Neutron dosimetry and shielding verification in commissioning of Compact Proton Therapy Centers (CPTC) using MCNP6.2 Monte Carlo code

García-Fernández, Gonzalo F.; Gallego, Eduardo; Gómez-Ros, J.M.; Vega‐Carrillo, Héctor René; García-Baonza, Roberto; Cevallos-Robalino, Lenin E.; Guzmán-García, Karen Arlete

doi:10.1016/j.apradiso.2020.109279

Cited by 13 publications

(5 citation statements)

References 24 publications

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“…By contrast, when a neutron passed a material with a low hydrogen fraction, Σ 𝑅 = 2 3 ⁄ Σ 𝑡 for the energy of 6-8 MeV [39][40][41]. The macroscopic removal cross-section of a compound material comprising numerous elements is identified via summation of all components [38,41]: (4) where (Σ 𝑅 𝜌 ⁄ ) 𝑖 is the mass removal cross-section from the i-th element (cm 2 /g), in which the atomic weight function 𝑊 𝑖 is partial density (g/cm 3 ) or density of component i in the compound, and 𝜌 is material or compound density (g/cm 3 ).…”

Section: Removal Cross-section For Fast Neutronmentioning

confidence: 99%

“…Secondary neutrons can be produced by interacting protons or heavy ion particles with target materials in accelerators. In addition to neutrons, the interaction of protons and heavy ions produces photons [1][2][3][4][5][6]. The utilization of heavy ions and protons in the health sector, such as cancer therapy, has rapidly progressed and continuously exponentially grown in the last decade.…”

Section: Introductionmentioning

confidence: 99%

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Combined Method of Bulk Material Shielding Evaluation for 200 Mev High Energy Neutron Source Using Phits Modelling and Partial Density

Aliyah

Rahman

Radzi

et al. 2023

SPEKTRA

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Neutron encounters difficulties in shielding protection. Thus, many researchers have performed simulation and experimental research on neutron shielding materials. The characteristic of materials is highly dependent on neutron energy. The evaluation of neutron shielding for various materials, such as iron, concrete, aluminum, and borated polyethylene (BPE), was conducted in this paper through simulation using a Monte Carlo code of PHITS 3.27 and calculation via partial density method. A mono-energetic neutron source with an energy of 200 MeV is emitted perpendicular to the shielding material with a thickness of 105 cm. The parameters measured in this analysis include flux, fast neutron removal cross-section, neutron depth dose, ambient dose H*(10) equivalent, and neutron dose reduction factor (RF). Results show that iron is a good material against high-energy neutron and secondary photon radiation at the energy range with the highest removal cross-section and the lowest RF value (0.39), followed by concrete, BPE, and aluminum. The integrated fluence and effective dose profiles were consistent with previous results in the literature. Benchmarking calculation of neutron dose RF was conducted with other publications and was in good agreement within the value range.

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Section: Removal Cross-section For Fast Neutronmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Combined Method of Bulk Material Shielding Evaluation for 200 Mev High Energy Neutron Source Using Phits Modelling and Partial Density

Aliyah

Rahman

Radzi

et al. 2023

SPEKTRA

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“…The Monte Carlo method has the advantage of producing highly reliable results, but it has the disadvantage of requiring a significant amount of resources for calculations [24][25][26]. Measurement 4 methods can provide intuitive results, but there is a possibility of measurement errors due to exposure time or errors in measurement equipment [15].…”

Section: Introductionmentioning

confidence: 99%

Development of O-ring Type Radiation Treatment Equipment Shielding Evaluation and Management Program

Choi

Ahn

Kim

et al. 2023

Preprint

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The objective of this study is to evaluate the effectiveness of O-ring type linear accelerator shielding using a developed program (O-ring Type Radiation therapy Equipment Shielding Evaluation, ORSE) that automatically evaluates Digital Imaging and Communications in Medicine Radiation Therapy (DICOM RT) plan files and applies them to determine the adequacy of the shielding. The shielding evaluation was conducted for a total of four treatment rooms including Magnetic Resonance Linear Accelerator (MR-LINAC), Halcyon, Tomotherapy. The analysis was performed using the program that analyzed DICOM RT plan files of patients who received treatment for five days. The program obtained the IMRT factor, which considered the Monitor Unit (MU), and the use factor, which considered the gantry angle. Based on the National Council on Radiation Protection & Measurements (NCRP)-151 report, shielding calculations were performed to determine the transmitted dose for each location behind the barrier, and the maximum number of treatable patients and the shield wall thickness were calculated based on patient data. To compare the results with the program, doses were measured over five days using a glass dosimeter for photon detection. The IMRT factors and Use factors obtained from patient data showed differences of up to 65.0% and 33.8%, respectively, compared to NCRP-151. Shielding evaluation conducted in each treatment room showed that the transmitted dose at every location was below 1% of the dose limit. The program results and detector results showed a maximum error of 0.003 mSv/week in transmitted dose. The ORSE program allows for the shielding evaluation results to the clinical environment of each institution based on patient data for the desired analysis period through straightforward manipulation.

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“…Craniopharyngiomas are rare in cases of intracranial tumors, only about 7.8% in pediatric tumors and (1-4)% in adult tumors. These tumors usually attack children at the age of (5)(6)(7)(8)(9)(10)(11)(12)(13)(14) years and adults at the age of (50-70) years [1]. These tumors are located in the prasella region adjacent to the frontal lobe, temporal lobe, cranial fossa and brain stem.…”

Section: Introductionmentioning

confidence: 99%

“…1. In X-ray radiotherapy, radiation dose is distributed very high at baseline and decreases with increasing depth, whereas in proton therapy, the proton dose is distributed only at a certain depth [5].…”

Section: Introductionmentioning

confidence: 99%

Optimization of Energy for Proton Therapy with Pencil Beam Collimator Model in Craniopharyngioma Tumor Using MCNP6 Code

Putri,

Riyatun,

Darmanto

et al. 2023

J. Phys. Appl.

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Computational simulations of proton therapy with a pencil beam collimator for craniopharyngioma have been done using MCNP6. A pencil beam was radiated towards cube shaped tumor cells in size 1.2 cm, located at a 5.4 cm depth from the surface of the scalp. A 0.1 cm pencil beam was radiated from the left 19.6 cm from the scalp. The cube of tumor cell is divided into the front layer, middle layer, and back layer. Each layer of the tumor cell is divided into 9 cubicles, thus there are 27 cubicles. Using various energy from 108 MeV to 115 MeV and various intensity of energy for each irradiation, it produces the dose for each cubicle in unit MeV/gram per proton. The best isodoses occurred in 5 variations of energy which is 108.2; 111.2; 113.4; 114.7 and 115 MeV. The healthy organ that received the largest dose of the proton is the brain, it is (7.38±0.01)×10-2 MeV/gram per proton, or only 0.412% compared to the tumor cell dose.

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Neutron dosimetry and shielding verification in commissioning of Compact Proton Therapy Centers (CPTC) using MCNP6.2 Monte Carlo code

Cited by 13 publications

References 24 publications

Combined Method of Bulk Material Shielding Evaluation for 200 Mev High Energy Neutron Source Using Phits Modelling and Partial Density

Combined Method of Bulk Material Shielding Evaluation for 200 Mev High Energy Neutron Source Using Phits Modelling and Partial Density

Development of O-ring Type Radiation Treatment Equipment Shielding Evaluation and Management Program

Optimization of Energy for Proton Therapy with Pencil Beam Collimator Model in Craniopharyngioma Tumor Using MCNP6 Code

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