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Published in 2018 at "Annals of Nuclear Energy"
DOI: 10.1016/j.anucene.2017.11.035
Abstract: Abstract The total neutron cross sections of 93Nb in keV energy region were determined by transmission measurements with the filtered neutron beams from the horizontal channel No. 4 of the Dalat research reactor. The natural…
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Keywords:
filtered neutron;
total neutron;
cross;
neutron beams ... See more keywords
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Published in 2019 at "Radiation Physics and Chemistry"
DOI: 10.1016/j.radphyschem.2019.108435
Abstract: Neutron shielding materials are used in aerospace, space, medical, and nuclear applications and there is a growing need of neutron shielding materials with increased temperature resistance. This is difficult to achieve with the current approach…
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Keywords:
neutron cross;
neutron shielding;
graphene platelets;
gadolinium ... See more keywords
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Published in 2018 at "Journal of Nuclear Science and Technology"
DOI: 10.1080/00223131.2018.1479989
Abstract: ABSTRACT Neutron cross sections of 90,91,92,94,96Zr were calculated in the incident energy (En) range from 200 keV to 20 MeV for the revision of the 4th version of the Japanese Evaluated Nuclear Data Library (JENDL-4.0).…
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Keywords:
cross;
incident energy;
energy range;
cross sections ... See more keywords
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Published in 2017 at "Nuclear Science and Engineering"
DOI: 10.1080/00295639.2017.1354591
Abstract: Abstract Neutron multiplicity counting (NMC) techniques are widely used for nuclear materials accountability and international safeguards applications to quantitatively evaluate characteristic properties pertaining to fissile material. Mathematical models for NMC moments have been previously derived…
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Keywords:
cross talk;
multiplicity;
mass;
fissile mass ... See more keywords