Abstract
The different streams of waste water which are expected to arise from the operation of the Wackersdorf reprocessing plant were identified as well as their chemical and radiochemical composition. Before the enrichment of tritium by catalytic chemical exchange and electrolysis the remaining contaminations in the waste water must be removed by distillation. In the case of {sup 131}I and {sup 137}Cs, decontamination factors of 200-350 could be achieved. Other contaminations in the distillate were no longer detectable. An electrolyzer operating with a Solid Polymer Electrolyte, after a loading with 4 x 10{sup -5} g of ions could no longer be operated. Comparative experiments were carried out with a TELEDYNE hydrogen generator HG-501. This device requires 35% KOH as the electrolyte solution. There is neither {sup 131}I nor {sup 137}Cs in the generated hydrogen - and oxygen - flow detectable. Up to 99% of the {sup 131}I is fixed at the electrolytic cell. The operating life of the electrolytic cell is estimated to approx. 10 years, it therefore appears to be a suitable device if modified for operation with radioactive solutions containing tritium. Experiments on zirconium hydride formation served the purpose of determining suitable parameters for a trouble-free loading of zirconium
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Citation Formats
Riedel, H J, and Ullrich, W.
Immobilization of tritium enriched waste water from reprocessing by solidification as zirconium hydride; Immobilisierung von angereichertem tritiumabwasser aus der wiederaufarbeitung durch verfestigung als zirkoniumhydrid.
CEC: N. p.,
1993.
Web.
Riedel, H J, & Ullrich, W.
Immobilization of tritium enriched waste water from reprocessing by solidification as zirconium hydride; Immobilisierung von angereichertem tritiumabwasser aus der wiederaufarbeitung durch verfestigung als zirkoniumhydrid.
CEC.
Riedel, H J, and Ullrich, W.
1993.
"Immobilization of tritium enriched waste water from reprocessing by solidification as zirconium hydride; Immobilisierung von angereichertem tritiumabwasser aus der wiederaufarbeitung durch verfestigung als zirkoniumhydrid."
CEC.
@misc{etde_10153745,
title = {Immobilization of tritium enriched waste water from reprocessing by solidification as zirconium hydride; Immobilisierung von angereichertem tritiumabwasser aus der wiederaufarbeitung durch verfestigung als zirkoniumhydrid}
author = {Riedel, H J, and Ullrich, W}
abstractNote = {The different streams of waste water which are expected to arise from the operation of the Wackersdorf reprocessing plant were identified as well as their chemical and radiochemical composition. Before the enrichment of tritium by catalytic chemical exchange and electrolysis the remaining contaminations in the waste water must be removed by distillation. In the case of {sup 131}I and {sup 137}Cs, decontamination factors of 200-350 could be achieved. Other contaminations in the distillate were no longer detectable. An electrolyzer operating with a Solid Polymer Electrolyte, after a loading with 4 x 10{sup -5} g of ions could no longer be operated. Comparative experiments were carried out with a TELEDYNE hydrogen generator HG-501. This device requires 35% KOH as the electrolyte solution. There is neither {sup 131}I nor {sup 137}Cs in the generated hydrogen - and oxygen - flow detectable. Up to 99% of the {sup 131}I is fixed at the electrolytic cell. The operating life of the electrolytic cell is estimated to approx. 10 years, it therefore appears to be a suitable device if modified for operation with radioactive solutions containing tritium. Experiments on zirconium hydride formation served the purpose of determining suitable parameters for a trouble-free loading of zirconium sponge with tritium. Experimental results lead us to the proposal of a new concept for the formation of ZrHT and its final disposal. Batches of 100 g of zirconium sponge are hydrogenated. The HT gas can be directly fixed in batches of 22 litres. Accumulation and storage of the approx. 10 m{sup 3} of HT gas is thus dispensed with. Since fairly small quantities of tritium and protium (180 Ci of tritium in 22 litres of HT gas) are handled per charge the accident potential is low. There is no need for a large-scale facility for handling and fixing HT which is only operated sporadically.}
place = {CEC}
year = {1993}
month = {Jun}
}
title = {Immobilization of tritium enriched waste water from reprocessing by solidification as zirconium hydride; Immobilisierung von angereichertem tritiumabwasser aus der wiederaufarbeitung durch verfestigung als zirkoniumhydrid}
author = {Riedel, H J, and Ullrich, W}
abstractNote = {The different streams of waste water which are expected to arise from the operation of the Wackersdorf reprocessing plant were identified as well as their chemical and radiochemical composition. Before the enrichment of tritium by catalytic chemical exchange and electrolysis the remaining contaminations in the waste water must be removed by distillation. In the case of {sup 131}I and {sup 137}Cs, decontamination factors of 200-350 could be achieved. Other contaminations in the distillate were no longer detectable. An electrolyzer operating with a Solid Polymer Electrolyte, after a loading with 4 x 10{sup -5} g of ions could no longer be operated. Comparative experiments were carried out with a TELEDYNE hydrogen generator HG-501. This device requires 35% KOH as the electrolyte solution. There is neither {sup 131}I nor {sup 137}Cs in the generated hydrogen - and oxygen - flow detectable. Up to 99% of the {sup 131}I is fixed at the electrolytic cell. The operating life of the electrolytic cell is estimated to approx. 10 years, it therefore appears to be a suitable device if modified for operation with radioactive solutions containing tritium. Experiments on zirconium hydride formation served the purpose of determining suitable parameters for a trouble-free loading of zirconium sponge with tritium. Experimental results lead us to the proposal of a new concept for the formation of ZrHT and its final disposal. Batches of 100 g of zirconium sponge are hydrogenated. The HT gas can be directly fixed in batches of 22 litres. Accumulation and storage of the approx. 10 m{sup 3} of HT gas is thus dispensed with. Since fairly small quantities of tritium and protium (180 Ci of tritium in 22 litres of HT gas) are handled per charge the accident potential is low. There is no need for a large-scale facility for handling and fixing HT which is only operated sporadically.}
place = {CEC}
year = {1993}
month = {Jun}
}