Articles with "neutron cross" as a keyword



Photo from wikipedia

Measurements of the total neutron cross sections of 93 Nb by using the filtered neutron beams

Sign Up to like & get
recommendations!
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… read more here.

Keywords: filtered neutron; total neutron; cross; neutron beams ... See more keywords
Photo by thanti_riess from unsplash

Computational and experimental comparison of boron carbide, gadolinium oxide, samarium oxide, and graphene platelets as additives for a neutron shield

Sign Up to like & get
recommendations!
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… read more here.

Keywords: neutron cross; neutron shielding; graphene platelets; gadolinium ... See more keywords
Photo from wikipedia

Theoretical calculation of neutron cross sections for 90,91,92,94,96Zr in the incident energy range between 200 keV and 20 MeV

Sign Up to like & get
recommendations!
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).… read more here.

Keywords: cross; incident energy; energy range; cross sections ... See more keywords
Photo by thanti_riess from unsplash

Neutron Multiplicity Counting Moments for Fissile Mass Estimation in Scatter-Based Neutron Detection Systems

Sign Up to like & get
recommendations!
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… read more here.

Keywords: cross talk; multiplicity; mass; fissile mass ... See more keywords