Publication detail

EXPERIMENTAL INVESTIGATION OF NANOTUBES UTILIZATION AS A NUCLEAR FUEL MATRIX ADDITIVE

VARMUŽA, J. KATOVSKÝ, K. FORAL, Š. MATĚJKOVÁ, J.

Original Title

EXPERIMENTAL INVESTIGATION OF NANOTUBES UTILIZATION AS A NUCLEAR FUEL MATRIX ADDITIVE

English Title

EXPERIMENTAL INVESTIGATION OF NANOTUBES UTILIZATION AS A NUCLEAR FUEL MATRIX ADDITIVE

Type

conference paper

Language

en

Original Abstract

Knowledge of the materials behavior is particularly required in the environment where the materials are exposed to neutron flux. This article focuses on new promising materials that can be used in a nuclear fuel, a nuclear reactor or its closest vicinity. Carbon nano materials can be included among these types of materials. Composite materials have generally improved mechanical and thermal properties with addition of nanoparticles. However the additives itself have an impact on the behavior of the neutron field. This article describes an experiment that examined the behavior of neutrons in carbon nano materials. The main goal of the experiment was to determine how neutron scattering is affected, when the sample is exposed to neutron beam. The aim of the experiment was to determine the influence of the different types of nano materials on the neutron beam. The main nano materials used during the experiment were unoriented multi walled carbon nano tubes, carbon nano fibers and common graphite.

English abstract

Knowledge of the materials behavior is particularly required in the environment where the materials are exposed to neutron flux. This article focuses on new promising materials that can be used in a nuclear fuel, a nuclear reactor or its closest vicinity. Carbon nano materials can be included among these types of materials. Composite materials have generally improved mechanical and thermal properties with addition of nanoparticles. However the additives itself have an impact on the behavior of the neutron field. This article describes an experiment that examined the behavior of neutrons in carbon nano materials. The main goal of the experiment was to determine how neutron scattering is affected, when the sample is exposed to neutron beam. The aim of the experiment was to determine the influence of the different types of nano materials on the neutron beam. The main nano materials used during the experiment were unoriented multi walled carbon nano tubes, carbon nano fibers and common graphite.

Keywords

Scattering, nano material, nano tube, neutron beam.

RIV year

2014

Released

09.07.2014

ISBN

978-0-7918-4594-3

Book

Proccedings on 2014 22nd International Conference on Nuclear Engineering (ICONE 22)

Pages from

354

Pages to

363

Pages count

9

Documents

BibTex


@inproceedings{BUT108855,
  author="Jan {Varmuža} and Karel {Katovský} and Štěpán {Foral} and Jitka {Vojáčková}",
  title="EXPERIMENTAL INVESTIGATION OF NANOTUBES UTILIZATION AS A NUCLEAR FUEL MATRIX ADDITIVE",
  annote="Knowledge of the materials behavior is particularly required in the environment where the materials are exposed to neutron flux. This article
focuses on new promising materials that can be used in a nuclear fuel, a nuclear reactor or its closest vicinity. Carbon nano materials can be included among these types of materials. Composite materials have generally improved mechanical and thermal properties with addition of nanoparticles. However the additives itself have an impact on the behavior of the neutron field. This article describes an experiment that examined the behavior of neutrons in carbon nano materials. The main goal of the experiment was to determine how neutron scattering is affected, when the sample is exposed to neutron beam. The aim of the experiment was to determine the influence of the different
types of nano materials on the neutron beam. The main nano materials used during the experiment were unoriented multi walled carbon nano
tubes, carbon nano fibers and common graphite.",
  booktitle="Proccedings on 2014 22nd International Conference on Nuclear Engineering (ICONE 22)",
  chapter="108855",
  howpublished="electronic, physical medium",
  year="2014",
  month="july",
  pages="354--363",
  type="conference paper"
}