Published January 1980
| Version v1
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Concentration, conditioning, storage and disposal of tritium-bearing waste
- 1. Oesterreichische Studiengesellschaft fuer Atomenergie G.m.b.H., Seibersdorf. Hauptabteilung Abfallverarbeitung
Description
A review is given on the technical possibilities to remove tritium from the waste-streams of nuclear facilities, as reactors, reprocessing plants, laboratories etc. The methods for concentration, immobilization, storing and disposing are discussed. A review is given on the detection methods for tritium in several concentration ranges. Safety considerations are showing, that removal of tritium from waste streams is only necessary at certain types of reactors and reprocessing plants, to avoid punctual releases of high concentrations. A basic evaluation shows, that the natural tritium production is much higher than the total tritium of all nuclear reactors. (author)
Availability note (English)
MF available from INIS under the Report Number.Files
12586091.pdf
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Additional details
Additional titles
- Original title (German)
- Anreicherung, Konditionierung und Endlagerung Tritium-haeltiger Abfaelle
Publishing Information
- Imprint Pagination
- 46 p.
- Report number
- SGAE--3083
INIS
- Country of Publication
- Austria
- Country of Input or Organization
- Austria
- INIS RN
- 12586091
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Descriptors DEI
- ISOTOPE SEPARATION; RADIOACTIVE WASTE DISPOSAL; RADIOACTIVE WASTE PROCESSING; RADIOACTIVE WASTE STORAGE; TRITIUM
- Descriptors DEC
- BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; HYDROGEN ISOTOPES; ISOTOPES; LIGHT NUCLEI; MANAGEMENT; NUCLEI; ODD-EVEN NUCLEI; RADIOISOTOPES; SEPARATION PROCESSES; STORAGE; WASTE DISPOSAL; WASTE MANAGEMENT; WASTE PROCESSING; WASTE STORAGE; YEARS LIVING RADIOISOTOPES
Optional Information
- Secondary number(s)
- AV--2/80.