Measurements and Monte Carlo calculations of gamma and neutron flux spectra inside and behind iron/steel/water configurations


Measurements and Monte Carlo calculations of gamma and neutron flux spectra inside and behind iron/steel/water configurations

Boehmer, B.; Konheiser, J.; Noack, K.; Rogov, A.; Stephan, I.; Hansen, W.; Hinke, D.; Unholzer, S.; Grantz, M.; Mehner, H.-C.

Gamma and neutron flux spectra were measured inside and behind various combined iron, steel and water slabs, which were set up in the radial beams of the zero-power training and research reactors AKR of the Technical University Dresden and ZLFR of the University of Applied Sciences Zittau/Görlitz. The measurements were carried out with a liquid NE-213 scintillation spectrometer in the energy ranges 0.23-10 MeV for photons and 1-20 MeV for neutrons. These experiments were simulated with help of the Monte Carlo transport codes MCNP-4C2 and TRAMO. With MCNP the energy point-wise representation of the nuclear data from ENDF/B-VI library, release 8, was used but with TRAMO effective group cross sections prepared by means of NJOY from the same data library. The paper describes the experiments and calculations and exemplarily presents and compares some results.

Keywords: Neutron/Gamma flux spectra; NE-213 scintillation spectrometer; neutron/gamma transport calculations; Monte Carlo method; MCNP; TRAMO

  • Lecture (Conference)
    12th International Symposium on Reactor Dosimetry, 08.-13.05.2005, Gatlinburg, United States
  • Journal of ASTM International 3(2006)8
  • Contribution to proceedings
    12 th International Symposium on Reactor Dosimetry, 08.-13.05.2005, Gatlinburg, United States
    Reactor Dosimetry: 12th International Symposium, West Conshohocken: ASTM, 978-0-8031-3412-6

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