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Determination of the spatial response of neutron based analysers using a Monte Carlo based method

  • Published:2000-11 Issue:4-5 Volume:53 Page:507-513
  • ISSN:0969-8043
  • Container-title:Applied Radiation and Isotopes
  • language:en
  • Short-container-title:Applied Radiation and Isotopes

Author:

Tickner James

Publisher

Elsevier BV

Subject

Radiation

Reference12 articles.

1. Atwell, T.L., 1998. Enhancement of measurement accuracy in bulk material analyzer. US Patent 5,732,115

2. Briesmeister, J. (Ed.), 1997. MCNP — a general purpose Monte Carlo N-particle transport code, Los Alamos National Laboratory Report LA-12625-M

3. Nuclear methods for on-line analysis of metalliferous and nonmetalliferous minerals;Clayton,1991

4. Single peak versus library least-squares analysis methods for the PGNAA analysis of vitrified waste;Gardner;Appl. Radiat. Isotopes,1997

5. Gehrke, R.J., et al., 1995. Application of PGNAA to preincineration assay of combustible waste for chlorine. Trans. Amer. Nucl. Sci., 117

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3. Evaluation the nonlinear response function of a 3×3in NaI scintillation detector for PGNAA applications;Applied Radiation and Isotopes;2007-08

4. Sample to moderator volume ratio effects in neutron yield from a PGNAA setup;Radiation Measurements;2007-02

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