Issue 15, 2009, Pages 3650-3663

  Pathak, P N ^a   Prabhu, D R ^a   Kanekar, A S ^a   Manchanda, V K ^a  

^a BHABHA ATOMIC RESEARCH CENTRE   (India)

Author keywords

Coprocessing; Dihexyloctanamide; Plutonium; PUREX; TBP; Uranium

Indexed keywords

FUELS; HEAVY WATER; HEAVY WATER REACTORS; NITRIC ACID; NUCLEAR ENERGY; PLUTONIUM; RADIOACTIVE WASTES; SOLVENT EXTRACTION; SOLVENTS; SPECTROSCOPIC ANALYSIS; STOICHIOMETRY; STRIPPING (DYES); URANIUM;

ADVANCED FUEL CYCLE; BATCH EXTRACTION; COPROCESSING; DIHEXYLOCTANAMIDE; HIGH-BURN UP; N-DODECANE; PRESSURIZED HEAVY WATER REACTORS; PRODUCT STREAMS; PUREX PROCESS; SPENT NUCLEAR FUELS; STRIPPING BEHAVIOR;

NUCLEAR FUEL REPROCESSING;

CHEMICAL COMPOSITION; CHEMICAL REACTION; EXTRACTION METHOD; HEAVY METAL; NITRIC ACID; NUCLEATION;

EID: 78149416839     PISSN: 01496395     EISSN: 15205754     Source Type: Journal    
DOI: 10.1080/01496390903183147     Document Type: Article

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