“CARONTE”, A Treatment Planning System Based on Real Macroscopic Boron Distribution and MCNP-4A Code

Cerullo, N.; Daquino, G.G.

doi:10.1007/978-1-4615-1285-1_29

Cited by 5 publications

(5 citation statements)

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“…23 An extensive comparison between SERA and MCNP, 24 which is the ''transport engine'' used in MacNCTPlan, was recently completed for boron neutron capture synovectomy. 25 Other NCT treatment planning systems are being developed in Australia, 26 Italy, 27 and Japan, 28 but to date have not been described in the scientific literature or applied clinically.…”

Section: Introductionmentioning

confidence: 99%

Reference dosimetry calculations for neutron capture therapy with comparison of analytical and voxel models

2002

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As clinical trials of Neutron Capture Therapy (NCT) are initiated in the U.S. and other countries, new treatment planning codes are being developed to calculate detailed dose distributions in patient-specific models. The thorough evaluation and comparison of treatment planning codes is a critical step toward the eventual standardization of dosimetry, which, in turn, is an essential element for the rational comparison of clinical results from different institutions. In this paper we report development of a reference suite of computational test problems for NCT dosimetry and discuss common issues encountered in these calculations to facilitate quantitative evaluations and comparisons of NCT treatment planning codes. Specifically, detailed depth-kerma rate curves were calculated using the Monte Carlo radiation transport code MCNP4B for four different representations of the modified Snyder head phantom, an analytic, multishell, ellipsoidal model, and voxel representations of this model with cubic voxel sizes of 16, 8, and 4 mm. Monoenergetic and monodirectional beams of 0.0253 eV, 1, 2, 10, 100, and 1000 keV neutrons, and 0.2, 0.5, 1, 2, 5, and 10 MeV photons were individually simulated to calculate kerma rates to a statistical uncertainty of <1% (1 std. dev.) in the center of the head model. In addition, a "generic" epithermal neutron beam with a broad neutron spectrum, similar to epithermal beams currently used or proposed for NCT clinical trials, was computed for all models. The thermal neutron, fast neutron, and photon kerma rates calculated with the 4 and 8 mm voxel models were within 2% and 4%, respectively, of those calculated for the analytical model. The 16 mm voxel model produced unacceptably large discrepancies for all dose components. The effects from different kerma data sets and tissue compositions were evaluated. Updating the kerma data from ICRU 46 to ICRU 63 data produced less than 2% difference in kerma rate profiles. The depth-dose profile data, Monte Carlo code input, kerma factors, and model construction files are available electronically to aid in verifying new and existing NCT treatment planning codes.

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Section: Introductionmentioning

confidence: 99%

Reference dosimetry calculations for neutron capture therapy with comparison of analytical and voxel models

2002

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“…Boron dose is from 10 B(n,α) 7 Li reaction. Neutron dose is major from 1 H(n,n)p and 14 N(n,p) 14 C reactions. Photon dose comes from beam port and 1 H(n,γ) 2 H, 16 O(n,γ) 17 O, and 12 C(n,γ) 13 C reactions.…”

Section: Monte Carlo Dose Engine In Neumantamentioning

confidence: 99%

“…Tsukuba Plan [10,11] developed by a team including researchers from the University of Tsukuba, is another MC-based TPS [12] utilized PHITS [13] as MC engine. An original prototype software CARONTE [14] and BDTPS are both PET-based TPS, featured a pre-processed module for processing PET images for in vivo boron distribution [15]. NeuCure [16] is a TPS designed especially for BNCT, which developed by Sumitomo Heavy Industries, must be used in combination with another radiotherapy treatment planning product RayStation for image processing.…”

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confidence: 99%

Development of Monte Carlo based treatment planning system for BNCT

Jiang

Teng

Zhong

et al. 2022

J. Phys.: Conf. Ser.

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A treatment planning system (TPS) plays a major role for a successful radiotherapy, directly influencing the calculated dose accuracy, and thus the treatment quality. Multifunctional Arithmetic for Neutron Transportation Analysis (NeuMANTA), a TPS especially designed for complete workflow for BNCT, which aims to provide high precision dose calculation with maximizing the efficacy. The dedicated MC engine COMPASS seamlessly embedded in NeuMANTA can be called for dose distribution calculation in background. Optimized cross-section library, parallel computing, and various variance reduction techniques are applied to speed up the particle transportations. A benchmark was performed between NeuMANTA and MCNP6, and results agreed well with no significant statistical difference, however, NeuMANTA needs only half of the calculation time. The accuracy of estimated doses, and complete treatment workflow are the main features in NeuMANTA.

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“…Our idea was to link the PET information, related to the in vivo boron distribution, to the 3-D modeling for the Monte Carlo simulation. This idea led to the development of the original prototype software CARONTE [2].…”

Section: A the Caronte Systemmentioning

confidence: 99%

An overview on the developments and improvements of a treatment planning system for BNCT

Cerullo

Daquino

Muzi³

2006

IEEE Trans. Nucl. Sci.

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Boron Neutron Capture Therapy (BNCT) is a radiation therapy for cancer that employs a neutron beam and a 10 B-loaded drug to selectively kill tumor cells whilst sparing surrounding healthy tissues (HT). In conventional radiation therapy, treatment planning systems (TPSs) implementing simplified models of radiation transport and dose deposition allow to efficiently optimize all the relevant parameters prior to the patient's irradiation. This simplified approach is not feasible in BNCT, because the presence of neutrons requires the use of more complex radiation transport models. For this reason, current BNCT TPSs routinely perform several radiation transport simulations based on the Monte Carlo method.Our team has been involved in BNCT TPS research since 1996, introducing the original trait of employing in the simulation a three-dimensional map of the highly heterogeneous boron distribution in tissues, obtained through PET scanning of the target region. This approach differs markedly from the standard one, in which boron concentration is assumed to be uniform in each "macro region" within the patient's head, and its value is estimated on the basis of blood sampling. The first result of this research was the prototype software CARONTE, employed to test the feasibility of the new approach and to carry out a comparative study by applying the two different approaches to the same test case. The results, presented in this paper in terms of the computed physical dose rate due to the 10 B reaction, show how the different assumptions made in the two approaches can significantly influence important TP parameters. This led to the development of Boron Distribution TP Software (BDTPS), an original and complete TPS. The different phases of the experimental validation of BDTPS, which included the design and construction of an ad hoc phantom able to host a number of vials loaded with 10 B solutions, is presented here. The phantom, which subsequently underwent computed tomography (CT) and positron emission tomography (PET) scanning, was irradiated in the High Flux Reactor (HFR) at JRC, Petten, The Netherlands.Index Terms-Boron neutron capture therapy, dosimetry, image processing, Monte Carlo methods, positron emission tomography, treatment planning system.

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“CARONTE”, A Treatment Planning System Based on Real Macroscopic Boron Distribution and MCNP-4A Code

Cited by 5 publications

References 2 publications

Reference dosimetry calculations for neutron capture therapy with comparison of analytical and voxel models

Reference dosimetry calculations for neutron capture therapy with comparison of analytical and voxel models

Development of Monte Carlo based treatment planning system for BNCT

An overview on the developments and improvements of a treatment planning system for BNCT

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