270 research outputs found
Ion counting efficiencies at the IGISOL facility
At the IGISOL-JYFLTRAP facility, fission mass yields can be studied at high
precision. Fission fragments from a U target are passing through a Ni foil and
entering a gas filled chamber. The collected fragments are guided through a
mass separator to a Penning trap where their masses are identified. This
simulation work focuses on how different fission fragment properties (mass,
charge and energy) affect the stopping efficiency in the gas cell. In addition,
different experimental parameters are varied (e. g. U and Ni thickness and He
gas pressure) to study their impact on the stopping efficiency. The simulations
were performed using the Geant4 package and the SRIM code. The main results
suggest a small variation in the stopping efficiency as a function of mass,
charge and kinetic energy. It is predicted that heavy fragments are stopped
about 9% less efficiently than the light fragments. However it was found that
the properties of the U, Ni and the He gas influences this behavior. Hence it
could be possible to optimize the efficiency.Comment: 52 pages, 44 figure
Intestinal permeability to iohexol as an in vivo marker of chemotherapy-induced gastrointestinal toxicity in Sprague-Dawley rats
Gastrointestinal toxicity is the most common adverse effect of chemotherapy. Chemotherapeutic drugs damage the intestinal mucosa and increase intestinal permeability. Intestinal permeability is one of the key markers of gastrointestinal function and measuring intestinal permeability could serve as a useful tool for assessing the severity of chemotherapy-induced gastrointestinal toxicity.Peer reviewe
Fractionnement granulométrique de métaux dissous dans les eaux pluviales à Umeå, Suède
Colloque avec actes et comité de lecture. Internationale.International audienc
Light-ion Production And Fission Studies Using The Medley Facility At Tsl
oS(FNDA2006)001 © Copyright owned by the author(s) under the terms of the Creative Commons Attribution-NonCommercial-ShareAlike Licence
Light-ion production in the interaction of 96 MeV neutrons with oxygen
Double-differential cross sections for light-ion (p, d, t, He-3 and alpha)
production in oxygen, induced by 96 MeV neutrons are reported. Energy spectra
are measured at eight laboratory angles from 20 degrees to 160 degrees in steps
of 20 degrees. Procedures for data taking and data reduction are presented.
Deduced energy-differential and production cross sections are reported.
Experimental cross sections are compared to theoretical reaction model
calculations and experimental data at lower neutron energies in the literature.
The measured proton data agree reasonably well with the results of the model
calculations, whereas the agreement for the other particles is less convincing.
The measured production cross sections for protons, deuterons, tritons and
alpha particles support the trends suggested by data at lower energies.Comment: 21 pages, 13 figures, submitted to Phys. Rev.
Propagation of nuclear data uncertainties for ELECTRA burn-up calculations
The European Lead-Cooled Training Reactor (ELECTRA) has been proposed as a
training reactor for fast systems within the Swedish nuclear program. It is a
low-power fast reactor cooled by pure liquid lead. In this work, we propagate
the uncertainties in Pu-239 transport data to uncertainties in the fuel
inventory of ELECTRA during the reactor life using the Total Monte Carlo
approach (TMC). Within the TENDL project the nuclear models input parameters
were randomized within their uncertainties and 740 Pu-239 nuclear data
libraries were generated. These libraries are used as inputs to reactor codes,
in our case SERPENT, to perform uncertainty analysis of nuclear reactor
inventory during burn-up. The uncertainty in the inventory determines
uncertainties in: the long-term radio-toxicity, the decay heat, the evolution
of reactivity parameters, gas pressure and volatile fission product content. In
this work, a methodology called fast TMC is utilized, which reduces the overall
calculation time. The uncertainty in the long-term radiotoxicity, decay heat,
gas pressure and volatile fission products were found to be insignificant.
However, the uncertainty of some minor actinides were observed to be rather
large and therefore their impact on multiple recycling should be investigated
further. It was also found that, criticality benchmarks can be used to reduce
inventory uncertainties due to nuclear data. Further studies are needed to
include fission yield uncertainties, more isotopes, and a larger set of
benchmarks.Comment: 4 pages, 4 figures, Proc. 2013 International Conference on Nuclear
Data for Science & Technology (ND2013), March 4-8, 2013, New York, USA, to be
published in Nuclear Data Sheet
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