Neutron Diffusion — Basic Concepts

Almenas, K.; Lee, R.

doi:10.1007/978-3-642-48876-4_4

Cited by 2 publications

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“…From the Figure 5, we can notice that, variations of dose rate did not follow a sharp way. From the transport theory approach, at a given location the neutrons are sorted according to their direction and each bundle of neutrons having a specific direction [18]. Initially collimated neutrons travel toward the target and get scattered in various directions.…”

Section: Neutron Dose Rate As a Function Of Detector Positionmentioning

confidence: 99%

Measurements of photoneutron dose rate for 15 MV photon beam from medical linear accelerator using neutron survey meter

Musfika,

Jamil,

Siddiqua

et al. 2023

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High-energy medical linear accelerators (>10MV) are increasingly used in the medical field to treat cancer patients depending on the treatment organ and patient physic. Medical linear accelerators (Linacs) operating above 10 MV photon beam produce unwanted neutrons (photoneutron) by means of photonuclear reaction (γ, n) between bremsstrahlung photon beams and constituent materials of Linac head. This study involved the measurement of the neutron dose rate from photon beam of medical linear accelerator (Elekta Synergy) operated at 15 MV photon. For the measurement of dose rate, a neutron survey meter LB 6411 probe was used. Neutron dose rate was obtained as a function of delivered dose, field size and detector position. In the study neutron dose rate was found 13.14 mSv/h at a field size of 10 × 10 cm2 at position (0,90,0) cm for 350 cGy and 9.26 mSv/h at 5 × 5 cm2 field size at position (0,80,0) cm for 200 cGy photon dose delivery. The dose rate varied with respect to detector position in an irregular manner; 2.95 mSv/h at position (-100,0,0) cm -on the side of maze entrance and 4.85 mSv/h at position (100,0,0) cm -off side of maze entrance.

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Section: Neutron Dose Rate As a Function Of Detector Positionmentioning

confidence: 99%

Measurements of photoneutron dose rate for 15 MV photon beam from medical linear accelerator using neutron survey meter

Musfika,

Jamil,

Siddiqua

et al. 2023

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“…One of the most interesting physics problems that are expressed through partial differential equations is the neutron diffusion equations with delayed neutrons system (NDEDNS) of the form [35][36][37][38]:…”

Section: Introductionmentioning

confidence: 99%

A Novel Scheme of the ARA Transform for Solving Systems of Partial Fractional Differential Equations

Burqan

2023

Fractal Fract

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In this article, a new analytical scheme of the ARA transform is introduced to solve systems of fractional partial differential equations. The principle of the proposed technique is based on combining the ARA transform with the residual power series method to create an approximate series solution for a system of partial differential equations of fractional order on the form of a rapid convergent series. To illustrate the effectiveness, accuracy, and validity of the suggested technique, an Attractive physical system, the fractional neutron diffusion equation with one delayed neutrons group, is discussed and solved. Two different neutron flux initial conditions are presented numerically to clarify various cases in order to ensure the theoretical results. The necessary Mathematica codes are run using vital nuclear reactor cross-section data, and the results for various values of time are tabulated and graphically represented.

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Neutron Diffusion — Basic Concepts

Cited by 2 publications

References 0 publications

Measurements of photoneutron dose rate for 15 MV photon beam from medical linear accelerator using neutron survey meter

Measurements of photoneutron dose rate for 15 MV photon beam from medical linear accelerator using neutron survey meter

A Novel Scheme of the ARA Transform for Solving Systems of Partial Fractional Differential Equations

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