scholarly journals Permissible radionuclide loading for organic ion exchange resins from nuclear power plants

1983 ◽  
Author(s):  
D.R. MacKenzie ◽  
M. Lin ◽  
R.E. Barletta
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

2018 ◽  
Vol 29 (4) ◽  
pp. 188-194
Author(s):  
Takeshi IZUMI ◽  
Makoto KOMATSU ◽  
Tatsuya DEGUCHI

2019 ◽  
Vol 58 (5) ◽  
pp. 54-61
Author(s):  
Marina M. Kozlova ◽  
◽  
Artem E. Bobylev ◽  
Larisa N. Maskaeva ◽  
Vyacheslav F. Markov ◽  
...  

During the operation of nuclear power plants, spent ion-exchange resins are formed, which are heterogeneous radioactive low-level waste in the form of particles from a cross-linked organic polymer. Such resins may not always be regenerated. Therefore, the disposal of spent ion exchange resins is currently one of the primary problems at nuclear power plants. Conventional technologies for the processing of waste resins are relatively expensive. In addition, there are difficulties with transportation and storage of waste, and the disposal of spent ion exchange resins is a complex process. In the present study, an attempt has been made to solve the problem of spent ion-exchange resins utilization on example of the sulfonic acid cation exchanger’s KU-2×8 oxidative degradation with the Fenton reaction. The decomposition of the cation exchanger was carried out with 20% hydrogen peroxide in the temperature range 323-353 K in the presence of a catalyst – low concentration copper(II) sulfate (0.001-0.009 mmol/l). The influence of process temperature and catalyst concentration on the reaction rate was estimated. When determining the rate of the cation exchanger KU-2×8 heterogeneous oxidation reaction with hydrogen peroxide in the presence of a catalytic additive, the spherical shape of the sorbent granules, the surface area of which changed during reaction, was taken into account. It was shown that with a reaction temperature increasing from 323 to 353 K, the rate constant of cation exchanger's oxidative decomposition have increased by a factor of 20-37. The activation energy values of the sulfonic acid cation exchanger's KU-2×8 decomposition with hydrogen peroxide in the presence of copper(II) sulfate are 89.7-115.2 kJ/mol, which indicates that the process is in the kinetic mode. It was established with electron-microscopic studies that the beads of the cation exchanger KU-2×8, when decomposed in H2O2 solution in the presence of a catalyst can stick together, change their shape and volume, and their surface becomes covered with cracks. The studies performed showed almost complete catalytic decomposition of cation exchanger KU-2×8 in a hydrogen peroxide solution at 323-353 K after 420-220 minutes, which allows accelerating the oxidation at relatively low temperatures.


2012 ◽  
Vol 1475 ◽  
Author(s):  
Stasys Motiejunas ◽  
Algirdas Vaidotas ◽  
Jonas Mazeika ◽  
Zana Skuratovic ◽  
Violeta Vaitkeviciene

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.


1992 ◽  
Vol 294 ◽  
Author(s):  
Ari Ipatti

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.


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