Choice of protective barriers for radioactive wastes' localization
Description
In this paper a protective ability of engineering barriers based on possibility estimation of radionuclides delocalization from storage is discussed. Radionuclide migration through the thickness of protective barriers (multi-layer medium) is described with known one-degree equation of non-stationary diffusive-convective mass-transfer. Equation has put in computer program used for modeling of mass-transfer processes in protective layers of designed storage facilities intended for low- and middle-radioactive wastes. Protective layers' parameters as well as theirs composed material and their thickness has been selected during modeling process under corresponding diffusion coefficient, sorption coefficient and convention rate. Here with two variants of radionuclides delocalization into surrounding have been examined: 1) the best variant - radionuclides diffusion with maximum activity through protective barriers (protective barriers are not broken); 2) the worst variant -radionuclides'diffusion through protective barriers with regard of convective transfer (protective barriers are broken). The main criterion of protective barriers' choice is attainment of dominating radionuclides concentration not increasing the established norms, on the side of protective layer contacting to surroundings during radioactive wastes storage-time. Dominating radionuclides have been chosen either as radionuclides with high migration ability and/or as these with maximum content in wastes. 4 figs
Additional details
Publishing Information
- Publisher
- Omega Info.
- Imprint Place
- Bratislava (Slovakia)
- ISBN
- 80-967741-0-7
- Imprint Title
- Separation of Ionic Solutes. Vol. 7. The abstracts of the seventh international conference.
- Imprint Pagination
- 254 p.
- Journal Volume
- 1
- Series
- Omega Info series in studies in nuclear chemistry and radioecology.
- Journal Page Range
- p. 148-150.
Conference
- Title
- 7. international conference on Separation of Ionic Solutes.
- Acronym
- SIS'97
- Dates
- 18-23 May 1997.
- Place
- Piestany Spa (Slovakia).
INIS
- Country of Publication
- Slovakia
- Country of Input or Organization
- Slovakia
- INIS RN
- 29000147
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Resource subtype / Literary indicator
- Conference, Numerical Data, Non-conventional Literature, Computer Program Description
- Descriptors DEI
- CESIUM 137; COBALT 60; COMPUTER CODES; COMPUTER PROGRAM DOCUMENTATION; CONVECTION; DIFFUSION; ENGINEERED SAFETY SYSTEMS; EXPERIMENTAL DATA; FISSION PRODUCT RELEASE; RADIOACTIVE EFFLUENTS; RADIOACTIVE WASTE DISPOSAL; RADIOACTIVE WASTE FACILITIES; RADIOACTIVE WASTE STORAGE; RADIOECOLOGY; RADIONUCLIDE MIGRATION; RADIUM 226
- Descriptors DEC
- ALPHA DECAY RADIOISOTOPES; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CARBON 14 DECAY RADIOISOTOPES; CESIUM ISOTOPES; COBALT ISOTOPES; DATA; ECOLOGY; ENERGY TRANSFER; ENVIRONMENTAL TRANSPORT; EVEN-EVEN NUCLEI; HEAT TRANSFER; HEAVY ION DECAY RADIOISOTOPES; HEAVY NUCLEI; INFORMATION; INTERMEDIATE MASS NUCLEI; INTERNAL CONVERSION RADIOISOTOPES; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; MANAGEMENT; MASS TRANSFER; MATERIALS; MINUTES LIVING RADIOISOTOPES; NUCLEAR FACILITIES; NUCLEI; NUMERICAL DATA; ODD-EVEN NUCLEI; ODD-ODD NUCLEI; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; RADIOISOTOPES; RADIUM ISOTOPES; STORAGE; WASTE DISPOSAL; WASTE MANAGEMENT; WASTE STORAGE; WASTES; YEARS LIVING RADIOISOTOPES