The isolation of 99Mo from fission material for use in the 99Mo/99mTc generator for medical use

Radiochimica Acta

Volumn 92, Issue 4-6, 2004, Pages 251-257

  Van Der Walt, T N ^a   Coetzee, P P ^b  

^a ITHEMBA LABS   (South Africa)

^b UNIVERSITY OF JOHANNESBURG   (South Africa)

Author keywords

235U; 99Mo production; Fission products; Ion exchange chromatography; Isolation and purification

Indexed keywords

ACTIVATED CARBON; ALKALI; ALLOY; ALUMINUM; AMMONIA; BARIUM; IODINE 131; KRYPTON; LITHIUM SULFATE; MOLYBDENUM 99; NITRIC ACID; OXALIC ACID; RADIOISOTOPE; RESIN; SODIUM HYDROXIDE; STRONTIUM; TECHNETIUM 99M; TELLURIUM; URANIUM; XENON;

ACIDIFICATION; ANION EXCHANGE CHROMATOGRAPHY; DISSOLUTION; ELUTION; EVAPORATION; IRRADIATION; NUCLEAR ENERGY; NUCLEAR INDUSTRY; NUCLEAR MEDICINE; NUCLEAR REACTOR; PURIFICATION; RADIOACTIVITY; RADIOCHEMICAL PURITY; RADIOCHEMISTRY; RADIOISOTOPE DECAY; REVIEW; SOUTH AFRICA;

EID: 3142748995     PISSN: 00338230     EISSN: None     Source Type: Journal    
DOI: 10.1524/ract.92.4.251.35589     Document Type: Review

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