Simulation and Design of Biological Shield for the 115 kJ IR-MPF-100 Plasma Focus Device Using MCNP Code

Babaei, Morteza; Sadighzadeh, A.; Kiashemshaki, Maryam; Vosoghi, Sara; Zaeem, A. A.; Kasesaz, Yaser; Rezaeifard, Behzad; Damideh, Vahid

doi:10.1007/s10894-016-0073-2

Cited by 2 publications

(2 citation statements)

References 20 publications

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“…The MCNP code is based on the Monte Carlo method, which can realistically describe random events and calculate the particle transport problem. 26 Given that the problem is dealing with neutron and secondary photon interaction with the desired sample, MCNP code runs in neutron and photon mode. The schematic diagram of model is shown in Figure 1(a).…”

Section: Methodsmentioning

confidence: 99%

Boracic polyethylene/polyethylene wax blends and open-cell nickel foams as neutron-shielding composite

Zhang

Chen

Tang

et al. 2017

Journal of Reinforced Plastics and Composites

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This work shows that mechanical properties, thermal conductivity, and secondary gamma-ray shielding ability can be significantly improved when open-cell nickel foams are embedded into the shielding composites. The boracic polyethylene/polyethylene wax blends and open-cell nickel foam composites (PPNM) are designed and prepared by permeating homogeneous mixed melt fillers into open-cell nickel foams. The ratio of polyethylene and polyethylene wax is investigated to achieve higher filling rate. The quasi-static compressive response of PPNMs and polyethylene/polyethylene wax blends is measured, and the crystallization properties are studied by differential scanning calorimetry. The neutron and secondary gamma-ray shielding abilities of PPNMs are also simulated based on Monte Carlo particle transport method. Results show that the compression strength of PPNMs with boron carbide is slightly improved when compared with polyethylene/polyethylene wax blends. The nickel foams in PPNM composites improve the energy-absorbing efficiency by 30%. The thermal conductivity of PPNMs is 300% higher than polyethylene/polyethylene wax. The calculated results show that neutron-shielding abilities of PPNMs increase as content of boron carbide increases. Moreover, secondary gamma-ray shielding ability of PPNMs containing boron carbide is obviously higher than polyethylene/polyethylene wax. The PPNMs containing boron carbide neutron-shielding materials are proved to have good thermal conductivity, mechanical properties, and radiation-shielding ability.

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Section: Methodsmentioning

confidence: 99%

Boracic polyethylene/polyethylene wax blends and open-cell nickel foams as neutron-shielding composite

Zhang

Chen

Tang

et al. 2017

Journal of Reinforced Plastics and Composites

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“…The air sphere was supposed tangential to the shielding wall, as well as the distance between the center of the air phantom and the head of the generator tube was assumed 200 cm and the central axis of the tube is perpendicular to the central axis of the body phantom. Different materials were considered including Solid-Boric-Acid (SBA), Polyethylene Non-Borated (PNB), Paraffine (P), Concrete 806 (C), Borated-Polyethylene (60% polyethylene + 30% natural boron) (BP), AlF3 [23]. All shielding materials were examined with different thicknesses of 10, 20, 30, 40, 50, 60 cm at 90 degrees.…”

Section: Second Simulation Studymentioning

confidence: 99%

MCNP Dose evaluation around D-D and D-T neutron generators and shielding design

2021

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In recent years, neutron generators have extensively used as neutron sources and vast efforts have been made to develop high yield neutron generators, so the aspect of radiation shielding during the utilization of neutron generators is unavoidable. In this study, dose distribution around the D-D and D-T neutron generator was calculated by using Monte Carlo simulation. Then an effective shielding was designed and different materials with different thicknesses at distinction distances from the generator were examined. Finally, the organs dose was acquired by using ICRP 110 male phantom with and without shielding at different body position relative to generator tube.The results show that the dose induced by the D-T generator is 500 times greater than the D-D generator and the neutron dose is about 100 times more than gamma dose. The dose is reduced about 20 times by increasing the distance up to 5 m, however, the presence of Borated-Polyethylene with a thickness of 60 cm as most effective shielding reduces the whole-body dose up to 60%. Besides, inserting a layer of Pb to Borated-Polyethylene is effective to attenuate the gamma-rays. The received dose to organs depends on the body direction relative to tube head of neutron generator. In general, the best position of tube placement relative to shielding wall are 90 and 180 degrees for the D-T and D-D generators, respectively, distance between the generator tube head and the phantom is suggested 200 cm and it is recommended that for most dose reduction, the operator stands in the anterior-posterior position relative to generator tube. K: Dosimetry concepts and apparatus; Models and simulations; Radiation damage evaluation methods; Neutron sources

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Simulation and Design of Biological Shield for the 115 kJ IR-MPF-100 Plasma Focus Device Using MCNP Code

Cited by 2 publications

References 20 publications

Boracic polyethylene/polyethylene wax blends and open-cell nickel foams as neutron-shielding composite

Boracic polyethylene/polyethylene wax blends and open-cell nickel foams as neutron-shielding composite

MCNP Dose evaluation around D-D and D-T neutron generators and shielding design

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