The filter/moderator arrangement-optimisation for the boron-neutron capture therapy (BNCT).
The paper presents results of the numerical modelling of the fission-converter-based epithermal neutron source designed for the boron neutron capture therapy (BNCT) facility to be located at the Polish research nuclear reactor MARIA at Swierk. The unique design of the fission converter has been proposed due to a specific geometrical surrounding of the reactor. The filter/moderator arrangement has been optimised to moderate fission neutrons to epithermal energies and to remove both fast neutrons and photons from the therapeutic beam. The selected filter/moderator set-up ensures both high epithermal neutron flux and suitably low level of beam contamination. Photons originating from the reactor core are almost eliminated what is the exceptional advantage of the proposed design. It yields one order of magnitude lower gamma radiation dose than the maximum allowed dose in such a type of therapeutic facility. The MCNP code has been used for the computations.
Tracz
G
G
The Henryk Niewodniczański Institute of Nuclear Physics of the Polish Academy of Sciences, ul. Radzikowskiego 152, 31-342 Kraków, Poland. Grezegorz.Tracz@ifj.edu.pl
Dabkowski
L
L
Dworak
D
D
Pytel
K
K
Woźnicka
U
U
D000465:Algorithms; D016754:Boron Neutron Capture Therapy / Q000295:instrumentation* / Q000379:methods*; D003198:Computer Simulation; D017076:Computer-Aided Design; D004867:Equipment Design / Q000379:methods; D019544:Equipment Failure Analysis / Q000379:methods*; D006801:Humans; D018499:Linear Energy Transfer; D008962:Models, Theoretical; D009502:Neutrons / Q000627:therapeutic use*; D011786:Quality Control; D011874:Radiometry / Q000379:methods*; D011879:Radiotherapy Dosage; D012062:Relative Biological Effectiveness; D015203:Reproducibility of Results; D018570:Risk Assessment / Q000379:methods; D012307:Risk Factors; D012542:Scattering, Radiation; D012680:Sensitivity and Specificity