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Simulation of alpha dose for predicting radiolytic species at the surface of spent nuclear fuel pellets

Becker, F. ORCID iD icon 1; Kienzler, B. 1
1 Institut für Nukleare Entsorgung (INE), Karlsruher Institut für Technologie (KIT)


In many countries, spent nuclear fuel is considered as a waste form to be disposed of in underground disposal. Under deep host rock conditions, a reducing environment prevails. In the case of water contact, long-term radionuclide release from the fuel depends on dissolution processes of the UO$_{2}$ matrix. The dissolution rate of irradiated UO$_{2}$ is controlled by oxidizing processes facilitated by dissolved species formed by alpharadiolysis of water in contact with spent nuclear fuel. To understand the effect of the radiation, the information of the dose rate at the surface of the fuel and its proximity is needed. α particles contribute strongly due to their high linear energy transfer. However, their dose rate and the energy deposition at the fuel surface are difficult to measure. Cylindrical fuel pellets as used in fuel rods show specific features, such as the rim zone, where a higher Pu concentration and a different porosity of the fuel matrix is present. The a particle dose rate was determined by simulations with the code MCNPX with focus on the rim zone of a pellet. As a result a 40% increased dose level in the rim zone exists in comparison to the center of a pellet. ... mehr

Volltext §
DOI: 10.5445/IR/110100015
DOI: 10.1515/chem-2015-0076
Zitationen: 2
Web of Science
Zitationen: 1
Zitationen: 1
Cover der Publikation
Zugehörige Institution(en) am KIT Institut für Nukleare Entsorgung (INE)
Publikationstyp Zeitschriftenaufsatz
Publikationsjahr 2015
Sprache Englisch
Identifikator ISSN: 2391-5420
KITopen-ID: 110100015
HGF-Programm 32.01.16 (POF III, LK 01) Strahlenschutzforschung
Erschienen in Open chemistry
Verlag De Gruyter Open
Band 13
Seiten 586-590
Nachgewiesen in Web of Science
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