Part VI: Monte Carlo calculation of the nucleon meson cascade in shielding materials

Geibel, J.; Ranft, J.

doi:10.1016/0029-554x(65)90476-3

Cited by 17 publications

(2 citation statements)

References 13 publications

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“…The differential angular distribution of pions, i.e. the scattering kernel is given by the empirical relation (Geibel and Ranft 1965) (7) The Legendre coefficient a, is given by…”

Section: Scattering Kernelmentioning

confidence: 99%

Pion transport studies

Muthukrishnan¹

1986

Phys. Med. Biol.

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A method of solving the transport equation to study the transport of secondary pions due to the interaction of high-energy protons is described. The pion decays into a muon and a neutrino during its flight. This decay probability is considered during the flight of the pion. Towards the end of the range, a negative pion is absorbed by the nucleus, which results in the release of its rest energy of 140 MeV. About 30 MeV of the energy, released in the form of charged particles, is absorbed locally. When a positive pion is stopped, about 34 MeV energy, (4.2 MeV due to the muon and 30 MeV due to the positron) is deposited locally. The method described is used to calculate the depth-dose distribution of pions, which are produced due to high-energy protons incident normally on a 30 cm thick tissue slab. The results thus obtained are compared with the Monte Carlo values.

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“…The differential angular distribution of pions, i.e. the scattering kernel is given by the empirical relation (Geibel and Ranft 1965) (7) The Legendre coefficient a, is given by…”

Section: Scattering Kernelmentioning

confidence: 99%

Pion transport studies

Muthukrishnan¹

1986

Phys. Med. Biol.

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“…Radiation shielding aprons commonly use lead material due to its excellent properties, which has been around for a long time [5]. In advance, the method called Monte-Carlo simulation (MCNP) has been widely followed in the studies that comprises of the designing and testing of new materials for radiation shielding [6][7][8][9][10][11][12]. The MCNP is a mathematical program that uses random numbers to compute statistical outcomes from an interaction between radiation and other particles.…”

Section: Introductionmentioning

confidence: 99%

Design and Development of a Low-Cost, Less Weight, and Lead-Free Composite Materials for Radiation Shielding

Rajagopal¹,

Anand

2022

ECS Trans.

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The paper analyzes the performance of various composite materials in the lead-free apron for radiation shielding in biomedical applications. The challenging task is to extend the duration of wearing an apron, reduce the weight, and increase the comfort level for physicians. The lead-free composite materials used an alternative to lead in an apron due to their excellent properties, such as mass attenuation coefficients, effectiveness against gamma radiation, flexibility and light weight, and absorption. The present study discusses different simulation software used to assess the properties of the shielding material against the radiation effects. At the end of the paper, the promising directions are presented for future research.

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