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2005 | 14 | 5 |

Tytuł artykułu

Leaching study on the process of solidification of radionuclide 60 Co in concrete

Autorzy

Warianty tytułu

Języki publikacji

EN

Abstrakty

EN
To assess the safety for disposal of radioactive waste-cement composition, the leaching of ⁶⁰Co from a waste composite into a surrounding fluid has been studied. Leaching tests were carried out in accordance with a method recommended by the IAEA. Determination of retardation factors, K F and coefficients of distribution, k d , using a simplified mathematical model for analyzing the migration of radionuclides, has been developed. Results presented in this paper are examples of results obtained in a 30-year mortar and concrete testing project, which will influence the design of the engineered trench system for a future central radioactive waste disposal center.

Wydawca

-

Rocznik

Tom

14

Numer

5

Opis fizyczny

p.699-701,ref.

Twórcy

autor
  • Vinca Institute of Nuclear Sciences, P.O.Box 522, 11001 Belgrade, Serbia and Montenegro

Bibliografia

  • 1. BURNS R. H. Solidification of Low and Intermediate Level Waste. Atomic Energy Rew. 9, 547,1971.
  • 2. HASHIMOTO I., DESHPANDE K. B., THOMAS S. H. Peclet Numbers and Retardation Factors for Ion Exchange Columns. I&EC Fundamentals. 3, 213, 1964.
  • 3. HESPE E. D. Leach Testing of Immobilized Radioactive Waste Solids. AtomicEnergy Rev. 9,195, 1971.
  • 4. LU A. H. Modelling of Radionuclide Migration from a Low-Level Radioactive Waste burial Site. Health Physics. 34 (39), 39, 1978.
  • 5. MORIYAMA N., DOJIRI S., MATSUZURU H. Leaching of Cs from the Ion-Exchange Resin Incorporated in Polyethylene or Cement Composite. Health Physics. 32,549, 1977.
  • 6. PLECAS I., MIHAJLOVIC LJ., KOSTADINOVIC A. Optimization of concrete containers composition in radioactive waste technology. Radioactive waste management and nuclear fuel cycle. 6 (2), 161, 1985.

Typ dokumentu

Bibliografia

Identyfikatory

Identyfikator YADDA

bwmeta1.element.agro-article-22903b79-0f47-441c-9741-0250b1c5e1db
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