Application of nuclear track detectors as sensors for photoneutrons generated by medical accelerators

Szydlowski, A.; Jaskóła, M.; Malinowska, A.; Pszona, S.; Wysocka-Rabin, A.; Korman, A.; Pytel, Krzysztof; Prokopowicz, R.; Rostkowska, J; Bulski, W.; Kuk, M.

doi:10.1016/j.radmeas.2012.06.011

Cited by 9 publications

(4 citation statements)

References 12 publications

Supporting

Mentioning

Contrasting

Unclassified

Order By: Relevance

“…El espectro de fotoneutrones en un LINAC es diferente al espectro de una fuente de 252 Cf, sin embargo, es considerado aceptable la calibración del detector tal y como lo recomienda la IAEA y la Comisión Nacional de Protección Radiológica (NCRP) [38,39]. Cabe destacar que Szydlowski y colaboradores, para un estudio en un Varian Clinac 2300 18 MV, expusieron los detectores CR-39 ante una fuente 252 Cf considerando que este procedimiento provee una calibración propia inclusive cuando el espectro en el LINAC es diferente del 252 Cf [40,41].…”

Section: Mediciones Preliminares En La Fuente 252 Cfunclassified

Dosis equivalente ambiental H*(10) por neutrones producidos en un Varian Clinac 2300 mediante detectores tipo CR-39

Barrutia²

2022

Rev. Mex. Fís.

View full text Add to dashboard Cite

Mediante detectores de trazas tipo CR-39 se determinó la dosis equivalente ambiental H*(10) por neutrones rápidos y térmicos en un acelerador Varian Clinac 2300 que opera en el rango de 6-18 MV. Mediciones preliminares fueron efectuadas ante una fuente moderada de neutrones 252Cf para obtener la respuesta del detector según el rango de energía. Se obtuvieron valores de tasa de densidad de trazas, flujo y dosis equivalente ambiental H*(10) por neutrones rápidos y térmicos en la mesa de tratamiento del recinto. Se determinó que la dosis equivalente ambiental H*(10) por unidad de dosis Gy en el isocentro (IC) es de 162 ± 11 μSv/Gy a una distancia de 13 cm del IC. Se presentan igualmente valores de flujo y tasa de densidad de trazas en el cabezal del acelerador.

show abstract

Section: Mediciones Preliminares En La Fuente 252 Cfunclassified

Dosis equivalente ambiental H*(10) por neutrones producidos en un Varian Clinac 2300 mediante detectores tipo CR-39

Barrutia²

2022

Rev. Mex. Fís.

View full text Add to dashboard Cite

show abstract

“…Detectors were calibrated with a bare 252 Cf neutron source. This procedure provides a proper calibration even when the measured spectra is different from the 252 Cf [50].…”

Section: Photo-neutron Field Detection By Cr-39 Lined With 10 B Conve...mentioning

confidence: 99%

SSNTD Technique in Photo-Neutron Applications

Sajó-Bohus

Vega-Carrillo²,

Virk

2015

SSP

View full text Add to dashboard Cite

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.

show abstract

“…[1][2][3]17 The radiation activation technique is employed to measure neutrons and high-energy photon fluence in CLINAC. 4,22,25 This technique has been widely used in nuclear reactors and gamma irradiation facilities for the characterization of the high flux of neutron and high-energy gamma photon. [5][6][7]15 It has the advantage that the detector material can be formed into any shape; they can be large or small depending on the application.…”

Section: Introductionmentioning

confidence: 99%

Neutron and high energy photon fluence estimation in CLINAC using gold activation foils

Haddad

Anjak

Yousef

2019

Reports of Practical Oncology & Radiotherapy

View full text Add to dashboard Cite

The thermal neutron, epithermal neutron and high-energy photon fluence were measured in this work around the Varian 21EX 23 MV CLINAC, which is operated in Albairouni hospital in Damascus, Syria. Background: Photoneutron measurements around medical CLINAC aim to protect both patients and staff from unwanted radiation. Materials and methods: Neutron and photon activation techniques were applied using gold foils. Results: It was found that high-energy photons fluence has practically a constant value in the field size. The thermal and epithermal neutron fluence along ox and oy axes has the same order of magnitude. Conclusion: Gold foils have been used successfully to measure neutron flux and high-energy photons simultaneously using activation techniques.

show abstract

Application of nuclear track detectors as sensors for photoneutrons generated by medical accelerators

Cited by 9 publications

References 12 publications

Dosis equivalente ambiental H*(10) por neutrones producidos en un Varian Clinac 2300 mediante detectores tipo CR-39

Dosis equivalente ambiental H*(10) por neutrones producidos en un Varian Clinac 2300 mediante detectores tipo CR-39

SSNTD Technique in Photo-Neutron Applications

Neutron and high energy photon fluence estimation in CLINAC using gold activation foils

Contact Info

Product

Resources

About