Methods of high-sensitive analysis of actinides in liquid radioactive waste

Diakov, A.A.; Perekhozheva, T.N.; Zlokazova, E.I.

doi:10.1016/s1350-4487(01)00207-4

Cited by 6 publications

(3 citation statements)

References 3 publications

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“…The recovery was determined gravimetrically by weighing the strontium oxalate precipitate. The precipitate was dis-solved in 1M nitric acid, mixed with a scintillation cocktail Ultima Gold XR and beta activity counted on a liquid scintillation counter [2][3][4][5][13][14][15]. Table 1 shows the concentrations of selected radionuclides in six artificially prepared samples and Table 2 shows yields for various radionuclides after separation according to the described procedure.…”

Section: Analytical Proceduresmentioning

confidence: 99%

“…In the present work, we focused on determination of activation and fission products, which are alpha and beta emitters, in ion exchange resins. Separation of these nuclides is possible using ion exchange and extraction chromatography after destruction of the matrix using Fenton's reagent [2][3][4]. We *Author for correspondence (E-mail: polona.tavcar@ijs.si).…”

Section: Introductionmentioning

confidence: 99%

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Determination of actinides and ⁹⁰Sr in spent ion exchange resins

Tavčar¹,

Benedik²

2005

Radiochimica Acta

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In the present work, we focused on determination of some important activation products like 238 Pu, 239 Pu/ 240 Pu, 241 Am, and 237 Np, and 90 Sr as a fission product in spent ion exchange resins. The activation products of interest are alpha emitters, while 90 Sr is a beta emitter. Radioactive solutions of 241 Am, 238 Pu, 237 Np, and 90 Sr and pure ion exchange resins were used to prepare artificial samples which were subsequently subjected to an analytical procedure. This consisted of wet destruction of the resins with Fenton's reagent followed by separations using ion exchange. The activities found showed good agreement with calculated values and yields were also very good (above 50%). We also analysed five samples of spent ion exchange resin from the TRIGA Mark II research reactor. Activities of selected radionuclides were below expectations in all samples except in sample 1, which had higher activities of 90 Sr, 137 Cs, 60 Co, 152 Eu, and 154 Eu. Total beta/gamma activity did not exceed the max. permitted level for low level waste.

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Section: Analytical Proceduresmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Determination of actinides and ⁹⁰Sr in spent ion exchange resins

Tavčar¹,

Benedik²

2005

Radiochimica Acta

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“…The analytical determination of actinide concentration levels in water by alpha spectrometry usually requires very long operations that involve the following sequence: (i) separation, (ii) purification, (iii) preparation of solid sources and (iv) counting and spectrometric detection (Holm and Fukai, 1977, de Regge and Boden, 1984, Bickel et al, 2000, Diakov et al, 2001, Ayranov et al, 2005, Salar Amoli and Barker, 2007. Under such operating conditions, the time required from sampling to the analytical result delivery extends over several days.…”

Section: Introductionmentioning

confidence: 99%