Jove
Visualize
Contact Us
JoVE
x logofacebook logolinkedin logoyoutube logo
ABOUT JoVE
OverviewLeadershipBlogJoVE Help Center
AUTHORS
Publishing ProcessEditorial BoardScope & PoliciesPeer ReviewFAQSubmit
LIBRARIANS
TestimonialsSubscriptionsAccessResourcesLibrary Advisory BoardFAQ
RESEARCH
JoVE JournalMethods CollectionsJoVE Encyclopedia of ExperimentsArchive
EDUCATION
JoVE CoreJoVE BusinessJoVE Science EducationJoVE Lab ManualFaculty Resource CenterFaculty Site
Terms & Conditions of Use
Privacy Policy
Policies

Related Experiment Videos

Neutron dose rate evaluation for medical linear accelerators.

A Facure1, R C Falcão, A X Da Silva

  • 1Comissão Nacional de Energia Nuclear, R. Gal. Severiano 90, sala 416, 22294-900 Rio de Janeiro-RJ, Brazil. afsoares@cnen.gov.br

Radiation Protection Dosimetry
|September 16, 2004
PubMed
Summary

High-energy medical accelerators generate photoneutrons, posing radiation risks. This study simulates neutron doses in radiotherapy rooms, crucial for patient safety and shielding design in Brazil.

Related Concept Videos

You might also read

Related Articles

Articles linked to this work by shared authors, journal, and citation graph.

Sort by
Same author

COMPARISON OF THE NEUTRON ENERGY RESPONSE OF TWO DIFFERENT TLD ALBEDO DOSEMETERS.

Radiation protection dosimetry·2017
Same author

Comparison of the effective dose rate to aircrew members using hybrid computational phantoms in standing and sitting postures.

Journal of radiological protection : official journal of the Society for Radiological Protection·2016
Same author

MCNP SIMULATION OF THE HP(10) ENERGY RESPONSE OF A BRAZILIAN TLD ALBEDO NEUTRON INDIVIDUAL DOSEMETER, FROM THERMAL TO 20 MeV.

Radiation protection dosimetry·2015
Same author

A dosimetric study of prostate brachytherapy using Monte Carlo simulations with a voxel phantom, measurements and a comparison with a treatment planning procedure.

Radiation protection dosimetry·2015
Same author

New filter for iodine applied in nuclear medicine services.

Applied radiation and isotopes : including data, instrumentation and methods for use in agriculture, industry and medicine·2013
Same author

Application of digital image processing for the generation of voxels phantoms for Monte Carlo simulation.

Applied radiation and isotopes : including data, instrumentation and methods for use in agriculture, industry and medicine·2011

Area of Science:

  • Medical Physics
  • Radiation Oncology
  • Nuclear Engineering

Background:

  • Medical accelerators operating above the (X,n) reaction threshold produce photoneutron radiation.
  • Current Brazilian regulations lack neutron dose measurements for radiotherapy room licensing.
  • Accurate dose assessment is vital for patient/staff safety and effective shielding design.

Purpose of the Study:

  • To simulate photoneutron dose rates in radiotherapy rooms using MCNP.
  • To validate simulation results against manufacturer data for high-energy linear accelerators.
  • To provide essential data for radiation safety and shielding in Brazilian radiotherapy facilities.

Main Methods:

  • Utilized Monte Carlo N-Particle (MCNP) code for simulating dosimetric quantities.

Related Experiment Videos

  • Focused simulations on the isocenter of various high-energy linear accelerator models.
  • Compared simulated dose rates with data provided by equipment manufacturers.
  • Main Results:

    • MCNP simulations successfully modeled photoneutron dose rates at the isocenter.
    • Simulated results showed good agreement with manufacturer-provided values.
    • This validates the simulation approach for assessing neutron radiation in treatment rooms.

    Conclusions:

    • MCNP simulations are a reliable method for estimating photoneutron doses in radiotherapy.
    • The findings support the need for implementing neutron dose assessments in Brazil.
    • Accurate dose data will enhance patient safety and optimize radiation shielding for treatment rooms.