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2005 | 14 | 5 |

Tytuł artykułu

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

Autorzy

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.

Identyfikator YADDA

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