Monte-Carlo aided design of neutron shielding concretes

Tefelski, D.; Piotrowski, Tomasz; Polański, A.; Skubalski, Janusz; Blidéanu, V.

doi:10.2478/bpasts-2013-0015

Cited by 9 publications

(9 citation statements)

References 17 publications

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“…It is a numerical method of multiple sampling of a neutron history and the final result is obtained statistically. A simplified algorithm of the MC neutron transport simulation was presented by Tefelski et al [2]. The MC simulation in this research was performed using MCNP code on a geometry and Pu-Be neutron source as it was used in experiment.…”

Section: Simulationsmentioning

confidence: 99%

“…Previous studies by Piotrowski et al [1] and Tefelski et al [2] based on computer simulations using MC method indicate that both the type of concrete (normal and heavy-weight) and its compressive strength have a significant effect on the shielding against neutron. The decrease in the dose is proportional to the strength, apparent increase of cement content and the associated mass of bound water as a result of its hydration.…”

Section: Introductionmentioning

confidence: 98%

See 1 more Smart Citation

Importance of Atomic Composition and Moisture Content of Cement based Composites in Neutron Radiation Shielding

Piotrowski

Mazgaj

Żak

et al. 2015

Procedia Engineering

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Monte Carlo computer simulations confirmed that an increase in density has a minor effect on the weakening of neutron transport and, therefore, the optimum composition of a shielding concrete against gamma radiation is different than the one against neutron radiation. Neutron radiation shielding is a two-step process: slowing down of fast neutrons and absorption of thermal ones. Both result from the atomic composition of the barrier but their dependence on specified atomic compositions and moisture content is different. The aim of the presented research is to develop a high density concrete the composition of which would also assure good efficiency of neutron shielding. Neutron transport through standard cement mortar, PCC mortar, normal-weight concrete and magnetite heavy-weight concrete has been analyzed in the paper. The goal in research was to find an influence of the cement type, polymer addition, density and moisture content on the shielding properties against neutron. The research based on convergent results of MC computer simulations and real experiments confirmed the influence of the cement type on fast neutron attenuation. It was also found that each 1% of moisture content makes 10% increase of fast neutron thermalization effectiveness, what is a little less than it was estimated for cement based mortars. It was also proved that heavyweight concrete is not proper solution for shielding against fast neutrons, but its efficiency is visible in the case of thermal neutrons absorption, probably due to increase of Fe content at the expense of Si and O in the atomic composition as well as water retained by magnetite aggregate.

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Section: Simulationsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 98%

Importance of Atomic Composition and Moisture Content of Cement based Composites in Neutron Radiation Shielding

Piotrowski

Mazgaj

Żak

et al. 2015

Procedia Engineering

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“…Different are the results of studies made by Tefelski et al [6] who compared neutron shielding calculated using MCNP code for ordinary, heavy-weight barite and reinforced concrete and concluded that the worst concrete for this purpose is barite heavy-weight concrete as it is full of high elements with very small cross-sections for neutron capture. In the same research it was proved that neutron attenuation for borated concrete in comparison to heavy concrete is of one or two orders of magnitude, but this advantage of borated concretes is removed as they have been the most activated and their activation decrease in time has been the slowest.…”

Section: B-15 Frommentioning

confidence: 99%

Experiments on Neutron Transport through Concrete Member and the Potential for the Use in Material Investigation

et al. 2015

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Concrete has been used as a shield against high-energy photons and neutrons since the beginning of use of nuclear reaction in energy, medicine and research. From that time the progress in concrete technology is huge -very good concrete used in 60's was about 30 MPa compressive strength, and now the recommendation of ETC-C is to use in EPR nuclear power plant the concrete at least class C45/55 for airplane resistant shell or class C40/50 for other structures. The Monte Carlo computer simulations indicate that an increase in density of the shielding member has a minor effect on the weakening of neutron transport and, therefore, the optimal composition of a shielding concrete against gamma radiation is different than the optimal composition of shielding concrete against neutron radiation. Neutron stopping is a two-step effect: slowing down of fast neutrons and absorption of thermal ones. Both result from the atomic composition of the barrier. The paper presents an analysis of neutrons transport through concrete cement mortar and polymer cement composites mortar based on specially designed experiments which allows for measuring fast neutron attenuation and thermal neutron capture separately. The aim of experiments was to find an influence of the cement type, polymer addition and moisture content on both aspects of neutron shielding properties of a composite. The experimental results were confirmed in MCNP simulations. There was found an influence of cement type on fast neutron attenuation due to differences in chemical composition. Next an important improvement of both fast neutron attenuation and thermal neutron capture due to polymer modification of concrete. The last was fond of clear linear relationship between fast neutron attenuation to the hydrogen content which shows the possibility of using this phenomenon in building material investigation like measurement of moisture content or polymer content in the polymer cement composites.

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“…In the case of shielding against high-energy photons (gamma radiation) the increase in concrete density by change of aggregate type, e.g., from a normal to a heavy-weight type, is sufficiently effective [12,13]. Protection against neutrons is a more complex and sophisticated task [14][15][16], because neutrons are no-charge particles travelling in straight lines and interacting only with atomic nuclei while passing through matter. Neither the electrons surrounding a nucleus (the atomic electron cloud) nor the electric field caused by a positively charged nucleus affect a neutron's flight.…”

Section: Introductionmentioning

confidence: 99%

Influence of Polymer Modification on the Microstructure of Shielding Concrete

2020

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In this paper an analysis of the influence of polymer modification on the microstructure, shielding properties against neutrons, and compressive strength of heavy-weight magnetite concrete is carried out. The modifications involve the addition of acrylic or epoxy dispersions as well as micro- or/and macrofibers. A computer image analysis method is used to evaluate the microstructure of concretes and parameters of pore structure are calculated; these parameters include relative volume fraction, relative specific surface area, and pore arrangement ratios, including a proprietary ratio based on Voronoi tessellation. An assessment of significance of differences between stereological parameters of reference concrete and polymer modified concretes, as well as the impact of polymer form (dispersion or fibers) on shielding properties and compressive strength is carried out using Student’s t-test. The results show that except for the effect of the addition of both polypropylene micro- and macrofibers on the relative volume of pores, all other modifications result in statistically significant changes in the values of stereological parameters. Nevertheless, it is shown that neither polymer dispersions nor fibers have a statistically significant impact on shielding properties, but that they do influence compressive strength.

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Monte-Carlo aided design of neutron shielding concretes

Cited by 9 publications

References 17 publications

Importance of Atomic Composition and Moisture Content of Cement based Composites in Neutron Radiation Shielding

Importance of Atomic Composition and Moisture Content of Cement based Composites in Neutron Radiation Shielding

Experiments on Neutron Transport through Concrete Member and the Potential for the Use in Material Investigation

Influence of Polymer Modification on the Microstructure of Shielding Concrete

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