Zobrazeno 1 - 8
of 8
pro vyhledávání: '"Sergei Lemehov"'
Autor:
M. Wéber, Y. Parthoens, B. Boer, J. McGinley, M. Gysemans, Marc Verwerft, Sergei Lemehov, Joseph Somers
Publikováno v:
Journal of Nuclear Materials. 471:97-109
This paper examines the in-pile safety performance of (Th,Pu)O 2 fuel pins under simulated Pressurized Water Reactor (PWR) conditions. Both sol–gel and SOLMAS produced (Th,Pu)O 2 fuels at enrichments of 7.9% and 12.8% in Pu/HM have been irradiated
Publikováno v:
Progress in Nuclear Energy. 57:117-124
This paper focuses on the modelling of fission gas release in mixed oxide fuel. In a first part, the irradiation experiment, conducted by the Japanese Nuclear Energy Safety organization on high enriched mixed oxide fuel, is outlined. In a second part
Publikováno v:
Defect and Diffusion Forum. :215-220
Among the various products originating from fission events, the noble gas elements Xe and, in a lesser extent, Kr present important fission yields. The accumulated gas inventory in its various states (e.g. atomically dissolved, precipitated in caviti
Publikováno v:
Journal of Nuclear Materials. 420:282-290
In-pile diffusion of fission gas is generally modeled through an effective diffusion coefficient that must take into account various phenomena occurring at the grain scale. One of these relates to the trapping of gas by intragranular bubbles. This tr
Publikováno v:
Journal of Nuclear Materials. 416:179-191
The European Facility for Industrial Transmutation (EFIT) of the minor actinides (MA), from LWR spent fuel is being developed in the integrated project EUROTRANS within the 6th Framework Program of EURATOM. Two composite uranium-free fuel systems, co
Publikováno v:
Journal of Nuclear Materials. 395:131-139
Atomic scale simulation techniques based on empirical potentials have been considered in the present work to get insight on helium diffusion in uranium dioxide. By varying the stoichiometry, together with the system temperature, the performed molecul
Publikováno v:
Journal of Nuclear Materials. 376:66-77
An improved knowledge of nuclear fuel can be gained from a better description of atomic-scale processes such as point defects behaviour under irradiation. In these perspectives, computer simulation techniques involving semi-empirical potentials can p
Publikováno v:
Nuclear Technology. 133:153-168
A three-group model (PLUTON) is described, which predicts the power density distribution, plutonium buildup, and burnup profiles across the fuel pellet radius as a function of in-pile time and parameters characterizing the type of reactor system with