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| 2. |
- Tesinsky, Milan, 1982-
(författare)
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MCNPX Simulations for Neutron Cross Section Measurements
- 2010
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Licentiatavhandling (övrigt vetenskapligt/konstnärligt)abstract
- This thesis presents MCNPX simulations of the SCANDAL set-up used at the Theodor Svedberg Laboratory for neutron scattering cross-section measurements. The thesis describes processes and data important for the upcoming off-line data analysis. In the experiment, neutrons scattered off the target are converted to protons which are stopped in scintillator crystals. The results of presented simulations include a description of the proton spectra in dependence of the neutron-to-proton conversion angle, calculation of the hit position gates and a study of the converter describing the role of its chemical composition and also the role of other plastic scintillator on the proton spectra.
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| 3. |
- Tesinsky, Milan, 1982-
(författare)
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Science and Technology for Americium Transmutation
- 2012
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Doktorsavhandling (övrigt vetenskapligt/konstnärligt)abstract
- Americium could be seen as the most troublesome element that is presentin nuclear fuel. This thesis offers different points of view on the possibility ofamericium transmutation. The first point of view elaborates simulations ofamericium-bearing facilities, namely nuclear data, a popular computationalcode and modeling techniques. The second point of view is focused on practicalusage of the simulations to examine upper limit of americium in a specificreactor.
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| 4. |
- Tesinsky, Milan, et al.
(författare)
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The impact of americium on the ULOF and UTOP transients of the European Lead-cooled SYstem (ELSY)
- 2012
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Ingår i: Annals of Nuclear Energy. - : Elsevier BV. - 0306-4549 .- 1873-2100. ; 47, s. 104-109
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Tidskriftsartikel (refereegranskat)abstract
- The Unprotected Loss-of-Flow (ULOF) transient and the Unprotected Transient-Over-Power (UTOP) have been evaluated for the European Lead-cooled SYstem (ELSY) for americium concentrations in the fuel between 0% and 10%. With americium in the core, the ELSY design exceeds the maximum allowed asymptotic temperature limit for fuel during UTOP, except for low Am contents. During ULOF, fuel and clad temperatures stabilize below the asymptotic temperature limits.
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| 5. |
- Tesinsky, Milan, et al.
(författare)
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The impact of americium on transients in the European Lead-cooled SYstem ELSY loaded with nitride fuel
- 2012
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Ingår i: Annals of Nuclear Energy. - : Elsevier BV. - 0306-4549 .- 1873-2100. ; 50, s. 56-62
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Tidskriftsartikel (refereegranskat)abstract
- The Unprotected Loss-of-Flow transient (ULOF) and the Unprotected Transient-Over-Power (UTOP) have been evaluated for a modified design of the European Lead-cooled SYstem (ELSY) using nitride fuel. Additional americium has been added to the core in concentrations of 0%, 4% and 8%. During ULOF, fuel and clad asymptotic temperatures stabilize below limits. For UTOP, however, the maximum allowed cladding temperature limit is exceeded at EOC and introduction of a power penalty is necessary for Am transmutation. The power penalty is higher than that reported for SFR.
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