Calculation and Validation of the Response Matrix for a Neutron Multisphere Spectrometer with an Indium Central
P Vlk1, M Pavlovic2
1BratislavaIon Technologies, BIONT, Inc., Karloveská 63, SK-842 29 Bratislava, Slovak Republic.
Radiation Protection Dosimetry
|October 17, 2017
Summary
This study introduces an indium-based neutron multisphere spectrometer for accurate neutron measurements. The new design offers advantages for characterizing neutron fields near accelerator technologies.
Area of Science:
- Nuclear Physics
- Radiation Detection and Measurement
Background:
- Accelerator technologies require precise neutron field measurements.
- Neutron multisphere spectrometers are crucial for determining neutron energy spectra and dose rates.
- Indium is explored as an alternative activation material for neutron detection.
Purpose of the Study:
- To design and evaluate an indium-based neutron multisphere spectrometer.
- To calculate the spectrometer's response matrix using Monte Carlo simulations.
- To validate the design and assess its suitability for neutron measurements.
Main Methods:
- Utilized Monte Carlo code MCNP5 for response matrix calculation (0.001 eV to 20 MeV).
- Validated the response matrix using an Americium-Beryllium (Am-Be) standard neutron source.
- Employed MAXED code for neutron energy spectra unfolding and dose rate calculations.
Main Results:
- Successfully designed and simulated an indium-based neutron multisphere spectrometer.
- Calculated neutron energy spectra and ambient dose equivalent rates.
- Demonstrated the potential of indium as a viable activation material.
Conclusions:
- The indium-based spectrometer is a promising tool for neutron field characterization.
- Indium offers distinct properties and advantages for neutron spectrometry applications.
- This design contributes to improved safety and characterization in accelerator environments.
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