Radiation Shielding

Shultis, J. Kenneth; Faw, R.E.

doi:10.1007/978-1-4939-6618-9_25

Cited by 21 publications

(61 citation statements)

References 34 publications

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“…The parameters include the total macroscopic cross-section for gamma interactions Σ t , and the double-differential macroscopic scattering cross-section Σ s , which depends on the change in gamma energy from incident energy E to emergent energy E (i.e., E → E) and the change in gamma direction from incident direction Ω to Ω (i.e., Ω → Ω). We refer readers to Shultis and Faw [3] for a more detailed treatment of transport theory.…”

Section: Radiation Transport Model and Surrogate Formulationsmentioning

confidence: 99%

“…whereΩ is a unit vector pointing in the traveling direction of the gamma rays and E 0 is the source emission energy and delta denotes the Dirac delta function; see [3] for more details. Equation (2) can be solved to determine the intensity of photons arriving at any point r inside domain.…”

Section: Radiation Transport Model and Surrogate Formulationsmentioning

confidence: 99%

“…The computational complexity of deterministic [3] and stochastic, Monte Carlo [4] radiation transport models poses a second challenge since it limits the number of model realizations that can be obtained for optimization, or Bayesian or frequentist inference. This has led to the development of alternative parameterizations or surrogate models.…”

Section: Introductionmentioning

confidence: 99%

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Surrogate-Based Robust Design for a Non-Smooth Radiation Source Detection Problem

et al. 2019

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In this paper, we develop and numerically illustrate a robust sensor network design to optimally detect a radiation source in an urban environment. This problem exhibits several challenges: penalty functionals are non-smooth due to the presence of buildings, radiation transport models are often computationally expensive, sensor locations are not limited to a discrete number of points, and source intensity and location responses, based on a fixed number of sensors, are not unique. We consider a radiation source located in a prototypical 250 m × 180 m urban setting. To address the non-smooth properties of the model and computationally expensive simulation codes, we employ a verified surrogate model based on radial basis functions. Using this surrogate, we formulate and solve a robust design problem that is optimal in an average sense for detecting source location and intensity with minimized uncertainty.

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Section: Radiation Transport Model and Surrogate Formulationsmentioning

confidence: 99%

Section: Radiation Transport Model and Surrogate Formulationsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Surrogate-Based Robust Design for a Non-Smooth Radiation Source Detection Problem

et al. 2019

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“…Wedge dan Kurva Isodosis (Chang et al, 2014) Simulasi perhitungan laju dosis serap dapat dilakukan menggunakan Monte Carlo NPartikel (MCNP), software komputer berbasis metode Monte Carlo. Software MCNP digunakan untuk menyimulasikan perjalanan partikel neutron, elektron dan foton dalam suatu material tiga dimensi (Shultis and Faw, 2011).…”

Section: Pendahuluanunclassified

Optimalisasi Geometri Wedge pada Pesawat Teleterapi 60Co

et al. 2017

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Abstract: In RSUD Dr. Moewardi available wedge angle of 15°, 30°, 45°, and 60°. This research simulates with Monte Carlo N-Particle eXtended Version (MCNPX) computer software to determine the geometry of the wedge that produces the isodose angle of 20°, which is hoped to be applied to therapy of organ tilt of 20 ° in some cases of cervical cancer. In simulation obtained the value of the wedge factor of isodose angle of 20° and distribution of dose rate. The simulated material of wedge is Lead-Antimony Alloy. Verification of the simulation result was done by measuring the wedge factor of angle of 30° and 60°, the simulation result was validated with result of measurement experiment on 60Co teletherapy in RSUD Dr. Moewardi Surakarta. The relative error between simulation and measurement experiment of wedge angle of 30° is 8.84% and angle of 60° is 4.35%. The relative error is small to convince the researcher to develop a simulation at an isodose angle of about 20°. From the simulation results obtained isodose angle 20.3° of Lead-Antimony Alloy material with geometry is length 16 cm, width 14.9 cm, thick 0.83 cm, the value of the angle α of 3.2°. Wedge factor of isodose angle of 20.3 ° is (0.68 ± 0.01). Wedge isodose angle of 20.3° if used in therapy in an organ tilt about 20 ° gives dose rate enough uniform. Abstrak :. Di RSUD Dr. Moewardi tersedia wedge untuk sudut 15°, 30°, 45°, dan 60°. Penelitian ini mensimulasikan dengan software computer Monte Carlo N-Particle eXtended Version (MCNPX) untuk menentukan geometri wedge yang menghasilkan sudut isodosis 20°, dimana diharapkan dapat diaplikasikan pada terapi organ dengan kemiringan 20° di beberapa kasus kanker serviks. Besaran yang diperoleh dari simulasi adalah nilai faktor transmisi wedge sudut isodosis 20° dan distribusi laju dosis serap penggunaan wedge tersebut. Bahan wedge yang disimulasikan adalah Lead-Antimony Alloy. Verifikasi hasil simulasi dilakukan dengan pengukuran faktor wedge pada sudut isodosis 30° dan 60°, hasil simulasi divalidasi dengan hasil pengukuran langsung pada pesawat teleterapi 60Co di RSUD Dr. Moewardi Surakarta. Kesalahan antara simulasi dan pengukuran langsung pada isodosis sudut 30° adalah 8,84 % dan pada sudut 60° adalah 4,35 %. Kesalahan relatif tersebut cukup kecil sehingga meyakinkan peneliti untuk menyusun simulasi pada sudut sekitar 20°. Dari hasil simulasi diperoleh isodosis sudut 20,3° dari bahan Lead-Antimony Alloy dengan geometri yaitu panjangnya 16 cm, lebarnya 14,9 cm, tebalnya 0,83 cm, nilai sudut α sebesar 3,2°. Faktor wedge sudut 20,3° sebesar (0,68 ± 0,01). Wedge sudut isodosis 20,3° bila digunakan dalam terapi pada organ dengan kemiringan 20° memberikan laju dosis yang cukup seragam.

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“…Para cada tally, o MCNP além de calcular a média amostral x , também estima outros dados estatísticos. Um dos mais importantes e que sempre acompanha x é o erro relativo R [48] , definido como…”

Section: Fluxo De Nêutronsunclassified

Caracterização dos campos neutrônicos obtidos por meio de armadilhas de nêutrons a partir da utilização de água pesada (D2O) no interior do núcleo do reator nuclear IPEN/MB-01

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Radiation Shielding

Cited by 21 publications

References 34 publications

Surrogate-Based Robust Design for a Non-Smooth Radiation Source Detection Problem

Surrogate-Based Robust Design for a Non-Smooth Radiation Source Detection Problem

Optimalisasi Geometri Wedge pada Pesawat Teleterapi 60Co

Caracterização dos campos neutrônicos obtidos por meio de armadilhas de nêutrons a partir da utilização de água pesada (D2O) no interior do núcleo do reator nuclear IPEN/MB-01

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