Dosimetry Chain for the Dogs Irradiated in the Epithermal Neutron Beam at the Finnish BNCT Facility

Savolainen, Sauli; Auterinen, Iiro; Aschan, Carita; Hiismäki, Pekka; Kortesniemi, Mika; Kosunen, A; Kotiluoto, Petri; Lampinen, Juha; Seppälä, Tiina; Serén, Tom; Tanner, Vesa; Toivonen, M

doi:10.1007/978-1-4615-1285-1_189

Cited by 5 publications

(4 citation statements)

References 17 publications

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“…14 As a final test of the beam and the facility prior to patient irradiations a healthy tissue tolerance study has been performed. 16 Patient fixation system is under development.…”

Section: Discussionmentioning

confidence: 99%

Metamorphosis of a 35 Year-Old TRIGA Reactor into a Modern BNCT Facility

Auterinen

Hiismäki

Kotiluoto

et al. 2001

Frontiers in Neutron Capture Therapy

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“…14 As a final test of the beam and the facility prior to patient irradiations a healthy tissue tolerance study has been performed. 16 Patient fixation system is under development.…”

Section: Discussionmentioning

confidence: 99%

Metamorphosis of a 35 Year-Old TRIGA Reactor into a Modern BNCT Facility

Auterinen

Hiismäki

Kotiluoto

et al. 2001

Frontiers in Neutron Capture Therapy

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“…The Finnish BNCT facility can provide horizontal epithermal neutron beams originating from 8, 11, 14, 17, or 20 cm diameter circular apertures. The aperture sizes can be changed using removable 2.5 cm thick 6 Li-plastic plates. The ''free beam'' neutron spectrum was calculated at the beam entry using a DORT code 22 model of the beam.…”

Section: A Neutron Beam and Head Modelingmentioning

confidence: 99%

“…The weighted dose D W is a sum of physical ͑absorbed͒ dose components (D i ) multiplied by weighting factors (w i ) for each dose component, for a specified effect in a tissue. 5,6 This allows the effect of a given dose from an epithermal neutron beam to be equated with an equivalent dose of conventional photon irradiation, but knowledge of the total physical dose components and the respective weighting factors is also required. Some of these weighting factors, such as that for the nitrogen capture dose, will be independent of the epithermal neutron source, whereas others will not.…”

Section: Introductionmentioning

confidence: 99%

Dose planning with comparison to in vivo dosimetry for epithermal neutron irradiation of the dog brain

et al. 2002

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Boron neutron capture therapy (BNCT) is an experimental type of radiotherapy, presently being used to treat glioblastoma and melanoma. To improve patient safety and to determine the radiobiological characteristics of the epithermal neutron beam of Finnish BNCT facility (FiR 1) dose-response studies were carried on the brain of dogs before starting the clinical trials. A dose planning procedure was developed and uncertainties of the epithermal neutron-induced doses were estimated. The accuracy of the method of computing physical doses was assessed by comparing with in vivo dosimetry. Individual radiation dose plans were computed using magnetic resonance images of the heads of 15 Beagle dogs and the computational model of the FiR 1 epithermal neutron beam. For in vivo dosimetry, the thermal neutron fluences were measured using Mn activation foils and the gamma-ray doses with MCP-7s type thermoluminescent detectors placed both on the skin surface of the head and in the oral cavity. The degree of uncertainty of the reference doses at the thermal neutron maximum was estimated using a dose-planning program. The estimated uncertainty (+/-1 standard deviation) in the total physical reference dose was +/-8.9%. The calculated and the measured dose values agreed within the uncertainties at the point of beam entry. The conclusion is that the dose delivery to the tissue can be verified in a practical and reliable fashion by placing an activation dosimeter and a TL detector at the beam entry point on the skin surface with homogeneous tissues below. However, the point doses cannot be calculated correctly in the inhomogeneous area near air cavities of the head model with this type of dose-planning program. This calls for attention in dose planning in human clinical trials in the corresponding areas.

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“…[2][3][4] In practice the total dose in BNCT consists of several different dose components. [5][6][7][8][9][10] For instance, in the boron neutron capture reaction gamma radiation with 478 keV energy is also released. Also hydrogen and nitrogen, that are natural compounds both in soft and brain tissue, capture neutrons-hydrogen with 2.2 MeV gamma radiation release and nitrogen with 0.6 MeV proton release.…”

Section: Introductionmentioning

confidence: 99%

Application of the new MultiTrans radiation transport code in BNCT dose planning

Kotiluoto¹,

Hiismäki²,

Savolainen³

2001

Medical Physics

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Dose planning in boron neutron capture therapy (BNCT) is a complex problem and requires sophisticated numerical methods. In the framework of the Finnish BNCT project, new deterministic three-dimensional radiation transport code MultiTrans SP3 has been developed at VTT Chemical Technology, based on a novel application of the tree multigrid technique. To test the applicability of this new code in a realistic BNCT dose planning problem, cylindrical PMMA (polymethyl-methacrylate) phantom was chosen as a benchmark case. It is a convenient benchmark, as it has been modeled by several different codes, including well-known DORT and MCNP. Extensive measured data also exist. In this paper, a comparison of the new MultiTrans SP3 code with other methods is presented for the PMMA phantom case. Results show that the total neutron dose rate to ICRU adult brain calculated by the MultiTrans SP3 code differs less than 4% in 2 cm depth in phantom (in thermal maximum) from the DORT calculation. Results also show that the calculated 197Au(n,gamma) and 55Mn(n,gamma) reaction rates in 2 cm depth in phantom differ less than 4% and 1% from the measured values, respectively. However, the photon dose calculated by the MultiTrans SP3 code seems to be incorrect in this PMMA phantom case, which requires further studying. As expected, the deterministic MultiTrans SP3 code is over an order of magnitude faster than stochastic Monte Carlo codes (with similar resolution), thus providing a very efficient tool for BNCT dose planning.

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Dosimetry Chain for the Dogs Irradiated in the Epithermal Neutron Beam at the Finnish BNCT Facility

Cited by 5 publications

References 17 publications

Metamorphosis of a 35 Year-Old TRIGA Reactor into a Modern BNCT Facility

Metamorphosis of a 35 Year-Old TRIGA Reactor into a Modern BNCT Facility

Dose planning with comparison to in vivo dosimetry for epithermal neutron irradiation of the dog brain

Application of the new MultiTrans radiation transport code in BNCT dose planning

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