Monte Carlo calculation of CR-39 efficiency for fast neutron detection using a combination of MCNP and SRIM codes, and comparison with experimental results

Zaki-Dizaji, H.; Shahriari, M.; Etaati, G. R.

doi:10.1016/j.radmeas.2007.09.004

Cited by 10 publications

(2 citation statements)

References 7 publications

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“…A FORTRAN program, named FTRAC, was developed to determine the specifications of recoil protons using the kinematics of interactions and the PTRAC card produces an input for SRIM code where the proton transport through the radiator is simulated obtaining the tracks registered in the CR-39 TM detector. The polyethylene was used as radiator, and the aluminium was used as degrader [112].…”

Section: Computer Simulationmentioning

confidence: 99%

SSNTD Technique in Photo-Neutron Applications

Sajó-Bohus

Vega-Carrillo²,

Virk

2015

SSP

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Passive Solid State Nuclear Track Detectors (SSNTDs) are a versatile tool for neutron studies as has been shown long ago and several good quality materials are commercially available. They are useful for charged particle detection in the linear energy transfer (LET) range above the threshold value of ~10 keV μm-1. Linacs, operating above 6 MeV up to the energy region where radiotherapy is applied usually up to ~25MeV, induce unwanted photo-neutron field; their spectra shows two components due to reaction dynamics based on evaporation and knock-on mechanisms. Neutrons produced by Linacs are often neglected in health application; however, today it has become necessary to assess the effect on patient, staff and radiation workers. Radiation studies using SSNTDs play a major role in this case. Other fields also take advantage of the passive detectors properties; in fact they are employed with success to measure neutron signals relevant for plasma diagnostics as it was demonstrated at the RFX facility as part of the ITER project. The PADC-NTD techniques provide information on external neutron field values around the RFX-installation during pulsed operation. In any case, converter materials, as charged particles from (n, p) and (n, α) reactions, are required to produce neutron fingerprints through latent tracks. These once etched provide information on neutron fluence spatial values. Track histograms are then employed to determine photo-neutron induced damage in materials as well as radiation dose to both patient and professionally exposed workers. The estimated neutron fluence that can be determined by NTM covers a large range of values, the largest being above 1010(± 12%) neutrons/cm2.

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Section: Computer Simulationmentioning

confidence: 99%

SSNTD Technique in Photo-Neutron Applications

Sajó-Bohus

Vega-Carrillo²,

Virk

2015

SSP

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“…In passive personal dosimeters, detectors that can maintain data for a long time must be used. Solid state nuclear track detectors (SSNTDs) and thermoluminescence detectors (TLDs) are most commonly applied as film badges in passive dosimeters [1][2][3].…”

Section: Jinst 9 P06023mentioning

confidence: 99%

Detection and dosimetry studies on the response of silicon diodes to an²⁴¹Am-Be source

Lotfi¹,

Dizaji²,

Davani³

2014

J. Inst.

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Silicon diode detectors show potential for the development of an active personal dosimeter for neutron and photon radiation. Photons interact with the constituents of the diode detector and produce electrons. Fast neutrons interact with the constituents of the diode detector and converter, producing recoil nuclei and causing (n,α) and (n,p) reactions. These photonand neutron-induced charged particles contribute to the response of diode detectors. In this work, a silicon pin diode was used as a detector to produce pulses created by photon and neutron. A polyethylene fast neutron converter was used as a recoil proton source in front of the detector. The total registered photon and neutron efficiency and the partial contributions of the efficiency, due to interactions with the diode and converter, were calculated. The results show that the efficiency of the converter-diode is a function of the incident photon and neutron energy. The optimized thicknesses of the converter for neutron detection and neutron dosimetry were found to be 1 mm and 0.1 mm respectively. The neutron records caused by the (n,α) and (n,p) reactions were negligible. The photon records were strongly dependent upon the energy and the depletion layer of the diode. The photons and neutrons efficiency of the diode-based dosimeter was calculated by the MCNPX code, and the results were in good agreement with experimental results for photons and neutrons from an 241 Am-Be source.

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Study of a radiator degrader CR39 based neutron spectrometer

Caresana¹,

Ferrarini²,

Pola³

et al. 2010

Nuclear Instruments and Methods in Physics Research Section A:

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Monte Carlo calculation of CR-39 efficiency for fast neutron detection using a combination of MCNP and SRIM codes, and comparison with experimental results

Cited by 10 publications

References 7 publications

SSNTD Technique in Photo-Neutron Applications

SSNTD Technique in Photo-Neutron Applications

Detection and dosimetry studies on the response of silicon diodes to an²⁴¹Am-Be source

Study of a radiator degrader CR39 based neutron spectrometer

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Monte Carlo calculation of CR-39 efficiency for fast neutron detection using a combination of MCNP and SRIM codes, and comparison with experimental results

Cited by 10 publications

References 7 publications

SSNTD Technique in Photo-Neutron Applications

SSNTD Technique in Photo-Neutron Applications

Detection and dosimetry studies on the response of silicon diodes to an241Am-Be source

Study of a radiator degrader CR39 based neutron spectrometer

Contact Info

Product

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Detection and dosimetry studies on the response of silicon diodes to an²⁴¹Am-Be source