Studies on the immobilization of technetium under near field geochemical conditions
Creators
- 1. Forschungszentrum Karlruhe, Inst. fuer Nukleare Entsorgungstechnik (Germany)
Description
The immobilization of technetium dissolved in salt brines, which are in contact with simulated spent fuel and HAW glass packages, has been studied under aerobic conditions at room temperature. The retention effect of spent fuel packages has been investigated by adding UO2, hull (zircaloy-4) and container material (iron) in appropriate ratios to NaCl- and MgCl2-rich salt brines containing an initial TcO-4 concentration of 10-5 mol/L. The time dependence of the Tc concentration, pH and Eh has been measured simultaneously. Analoguous investigations have been carried out with borosilicate HAW glass. According to this scenario, container material (stainless steel) has been added to the salt solutions. In the system simulating the disposal of spent fuel, the Tc concentration decreases to less than 10-8 mol/L within 50 days, while in the system simulating the disposal of vitrified HAW, the immobilization of Tc is less efficient. In the latter case, even after 500 days there are still about 50-80% of the initial Tc dissolved. In both systems the addition of sulfide has a positive influence on the immobilization of Tc. The results are discussed in terms of reduction of Tc(VII) to sparingly soluble Tc(IV) hydrous oxide, sorption of technetium and precipitation of Tc2S7. (orig.)
Additional details
Publishing Information
- Journal Title
- Radiochimica Acta
- Journal Volume
- 74
- Journal Page Range
- p. 159-163.
- ISSN
- 0033-8230
- CODEN
- RAACAP
Conference
- Title
- 5. international conference on the chemistry and migration behaviour of actinides and fission products in the geosphere (Migration-5).
- Dates
- 10-15 Sep 1995.
- Place
- Saint-Malo (France).
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 28017567
- Subject category
- S58: GEOSCIENCES; S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BRINES; CHEMICAL REACTIONS; CONTAINERS; ION MOBILITY; PH VALUE; RADIOACTIVE WASTE DISPOSAL; RADIOECOLOGICAL CONCENTRATION; SPENT FUELS; TECHNETIUM 99
- Descriptors DEC
- BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; ECOLOGICAL CONCENTRATION; ENERGY SOURCES; FUELS; HOURS LIVING RADIOISOTOPES; INTERMEDIATE MASS NUCLEI; INTERNAL CONVERSION RADIOISOTOPES; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; MANAGEMENT; MATERIALS; MOBILITY; NUCLEAR FUELS; NUCLEI; ODD-EVEN NUCLEI; PARTICLE MOBILITY; RADIOISOTOPES; REACTOR MATERIALS; TECHNETIUM ISOTOPES; WASTE DISPOSAL; WASTE MANAGEMENT; YEARS LIVING RADIOISOTOPES