THE DETERMINATION OF PROTACTINIUM-233
Protactinium-233, together with a known amount of protactinium-231, is initially separated on anion exchange resin Deacidite FF. Further purification is achieved by extraction of the protactinium into methyi isobutyl ketone (MIBK) from 6M hydrochloric acid solution, followed by back extraction as the fluoride complex. The extraction cycle is repeated, and the protactinium-233 is then determined by gamma scintillation spectrometry, the chemical yield being assessed by alpha counting the protactinium-231. The method is applicable to solutions of irradiated thorium, thorium-uranium, and thorium-beryllium alloys in sulfuric, nitric, or hydrochloric acid. The procedure is especially suitable when a determination of radioactive zirconium is also required. (auth)
- Research Organization:
- United Kingdom Atomic Energy Authority. Research Group. Atomic Energy Research Establishment, Harwell, Berks, England
- NSA Number:
- NSA-17-001375
- OSTI ID:
- 4772502
- Report Number(s):
- AERE-AM-90
- Country of Publication:
- United Kingdom
- Language:
- English
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Related Subjects
BERYLLIUM ALLOYS
BUTYL RADICALS
CHEMISTRY
EFFICIENCY
GAMMA SPECTROMETERS
HYDROCHLORIC ACID
IMPURITIES
ION EXCHANGE MATERIALS
ISOTOPE SEPARATION
KETONES
METHYL RADICALS
NITRIC ACID
PROTACTINIUM 231
PROTACTINIUM 233
PROTACTINIUM COMPLEXES
PROTACTINIUM FLUORIDES
QUANTITATIVE ANALYSIS
SCINTILLATION COUNTERS
SOLUTIONS
SOLVENT EXTRACTION
SULFURIC ACID
THORIUM
THORIUM ALLOYS
URANIUM ALLOYS
USES
ZIRCONIUM ISOTOPES