The solubilisation of Ru and U from condensation particles released b overheated nuclear fuel and maturated in air and in argon
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P. Froment
Summary
The emission of uranium and ruthenium oxides from overheated nuclear fuel is a complex phenomenon which depends on fuel matrix, temperature, oxygen potential of the atmosphere in contact and on emission sequence. Furthermore, secondary annealing (“maturation”) reactions of aerosol particles in the gas phase, immediately after emission, strongly influence the properties of particles before their dispersion in the reactor containment building and/or in the environment. Maturation influences surface and bulk gradient composition, particle size, and, as a consequence, weathering rates in the environment. This paper describes how emission and maturation conditions may affect the solubility rates of condensation particles released by overheated U and Ru oxides mixtures, in small-scale laboratory simulations. It will be demonstrated that the presence of Ru decreases the solubilisation rate of U.
© Oldenbourg Wissenschaftsverlag, München
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- Synergistic extraction of uranium(VI) by bis(2,4,4-trimethylpentyl) phosphini acid in the presence of neutral oxo-donors
- Analysis of 237Np in spent fuel solutions
- The solubilisation of Ru and U from condensation particles released b overheated nuclear fuel and maturated in air and in argon
- Contrary effects of the water radiolysis product H2O2 upon th dissolution of nuclear fuel in natural ground water and deionized water
- Accelerator mass spectrometry dating at Çatalhöyük
- Radiochemical separation of no-carrier-added radioniobium from zirconiu targets for application of 90Nb-labelled compounds
- Separation of pertechnetate from molybdate by anion-exchange chromatography: Recovery of 99mTc from (n, γ)99Mo and suitability for use in central radiopharmacy (CRPh)
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Articles in the same Issue
- Photofission of 209Bi at intermediate energies
- Synergistic extraction of uranium(VI) by bis(2,4,4-trimethylpentyl) phosphini acid in the presence of neutral oxo-donors
- Analysis of 237Np in spent fuel solutions
- The solubilisation of Ru and U from condensation particles released b overheated nuclear fuel and maturated in air and in argon
- Contrary effects of the water radiolysis product H2O2 upon th dissolution of nuclear fuel in natural ground water and deionized water
- Accelerator mass spectrometry dating at Çatalhöyük
- Radiochemical separation of no-carrier-added radioniobium from zirconiu targets for application of 90Nb-labelled compounds
- Separation of pertechnetate from molybdate by anion-exchange chromatography: Recovery of 99mTc from (n, γ)99Mo and suitability for use in central radiopharmacy (CRPh)
- Synthesis, radiolabelling characteristics and biological evaluation of the derivatives of mercaptoacetyltriglycine
