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Background radioactivity level estimation and passive shield optimization using adjoint Monte Carlo method.

Khizar Hayat Satti1, Muhammad Dilband2, Muhammad Tariq Siddique3

  • 1Department of Physics and Applied Mathematics, Pakistan Institute of Engineering and Applied Sciences, Islamabad, Pakistan; Health Physics Division, Pakistan Institute of Nuclear Science and Technology, P.O Nilore, Islamabad, Pakistan.

Applied Radiation and Isotopes : Including Data, Instrumentation and Methods for Use in Agriculture, Industry and Medicine
|August 14, 2024
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Summary
This summary is machine-generated.

This study introduces adjoint Monte Carlo simulations for estimating natural radionuclide activity and optimizing HPGe detector shielding. A 12 cm lead shield significantly reduces background radiation, ensuring safety.

Keywords:
Adjoint Monte Carlo simulationsEnvironmental radioactivityFEPEGeant4Health risksShielding optimization

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Area of Science:

  • Nuclear Physics
  • Radiation Detection and Measurement
  • Computational Physics

Background:

  • High-purity germanium (HPGe) detectors are crucial for radiation analysis.
  • Estimating natural radionuclide activity and optimizing shielding are vital for accurate measurements.
  • Passive shielding is essential for reducing background noise in HPGe detector systems.

Purpose of the Study:

  • To develop and validate a procedure for estimating natural radionuclide activity concentration using adjoint Monte Carlo (MC) simulations.
  • To optimize passive shielding solutions for HPGe detectors.
  • To assess radiological risks associated with natural radioactivity in building materials and shielding.

Main Methods:

  • Utilized Geant4 adjoint MC simulation technique for the first time for HPGe detector shielding optimization and radionuclide activity estimation.
  • Acquired background spectra with and without shielding to determine radionuclide concentrations.
  • Validated detector design by comparing computed and measured Full Energy Peak Efficiency (FEPE) for various point sources.

Main Results:

  • Activity concentrations of 40K, 226Ra, and 232Th in building materials were determined (e.g., 524 ± 140 Bqkg-1 for 40K).
  • Natural radioactivity levels in lead shielding were measured (e.g., 155.7 ± 0.1 mBqkg-1 for 40K).
  • Optimal lead shield thickness of 12 cm was found to reduce background by two orders of magnitude; all radiological parameters were within safe limits.

Conclusions:

  • Adjoint MC simulations in Geant4 provide a rapid and viable solution for background radiation analysis and HPGe detector shield optimization.
  • Building materials used in the laboratory are radiologically safe.
  • The developed procedure effectively estimates natural radionuclide activity and optimizes shielding, enhancing detector performance.