Monte Carlo modelling of neutron depth dose distributions in optimizing prompt gamma in vivo neutron activation analysis systems

https://doi.org/10.1016/0969-8043(94)90130-9Get rights and content

Abstract

Optimization of prompt gamma in vivo neutron activation analysis systems is best achieved using Monte Carlo simulation. In this study the modelling of the dimensions and materials for source holders and collimators is described and compared with experimentally derived results where feasible. Results show that valid depth doses are obtained by modelling only the central part of an IVNAA system and that the use of borated paraffin as a reflector provides acceptable thermal fluence and depth dose.

References (16)

  • K. Boddy et al.

    The development of a facility for partial body in vivo activation analysis using californium-252 neutron sources

    Phys. Med. Biol.

    (1974)
  • A.A. Chan

    Monte Carlo calculations for an in vivo neutron activation analysis system

  • A.A. Chan et al.

    Application of the Monte Carlo technique to the study of radiation transport in a prompt in vivo neutron activation system

    Australas. Phys. Engng Sci. Med.

    (1985)
  • D.M. Franklin et al.

    An improved in vivo neutron activation analysis system for measuring kidney cadmium

    Phys. Med. Biol.

    (1990)
  • IAEA

    Handbook on Nuclear Activation Data

    (1987)
  • IAEA

    Compendium of Neutron Spectra and Detector Responses for Radiation Protection Purposes

    (1990)
  • ICRP

    1990 Recommendations of the International Commission on Radiological Protection

There are more references available in the full text version of this article.

Cited by (3)

  • A Monte Carlo simulation of neutron activation analysis of bulk objects

    2009, Radiation Measurements
    Citation Excerpt :

    The highest number of 0.478 MeV photons in the pulse height distribution, occurs in the case of the graphite filter with an increase by a factor of 1.29 over the case without filter (Table 2). This is due to the very good moderating and scattering properties of graphite, with a high elastic and inelastic scattering neutron cross-section and a high average neutron energy loss/collision (Utteridge et al., 1994). Hence, the moderating capability would shield off region #1 from the neutron beam, while the scattering capabilities would reflect neutrons towards region #2.

  • Chemometrics

    1996, Analytical Chemistry
View full text