Neutron capture therapy with <sup>235</sup>U seeds

Liu, Hungyuan B.; Brugger, R.M.; Shih, Jing‐Luen A.

doi:10.1118/1.596814

Cited by 6 publications

(2 citation statements)

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“…Various groups have used MCNP in medium energy ( 192 Ir) brachytherapy dosimetry 51 – 54 as well as in intravascular brachytherapy applications 55 57 And while significantly different from the present work, several groups have used MCNP to assist with dosimetric calculations for neutron‐emitting brachytherapy sources 58 59 …”

Section: Discussionmentioning

confidence: 87%

Dosimetric parameters of three new solid core I‐125 brachytherapy sources

Solberg

DeMarco

Hugo

et al. 2002

J Applied Clin Med Phys

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Monte Carlo calculations and TLD measurements have been performed for the purpose of characterizing dosimetric properties of new commercially available brachytherapy sources. All sources tested consisted of a solid core, upon which a thin layer of normalI125 has been adsorbed, encased within a titanium housing. The PharmaSeed BT‐125 source manufactured by Syncor is available in silver or palladium core configurations while the ADVANTAGE source from IsoAid has silver only. Dosimetric properties, including the dose rate constant, radial dose function, and anisotropy characteristics were determined according to the TG‐43 protocol. Additionally, the geometry function was calculated exactly using Monte Carlo and compared with both the point and line source approximations. The 1999 NIST standard was followed in determining air kerma strength. Dose rate constants were calculated to be 0.955±0.005,0.967±0.005, and 0.962±0.005 cGynormalh−1normalU−1 for the PharmaSeed BT‐125‐1, BT‐125‐2, and ADVANTAGE sources, respectively. TLD measurements were in excellent agreement with Monte Carlo calculations. Radial dose function, g(r), calculated to a distance of 10 cm, and anisotropy function F(r, θ), calculated for radii from 0.5 to 7.0 cm, were similar among all source configurations. Anisotropy constants, trueϕ¯an, were calculated to be 0.941, 0.944, and 0.960 for the three sources, respectively. All dosimetric parameters were found to be in close agreement with previously published data for similar source configurations. The MCNP Monte Carlo code appears to be ideally suited to low energy dosimetry applications.PACS number(s): 87.53.–j

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Section: Discussionmentioning

confidence: 87%

Dosimetric parameters of three new solid core I‐125 brachytherapy sources

Solberg

DeMarco

Hugo

et al. 2002

J Applied Clin Med Phys

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“…Originally, most studies using MCNP were focused on neutron transportation (Brugger and Herleth 1990, Liu et al 1992, Metzger et al 1993, Wallace et al 1995, Evans and Blue 1996. With the development of the extended version of MCNP 4A, known as MCNPX in 1994, extended particle and energy libraries were available with new variance reduction and data analysis techniques.…”

Section: Mcnp and Mcnpxmentioning

confidence: 99%

Monte Carlo methods for device simulations in radiation therapy

et al. 2021

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Monte Carlo (MC) simulations play an important role in radiotherapy, especially as a method to evaluate physical properties that are either impossible or difficult to measure. For example, MC simulations (MCSs) are used to aid in the design of radiotherapy devices or to understand their properties. The aim of this article is to review the MC method for device simulations in radiation therapy. After a brief history of the MC method and popular codes in medical physics, we review applications of the MC method to model treatment heads for neutral and charged particle radiation therapy as well as specific in-room devices for imaging and therapy purposes. We conclude by discussing the impact that MCSs had in this field and the role of MC in future device design.

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