13-18 May 2018
Casino Conference Centre
Europe/Prague timezone

Ultrafiltration study of Cs-137, Co-60, Sr-85 speciation in model solution of spent nuclear fuel pool

14 May 2018, 17:15
1h 30m
Gallery (Casino Conference Centre)

Gallery

Casino Conference Centre

Poster Separation Methods, Speciation

Speaker

Mr Aleksandr Zarubo (Joint Institute for Power and Nuclear Research – Sosny of the National Academy of Sciences of Belarus)

Description

Spent fuel is generated during power reactor operation in the form of spent fuel assemblies. Spent fuel assemblies are placed to at-reactor spent fuel pool for cooling, reducing of fission products radioactivity and radiation protection of staff. During storage of spent fuel assemblies radionuclides, both fission and activation origin, get to solution of spent fuel pool. Radionuclides, interacting with products of corrosion, can form radioactive soluble species and suspensions that fall to bottom of spent fuel pool or to hard-to-reach places. Radioactive sediments increase background radiation and staff doses, as well as problems at spent fuel pool decontamination during operation or decommissioning.
Existing treatment installations for spent fuel pool solutions manage with treatment process partially. More effective treatment methods and technologies for these solutions are required. Radionuclide speciation in solution of spent fuel pool is an important information that is necessary for solving this problem. The aim of this study is to establish speciation of major radionuclides in solution of spent fuel pool.
The retention of trace amounts of radionuclides ($^{60}$Со, $^{137}$Cs, $^{85}$Sr) in model solutions by regenerated cellulose ultrafiltration membrane with MWCO 1000 Da was studied within this research. The model solutions were: distilled water, 0.1 M KNO$_{3}$ and 20 g/L boric acid solution (the composition similar to spent fuel pool medium) at different pH values. Measurements of solutions were carried out by γ – spectrometry method (activity of radionuclides $^{60}$Со, $^{137}$Cs, $^{85}$Sr) and volumetric analysis of boric acid.
The results of radionuclides retention on ultrafiltration membrane depending on solution pH value and solution composition were obtained during of the research. Predictably, boric acid is retained on this membrane slightly, within 5%. Retention of radionuclide $^{60}$Со Co reaches 100% at pH 9 and more, and it weakly depends on solution medium. Probably, this is because of generation of hydrolysis forms of cobalt.
The speciation of all investigated radionuclides is similar (Fig. 1) in boric acid solution in weak acid pH region. Rather, equal speciation is explained by formation of pseudocolloid particles of radionuclides. As illustrated (Fig. 1), that speciation of radionuclides $^{137}$Cs, $^{85}$Sr is uniformly in boric acid solution.
The experiment has shown the possibility of $^{60}$Со, $^{137}$Cs, $^{85}$Sr separation from boric acid solution using membrane methods in the medium of spent fuel pool.
Figure 1

Primary authors

Mr Aleksandr Zarubo (Joint Institute for Power and Nuclear Research – Sosny of the National Academy of Sciences of Belarus) Mr Artsiom Radkevich (Joint Institute for Power and Nuclear Research – Sosny of the National Academy of Sciences of Belarus) Ms Olga Korenkova (Joint Institute for Power and Nuclear Research – Sosny of the National Academy of Sciences of Belarus)

Presentation Materials

There are no materials yet.
Your browser is out of date!

Update your browser to view this website correctly. Update my browser now

×