Zobrazeno 1 - 10
of 17
pro vyhledávání: '"Henrik Nylén"'
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2014 (2014)
Thorium-plutonium mixed oxide (Th-MOX) fuel has become one of the most promising solutions to reduce a large and increasing plutonium stockpile. Compared with traditional uranium-plutonium mixed oxide (U-MOX) fuels, Th-MOX fuel has higher consumption
Externí odkaz:
https://doaj.org/article/dcd857310b0a4383a1f035f7c9c16682
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2013 (2013)
Computer simulations have been carried out to investigate the possibility of extending operating cycle length in the Pressurised Water Reactor Ringhals 3 by the use of thorium-plutonium oxide fuel. The calculations have been carried out using tools a
Externí odkaz:
https://doaj.org/article/6ac58be857224aed9b1f565248bb7c33
Autor:
Vincent Lamirand, Gabor Por, Imre Pázsit, Mathieu Hursin, Victor Dykin, Pavel Frajtag, Oskari Pakari, Andreas Pautz, Gregory Perret, Henrik Nylén
Publikováno v:
Nuclear Technology. 206:1566-1583
The possibility of measuring the gas-phase velocity in a two-phase mixture through the use of neutron noise techniques is demonstrated in the zero-power reactor CROCUS of the Ecole Polytechnique Fe...
Autor:
Henrik Nylén, Victor Dykin, Gabor Por, Pavel Frajtag, Andreas Pautz, Gregory Perret, Oskari Pakari, Vincent Lamirand, Imre Pázsit, Mathieu Hursin
Publikováno v:
EPJ Web of Conferences, Vol 247, p 08004 (2021)
Recently a joint project has been carried out between the Paul Scherrer Institut, the Ecole Polytechnique Federale de Lausanne and swissnuclear, an industrial partner, in order to determine the axial void distribution in a channel installed in the re
Publikováno v:
Progress in Nuclear Energy. 138:103805
Determination of the local void fraction in BWRs from in-core neutron noise measurements requires the knowledge of the axial velocity of the void. The purpose of this paper is to revisit the problem of determining the axial void velocity profile from
Publikováno v:
Nuclear Science and Engineering. 185:277-293
Advanced sodium-cooled fast reactors with improved safety features, such as the French ASTRID CFV-core concept, is characterized by an axial heteroge- neous core, which will present a challenge on the homogenization procedures used today, taking into
Publikováno v:
Nuclear Science and Engineering. 185:263-276
In axially heterogeneous fast reactor concepts, such as the ASTRID CFV core, the accurate neutronic prediction of control rods is a challenge. In such cores, the performance of the classical 2D equivalence procedure, used for control rod homogenizati
Publikováno v:
EPJ Web of Conferences, Vol 247, p 02013 (2021)
The problem of determining the axial velocity profile from the in-core neutron noise measurements is revisited, with the purpose of developing an objective method for the determination of the void fraction. Until now it was assumed that in order to d
Autor:
Henrik Nylén, Imre Pázsit, Petty Bernitt Cartemo, C. Montalvo, Tell Andersson, Augusto Hernández-Solís
Publikováno v:
Nuclear Science and Engineering. 182:213-227
Core-barrel motion (CBM) surveillance and diagnostics, based on the amplitude of the peaks of the normalized auto power spectral densities (APSDs) of the ex-core neutron detectors, have been performed and continuously developed in Sweden and were app
Publikováno v:
Nuclear Science and Engineering. 181:204-215
Advanced fast reactor concepts, such as the CFV core (French acronym of "Coeur a Foible effet de Vide Sodium," meaning "low sodium void effect core"), are characterized by a heterogeneous axial core arrangement, with an inner fertile zone and a sodiu