Published January 10, 1996
| Version v1
Journal article
Decontamination of nitric acid by distillation or rectification
Description
The undesirable active and non-active components were removed from the simulated solution of nitric acid formed in the course of the absorption of NOx liberated during the vitrification of liquid medium-level nuclear power plant waste. Decontamination factor values of <=105 for both 137Cs and Na and the reduction of the content of inactive salts below the limits required by the State standard for technical nitric acid were attained by rectification. (author) 1 tab., 4 figs., 5 refs
Additional details
Publishing Information
- Journal Title
- Nucleon
- Journal Volume
- 1995
- Journal Issue
- 3
- Journal Page Range
- p. 20-22.
- ISSN
- 1210-2660
- CODEN
- NLEQEM
INIS
- Country of Publication
- Czech Republic
- Country of Input or Organization
- Czech Republic
- INIS RN
- 27023176
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Descriptors DEI
- CESIUM 137; DECONTAMINATION; DISTILLATION; EFFICIENCY; FRACTIONATION; INTERMEDIATE-LEVEL RADIOACTIVE WASTES; NITRIC ACID; NITROGEN OXIDES; RADIOACTIVE WASTE PROCESSING; SIMULATION; SODIUM CHLORIDES; VITRIFICATION
- Descriptors DEC
- ALKALI METAL COMPOUNDS; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CESIUM ISOTOPES; CHALCOGENIDES; CHLORIDES; CHLORINE COMPOUNDS; CLEANING; HALIDES; HALOGEN COMPOUNDS; HYDROGEN COMPOUNDS; INORGANIC ACIDS; INORGANIC COMPOUNDS; INTERMEDIATE MASS NUCLEI; ISOTOPES; MANAGEMENT; MATERIALS; NITROGEN COMPOUNDS; NUCLEI; ODD-EVEN NUCLEI; OXIDES; OXYGEN COMPOUNDS; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; RADIOISOTOPES; SEPARATION PROCESSES; SODIUM COMPOUNDS; WASTE MANAGEMENT; WASTE PROCESSING; WASTES; YEARS LIVING RADIOISOTOPES