Recovery of Neptunium from Highly Radioactive Waste Solutions of Purex Origin Using Tributyl Phosphate

Separation Science and Technology

Volumn 31, Issue 15, 1996, Pages 2045-2063

  Mathur, J N ^a   Murali, M S ^a   Balarama Krishna, M V ^a   Iyer, R H ^a   Chitnis, R R ^a   Wattal, P K ^a   Theyyunni, T K ^a   Ramanujam, A ^a   Dhami, P S ^a   Gopalakrishnan, V ^a  

^a BHABHA ATOMIC RESEARCH CENTRE   (India)

Author keywords

[No Author keywords available]

Indexed keywords

COMPUTER SIMULATION; FAST REACTORS; NEPTUNIUM; OXIDATION; PHOSPHATES; PLUTONIUM; PRESSURIZED WATER REACTORS; RADIOACTIVE WASTES; SOLUTIONS; STRIPPING (REMOVAL); URANIUM;

HIGH LEVEL WASTE SOLUTION; RESEARCH REACTOR FUELS; SELECTIVE STRIPPING; TRIBUTYL PHOSPHATE;

EXTRACTION;

EID: 0030242852     PISSN: 01496395     EISSN: None     Source Type: Journal    
DOI: 10.1080/01496399608001030     Document Type: Article

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