Radiochemical determination of plutonium in the JRR-1 irradiated uranium (in German)
Small amounts of plutonium were determined radiochemically after separating plutonium from uranium and fission products by the ion exchange methods. A 7 N nitric acid solution of irradiated uranium was passed through the anion exchange resin, Dowex 1. Uranium and fission prodcomplex of plutonium (IV) was adsorped on the resin bed. Plutonium was eluted with 5% hydroxylamine hydrochloride solution. The solution containing both plutonium and hydroxylamine was passed through the cation exchange resin, Dowex 50, in order to remove the hydroxylamine. After washing the resin with 0.3 N nitric acid, plutonium was cluted with 7 N nitric acid. The synthetic samples containing 2 approximately - 200 mg of uranium and 0 approximately - 4500 dpm of Pu239 were treated by the above method in order to determine the interferrence of uranium content on the recovery of plutonium. The recovery of plutonium, approximately 92%, is not affected practically with less than 200 mg of uranium. Amounts of plutonium in uranium samples irradiated 66.5 hr in experimental hole No. 2N of JRR-1 and 194 hr in experimental hole No. 13 were 79 dpm Pu/mg U238, respectively. 4890 dpm Pu/mg U238 was found in uranium irradiated for 50000 kwh in JRR-1.
- Research Organization:
- Japan Atomic Energy Agency (JAEA), Tokai (Japan)
- Sponsoring Organization:
- USDOE
- NSA Number:
- NSA-15-029144
- OSTI ID:
- 4843090
- Journal Information:
- Nippon Genshiryoku Gakkai-Shi, Vol. 3, Issue 7; Other Information: Orig. Receipt Date: 31-DEC-61; ISSN 0004-7120
- Country of Publication:
- Country unknown/Code not available
- Language:
- German
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Related Subjects
ADSORPTION
AMINES
FISSION PRODUCTS
ION EXCHANGE
IRRADIATION
NITRIC ACID
PLUTONIUM
PLUTONIUM 239
PLUTONIUM COMPLEXES
PLUTONIUM NITRATES
QUANTITATIVE ANALYSIS
RADIOCHEMISTRY
RECOVERY
RESEARCH REACTORS
RESINS
SEPARATION PROCESSES
SOLUTIONS
URANIUM
URANIUM 238
USES