By Topic

Prospect of Using The Photoneutron Beam Component from High Energy linacs in BNCT, A Monte Carlo Simulation

Sign In

Cookies must be enabled to login.After enabling cookies , please use refresh or reload or ctrl+f5 on the browser for the login options.

Formats Non-Member Member
$31 $13
Learn how you can qualify for the best price for this item!
Become an IEEE Member or Subscribe to
IEEE Xplore for exclusive pricing!
close button

puzzle piece

IEEE membership options for an individual and IEEE Xplore subscriptions for an organization offer the most affordable access to essential journal articles, conference papers, standards, eBooks, and eLearning courses.

Learn more about:

IEEE membership

IEEE Xplore subscriptions

4 Author(s)
Alfuraih, A. ; Dept. of Phys., Surrey Univ., Guildford ; Alghamdi, A.A. ; Ma, A. ; Spyrou, N.M.

One drawback in widely using neutron capture therapy (NCT) is the limited number of appropriate neutron source facilities. At present neutron sources for clinical NCT are mainly research reactors. However most reactors are not in close proximity to hospitals and their use for clinical trials can be difficult. Other suggested sources include dedicated single-purpose reactors, accelerator-based neutron sources and 252Cf isotopic sources. This study examines the potential of using the photoneutrons produced from medical linacs, which are embedded in hospital environments for radiotherapy, as a source for NCT. Preliminary simulation using MCNPX simulation were conducted to calculate the photoneutron flux of a medical linac head with the aim of maximizing the thermal and epithermal neutron component whilst minimizing the photon contribution from the primary beam. Further simulations were conducted to determine the most feasible conditioning methods. Target desirable minimum neutron beam fluence rate should be 10 9 cm-2 s-1 according to IAEA guidelines. Although beams of 5 times 108 cm-2 s -1 are useable, they result in rather long irradiation times as current experience show. In existing facilities the range of dose from epithermal neutrons is from 2.5 to 13 times 10-13 Gy cm2 per neutron. A target value should be 2 times 10-13 Gy cm2 per epithermal neutron. The goal of this work was to produce neutrons that meet these treatment conditions

Published in:

Computer as a Tool, 2005. EUROCON 2005.The International Conference on  (Volume:2 )

Date of Conference:

21-24 Nov. 2005