Retention of Cs-137 on concrete samples
Creators
- 1. Institute for Nuclear Research, PO Box 78, 1 Campului Street, 0300 Pitesti, Jud. Arges (Romania)
Description
The near-field disposal facility will be designed to provide effective containment for the radionuclides in the waste repository. Its design is based on a concept of multi-barrier containment, both physical (by steel and concrete packaging) and chemical containment. It is based on development of a uniform, beneficial aqueous condition and due both to the provision of a high sorption capacity across the repository cell and to geological isolation. The goal of this paper is to evaluate by means of DUST-MS computer code the chemical containment process (sorption capacity of backfill, distribution coefficient) of one potential contaminant which can be released from radioactive wastes conditioned form disposed in this repository, because of the dissolution/leaching processes. (authors)
Availability note (English)
Available from author(s) or Romanian Nuclear Energy Association, AREN, Str. Atomistilor 111, PO Box 53, RO-76900 Bucharest - Magurele (RO) or University Politehnica of Bucharest, Splaiul Independentei 313, Sector 6, RO-77206 Bucharest (RO)Additional details
Identifiers
Publishing Information
- Publisher
- Romanian Nuclear Energy Association, AREN
- Imprint Place
- Bucharest (Romania)
- Imprint Title
- Programme of the International Symposium on Nuclear Energy SIEN 2003, Nuclear Power - A New Challenge
- Imprint Pagination
- 606 p.
- Journal Page Range
- p. 553-557
Conference
- Title
- SIEN 2003, International Symposium on Nuclear Energy, Nuclear Power - A New Challenge
- Dates
- 22-25 Oct 2003
- Place
- Bucuresti (Romania)
INIS
- Country of Publication
- Romania
- Country of Input or Organization
- Romania
- INIS RN
- 35052680
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BACKFILLING; CANDU TYPE REACTORS; CARBON 14; CESIUM 134; CESIUM 137; CONCENTRATION RATIO; CONCRETES; CONTAINMENT; D CODES; DISTRIBUTION; RADIOACTIVE WASTE DISPOSAL; RADIONUCLIDE KINETICS; RETENTION FUNCTIONS; SORPTION; STAINLESS STEELS
- Descriptors DEC
- ALLOYS; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; BUILDING MATERIALS; CARBON ADDITIONS; CARBON ISOTOPES; CESIUM ISOTOPES; COMPUTER CODES; ELECTRON CAPTURE RADIOISOTOPES; EVEN-EVEN NUCLEI; FUNCTIONS; HEAVY WATER MODERATED REACTORS; HIGH ALLOY STEELS; HOURS LIVING RADIOISOTOPES; INTERMEDIATE MASS NUCLEI; INTERNAL CONVERSION RADIOISOTOPES; IRON ALLOYS; IRON BASE ALLOYS; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; KINETICS; LIGHT NUCLEI; MANAGEMENT; MATERIALS; NUCLEI; ODD-EVEN NUCLEI; ODD-ODD NUCLEI; POWER REACTORS; PRESSURE TUBE REACTORS; RADIOACTIVE WASTE MANAGEMENT; RADIOISOTOPES; REACTORS; STEELS; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WASTE DISPOSAL; WASTE MANAGEMENT; YEARS LIVING RADIOISOTOPES
Optional Information
- Notes
- 6 refs., 3 figs., 3 tabs.