Monte Carlo dose calculation in radiation therapy for different modelling of electron and photon transport
Creators
- 1. VINCA Institute of Nuclear Sciences, Belgrade (Yugoslavia)
- 2. Military Medical Academy, Belgrade (Yugoslavia)
Description
The goal of any Monte Carlo Dose Calculation is to deliver the result that is both accurate and sufficiently fast for routine radiotherapy treatment on a patient. Radiotherapy planning require compositions of the relevant accelerator components. In this work, we examined different manners for modelling of nuclear particles transport through material domains of accelerator configuration that are based on two numerical algorithm. First algorithm (marked as full-physics in MC simulation) describes all interactions incident photons or electrons and produced secondary electrons in all components, while second algorithm (marked as reduced-physics in MC simulation) decreases number of interactions when is estimated that is unacceptable nuclear particle free path in relate to distance from boundary of some noticed component in random chosen direction. In the case of reduced-physics, the CPU time is also decreased and saved is the accurate level of dose calculation in relate to full-physics nuclear particle tracking through identical geometry configuration and material domains. Examination of different modelling are carried out by Monte Carlo code FOTELP (RSIC Code package CCC-581). Software package FOTELP was developed to simulate the transport of photons, electrons and positrons by Monte Carlo method for numerical experiments in dosimetry, radiotherapy and nuclear medicine. This code is suitable for computing the absorbed energy in the layers of tissue and other significant material, for estimating radiation damage of materials, and other numerical experiments concerning the mentioned nuclear particles. Codes from this package perform calculations in 3D geometry with random spectra of nuclear particles having energy in the range from 1 keV to 100 MeV, and material region for which geometry can be described by planes and surfaces of second order. Last version of this code has a possibility that made nuclear particle transport simulation with both the full-physics and reduced-physics. On the base results of this MC simulations concluded is for which processes must be apply the modelling with reduced-physics at 3D radiotherapy planning. (author)
Additional details
Publishing Information
- Publisher
- Institute of Nuclear Sciences VINCA
- Imprint Place
- Belgrade (Yugoslavia)
- ISBN
- 86-7306-049-4
- Imprint Title
- Proceedings; Yugoslav Nuclear Society; Institute of Nuclear Sciences VINCA
- Imprint Pagination
- 807 p.
- Journal Page Range
- p. 686-690
Conference
- Title
- 3. International Yugoslav Nuclear Society Conference (YUNSC-2000)
- Dates
- 2-5 Oct 2000
- Place
- Belgrade (Yugoslavia)
INIS
- Country of Publication
- Yugoslavia
- Country of Input or Organization
- Yugoslavia
- INIS RN
- 33044930
- Subject category
- S99: GENERAL AND MISCELLANEOUS; S62: RADIOLOGY AND NUCLEAR MEDICINE;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- ALGORITHMS; COMPUTERIZED SIMULATION; CONCENTRATION RATIO; ELECTRON BEAMS; ELECTRON TRANSFER; ENERGY ABSORPTION; ENERGY LOSSES; EVALUATED DATA; EXPERIMENTAL DATA; F CODES; KEV RANGE 01-10; KEV RANGE 10-100; KEV RANGE 100-1000; LINEAR ACCELERATORS; MEV RANGE 01-10; MEV RANGE 10-100; MONTE CARLO METHOD; P CODES; PARTICLE TRACKS; PHOTON TRANSPORT; PLANNING; RADIATION DOSES; RADIOTHERAPY; THREE-DIMENSIONAL CALCULATIONS; TISSUE-EQUIVALENT MATERIALS
- Descriptors DEC
- ABSORPTION; ACCELERATORS; BEAMS; CALCULATION METHODS; COMPUTER CODES; DATA; DOSES; ENERGY RANGE; INFORMATION; KEV RANGE; LEPTON BEAMS; LOSSES; MATERIALS; MATHEMATICAL LOGIC; MEDICINE; MEV RANGE; NEUTRAL-PARTICLE TRANSPORT; NUCLEAR MEDICINE; NUMERICAL DATA; PARTICLE BEAMS; RADIATION TRANSPORT; RADIOLOGY; SIMULATION; SORPTION; THERAPY
Optional Information
- Notes
- 18 refs., 6 figs.