Compendium of Material Composition Data for Radiation Transport Modeling

Williams, Ralph G.; Gesh, Christopher J.; Pagh, Richard T.

doi:10.2172/902408

Cited by 41 publications

(19 citation statements)

References 2 publications

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“…Simulated material compositions, drawn from the literature as appropriate [16,17], appear in Table 1. Although efforts were made to model the measurements as faithfully as possible, simplifications were present in the geometries of the surrounding environment, neutron generator, and neutron detectors.…”

Section: Monte Carlo Simulationsmentioning

confidence: 99%

D-D neutron-scatter measurements for a novel explosives-detection technique

Lehnert

Flaska

Kearfott

2012

Nuclear Instruments and Methods in Physics Research Section A:

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Section: Monte Carlo Simulationsmentioning

confidence: 99%

D-D neutron-scatter measurements for a novel explosives-detection technique

Lehnert

Flaska

Kearfott

2012

Nuclear Instruments and Methods in Physics Research Section A:

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“…Initiation of MCNP requires an input file that contains complete information about the radiation source, the geometry of the system to be simulated, and both the density and the elemental composition of all interacting materials. The Concrete composition was taken as an ordinary concrete 2.3 g cm -3 in density [12].…”

Section: Methodsmentioning

confidence: 99%

Shielding calculations for industrial 5/7.5MeV electron accelerators using the MCNP Monte Carlo Code

Peri¹,

Orion

2017

EPJ Web Conf.

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Abstract..High energy X-rays from accelerators are used to irradiate food ingredients to prevent growth and development of unwanted biological organisms in food, and by that extend the shelf life of the products. The production of X-rays is done by accelerating 5 MeV electrons and bombarding them into a heavy target (high Z). Since 2004, the FDA has approved using 7.5 MeV energy, providing higher production rates with lower treatments costs. In this study we calculated all the essential data needed for a straightforward concrete shielding design of typical food accelerator rooms. The following evaluation is done using the MCNP Monte Carlo code system: (1) Angular dependence (0-180°) of photon dose rate for 5 MeV and 7.5 MeV electron beams bombarding iron, aluminum, gold, tantalum, and tungsten targets. (2) Angular dependence (0-180°) spectral distribution simulations of bremsstrahlung for gold, tantalum, and tungsten bombarded by 5 MeV and 7.5 MeV electron beams. (3) Concrete attenuation calculations in several photon emission angles for the 5 MeV and 7.5 MeV electron beams bombarding a tantalum target. Based on the simulation, we calculated the expected increase in dose rate for facilities intending to increase the energy from 5 MeV to 7.5 MeV, and the concrete width needed to be added in order to keep the existing dose rate unchanged.

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“…The shapes of the elements in the flow diagram are as follows: rounded ovals for user inputs, parallelograms for matrices, rectangles for calculations, diamonds for decisions, and squared oval for the output. The initial guess of the elemental composition was obtained from the elemental composition of the suspected concrete type from the Compendium of Material Composition Data for Radiation Transport Modeling published by Pacific Northwest National Laboratory (Williams et al 2006).…”

Section: Solving For Elemental Compositionmentioning

confidence: 99%

Developing a Methodology for Determination of Elemental Composition of Shielding Materials

Fitzmaurice¹,

Marianno²,

Солодов³

2015

Health Physics

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Radiation transport simulation models can provide estimations of radiation effects such as detector response and detection capabilities. The objective of this research was to develop a methodology for quick, efficient, and effective determination of the composition of shielding materials to be used in radiation transport models. A C++ code, MatFit, was developed that used the concept of densitometry and the iterative method developed for the Spectrum Analysis by Neutron Detectors II (SAND II) computer program to estimate the elemental composition of shielding materials. These results were compared to previous neutron activation analysis (NAA) on the same samples. It was determined that densitometry provided an elemental approximation that yielded an attenuation rate within 10% of that found through NAA but requires much fewer resources, as well as less time. From this research, it is recommended that the developed method and C++ program be used when constructing models for detector response.

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Compendium of Material Composition Data for Radiation Transport Modeling

Cited by 41 publications

References 2 publications

D-D neutron-scatter measurements for a novel explosives-detection technique

D-D neutron-scatter measurements for a novel explosives-detection technique

Shielding calculations for industrial 5/7.5MeV electron accelerators using the MCNP Monte Carlo Code

Developing a Methodology for Determination of Elemental Composition of Shielding Materials

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