Abstract
The waste form studies serve to determine the activities released from low and intermediate-level cemented waste forms via the water path (leaching). The work performed was concentrated on the behaviour of the actinide elements. Beside a kinetic approach, a concept of chemical equilibrium is used for the quantitative description of radionuclide mobilization. According to that concept, a thermodynamic equilibrium between the solid phases (waste form, container material, back filling) and a solution phase (brine) establishes itself for each radionuclide. The equilibrium concentration of the radionuclides may be determined in that case by the solubility or the absorption/adsorption equilibria. As a result of the investigation of the equilibrium concentrations for the respective waste form/brine system under specific conditions (p, T, E{sub h}) maximum values are obtained for the radionuclide concentrations which can be directly used in safety considerations. The majority of investigations were performed on a laboratory scale with tracered samples (uranium, americium, plutonium, neptunium). In addition, laboratory experiments were carried out with real cemented waste forms in order to examine whether the results obtained with tracered samples can be transferred to real waste forms. A limited number of experiments were performed with inactive and active (real) full-scale samples (200 l).
More>>
Vejmelka, P;
Rudolph, G;
Kluger, W
[1]
- Kernforschungszentrum Karlsruhe GmbH (DE). Inst. fuer Nukleare Entsorgungstechnik
Citation Formats
Vejmelka, P, Rudolph, G, and Kluger, W.
Investigation of low and medium-level cemented waste forms from reprocessing Task 3 Characterization of radioactive waste forms A series of final reports (1985-89) No 4.
France: N. p.,
1991.
Web.
Vejmelka, P, Rudolph, G, & Kluger, W.
Investigation of low and medium-level cemented waste forms from reprocessing Task 3 Characterization of radioactive waste forms A series of final reports (1985-89) No 4.
France.
Vejmelka, P, Rudolph, G, and Kluger, W.
1991.
"Investigation of low and medium-level cemented waste forms from reprocessing Task 3 Characterization of radioactive waste forms A series of final reports (1985-89) No 4."
France.
@misc{etde_10131322,
title = {Investigation of low and medium-level cemented waste forms from reprocessing Task 3 Characterization of radioactive waste forms A series of final reports (1985-89) No 4}
author = {Vejmelka, P, Rudolph, G, and Kluger, W}
abstractNote = {The waste form studies serve to determine the activities released from low and intermediate-level cemented waste forms via the water path (leaching). The work performed was concentrated on the behaviour of the actinide elements. Beside a kinetic approach, a concept of chemical equilibrium is used for the quantitative description of radionuclide mobilization. According to that concept, a thermodynamic equilibrium between the solid phases (waste form, container material, back filling) and a solution phase (brine) establishes itself for each radionuclide. The equilibrium concentration of the radionuclides may be determined in that case by the solubility or the absorption/adsorption equilibria. As a result of the investigation of the equilibrium concentrations for the respective waste form/brine system under specific conditions (p, T, E{sub h}) maximum values are obtained for the radionuclide concentrations which can be directly used in safety considerations. The majority of investigations were performed on a laboratory scale with tracered samples (uranium, americium, plutonium, neptunium). In addition, laboratory experiments were carried out with real cemented waste forms in order to examine whether the results obtained with tracered samples can be transferred to real waste forms. A limited number of experiments were performed with inactive and active (real) full-scale samples (200 l). These investigations were carried out to determine the influence of the cementation process on the waste form properties. The target was to elaborate results which can be used to formulate the source term for the description of the long-term activity release from cemented waste forms. 16 figs; 10 tabs.; 8 refs.}
place = {France}
year = {1991}
month = {Dec}
}
title = {Investigation of low and medium-level cemented waste forms from reprocessing Task 3 Characterization of radioactive waste forms A series of final reports (1985-89) No 4}
author = {Vejmelka, P, Rudolph, G, and Kluger, W}
abstractNote = {The waste form studies serve to determine the activities released from low and intermediate-level cemented waste forms via the water path (leaching). The work performed was concentrated on the behaviour of the actinide elements. Beside a kinetic approach, a concept of chemical equilibrium is used for the quantitative description of radionuclide mobilization. According to that concept, a thermodynamic equilibrium between the solid phases (waste form, container material, back filling) and a solution phase (brine) establishes itself for each radionuclide. The equilibrium concentration of the radionuclides may be determined in that case by the solubility or the absorption/adsorption equilibria. As a result of the investigation of the equilibrium concentrations for the respective waste form/brine system under specific conditions (p, T, E{sub h}) maximum values are obtained for the radionuclide concentrations which can be directly used in safety considerations. The majority of investigations were performed on a laboratory scale with tracered samples (uranium, americium, plutonium, neptunium). In addition, laboratory experiments were carried out with real cemented waste forms in order to examine whether the results obtained with tracered samples can be transferred to real waste forms. A limited number of experiments were performed with inactive and active (real) full-scale samples (200 l). These investigations were carried out to determine the influence of the cementation process on the waste form properties. The target was to elaborate results which can be used to formulate the source term for the description of the long-term activity release from cemented waste forms. 16 figs; 10 tabs.; 8 refs.}
place = {France}
year = {1991}
month = {Dec}
}