scholarly journals 14C content in candu spent ion exchange resins and its release under alkaline conditions

Radiocarbon ◽  
2018 ◽  
Vol 60 (6) ◽  
pp. 1797-1808
Author(s):  
C Bucur ◽  
I Florea ◽  
P E Reiller ◽  
D Dumitrescu
Keyword(s):  
Ion Exchange ◽  
Gas Phase ◽  
Nuclear Power ◽  
Ion Exchange Resins ◽  
Dissolved Species ◽  
Alkaline Conditions ◽  
Naoh Solution ◽  
Ca Ions ◽  
Soluble Species ◽  
Exchange Resins

ABSTRACTThe total 14C content and its speciation (inorganic/organic) were measured in spent ion exchange resins (SIERs) received from Cernavoda Nuclear Power Plant (NPP). Also, 14C release from SIERs was investigated by desorption tests carried out in alkaline solution relevant for cementitious environment disposal. The method used for total 14C measurement consists of combustion in oxygen-rich atmosphere, while for speciation measurements, both in SIERs and in desorption solutions, an analytical method based on acid stripping and wet oxidation was applied. Around 97% from the total 14C inventory measured on the Cernavoda SIERs (33.7 kBq/g) was found to be in inorganic form and only 7% as organic 14C. Under alkaline conditions, 14C could be released both as gaseous and as soluble species: from the total 14C present in the SIERs samples around 7% was released as inorganic 14C in the gas phase and 79% as dissolved species (mainly as inorganic 14C). These percentages were obtained for unconditioned SIERs in NaOH solution. The SIERs will be immobilized in a suitable matrix for disposal, and the presence of Ca ions dissolved in cement pore water favor precipitation of 14C and consequently the amount of 14C released from disposal area should be lower.

Heat-treatment and storage technology for spent ion-exchange resins for new-generation nuclear power plants

Atomic Energy ◽  
2012 ◽  
Vol 111 (4) ◽  
pp. 276-281
Author(s):  
D. N. Babkin ◽  
N. A. Prokhorov ◽  
V. T. Sorokin ◽  
A. V. Demin ◽  
V. V. Iroshnikov
Keyword(s):  
Heat Treatment ◽  
Ion Exchange ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Ion Exchange Resins ◽  
Storage Technology ◽  
Exchange Resins ◽  
New Generation ◽  
And Storage

Radiocarbon measurements in cemented ion-exchange resins

2012 ◽  
Vol 1475 ◽  
Author(s):  
Stasys Motiejunas ◽  
Algirdas Vaidotas ◽  
Jonas Mazeika ◽  
Zana Skuratovic ◽  
Violeta Vaitkeviciene
Keyword(s):  
Ion Exchange ◽  
Nuclear Power ◽  
Inorganic Compounds ◽  
Liquid Radioactive Waste ◽  
Ion Exchange Resins ◽  
Near Surface ◽  
Solidified Waste ◽  
Order Of Magnitude ◽  
Exchange Resins

ABSTRACTA large amount of liquid radioactive waste has been generated at the Ignalina Nuclear Power Plant (NPP), Lithuania, during its operation. The contaminated liquids are treated with ion exchange-resins, which will generate significant waste stream for cementation. The cemented waste will be disposed of in a near-surface repository. The preliminary safety assessment uncovered that 14C is the most significant radionuclide affecting long-term safety of the closed repository. The method of combined acid striping and wet oxidation with subsequent catalytic combustion has been applied for 14C measurements in cemented ion-exchange resins. It allows separating organic and inorganic compounds from the same sample. At first, the inorganic fraction was extracted by adding acid to the sample followed by absorption of CO2 in a pair of alkali gas washed traps. The remaining carbon was extracted by application of a strong oxidizer. The preliminary results show that activity concentration of 14C in the solidified waste has an order of magnitude of tens and hundreds Bq per gram.

Solidification of Microbiologically Treated Ion-Exchange Resins Using Portland Cement-Based Systems

1992 ◽  
Vol 294 ◽  
Author(s):  
Ari Ipatti
Keyword(s):  
Ion Exchange ◽  
Portland Cement ◽  
Nuclear Power ◽  
Setting Time ◽  
Waste Product ◽  
Ion Exchange Resins ◽  
Portland Cements ◽  
Solidified Waste ◽  
Exchange Resins ◽  
Microbiological Treatment

ABSTRACTPretreated inactive ion exchange resins from the Loviisa nuclear power plant (NPP) were first reduced to one tenth of the original volume through microbiological treatment. During the process, the granular ion exchange resins were decomposed to result in dregs, which were solidified with two types of Portland cements. The objective of the present experiments was to investigate whether commercial cements are suitable solidification agents for this kind of waste.A total of ten mixtures were pretested for their rheological and setting properties. On the basis of the pretest results, four additional mixtures were chosen and tested for the spread value, density, air content, setting time and bleeding of the fresh waste product and for the dimensional stability and compressive strength of the hardened waste product. The cementing systems incorporated in the tests were ASTM type V Portland cement and ASTM type P Portland Composite cements. The dregs used in the tests were taken from a Pilot-Plant experiment at the Loviisa NPP and contained 2 wt-% solids.The test results were promising in showing that microbiological dregs can very easily be solidified with Portland cements to form a high-quality waste product. Thus, the microbiological treatment of spent ion exchange resins will drastically decrease the amount of solidified waste to be disposed of at the Loviisa NPP.

scholarly journals Prolongation Technology of Life Time of Ion Exchange Resins in Nuclear Power Plants

2018 ◽  
Vol 29 (4) ◽  
pp. 188-194
Author(s):  
Takeshi IZUMI ◽  
Makoto KOMATSU ◽  
Tatsuya DEGUCHI
Keyword(s):  
Ion Exchange ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Life Time ◽  
Ion Exchange Resins ◽  
Exchange Resins
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