Monte Carlo simulations for optimization of neutron shielding concrete

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

doi:10.2478/s13531-011-0063-0

Cited by 31 publications

(21 citation statements)

References 12 publications

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“…One more conclusion is that changing amount of Ba in wide area has no influence on shielding efficiency. It is in agreement with preliminary studies made by Piotrowski et al [24]. It is clear that the most activated concretes had a large amount of iron.…”

Section: Monte-carlo Aided Design Of Neutron Shielding Concretessupporting

confidence: 82%

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Monte-Carlo aided design of neutron shielding concretes

Tefelski

Piotrowski²,

Polański³

et al. 2013

Bulletin of the Polish Academy of Sciences: Technical Sciences

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Abstract. The process of design of building composites, like concrete is a complex one and involves many aspects like physical and mechanical properties, durability, shielding efficiency, costs of production and dismantlement etc. There are plenty of parameters to optimize and computer tools can help to choose the best solution. A computer aided design plays an important role nowadays. It becomes more accurate, faster and cheaper, so laboratories often apply computer simulation methods prior to field testing. In case of nuclear engineering, the radiation shielding problems are of much importance, because safety of such facilities is a key point. In this article the most effective methods for neutron shielding studies based on Monte-Carlo simulations of neutron transport and nuclide activation studies in concrete are presented. Two codes: MCNPX and CINDER'90 are extensively used to compare the shielding efficiency of commonly used concretes and to study the influence of concentration of B, Ba and Fe elements on shielding efficiency.

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Section: Monte-carlo Aided Design Of Neutron Shielding Concretessupporting

confidence: 82%

“…The presented results are the second step of the research program. The first were the simulations on shielding of theoretical composition of concretes in a theoretical neutron flux [24]. In this paper there have been simulated shielding and activation of real concretes from nuclear facilities in a theoretical neutron flux.…”

Section: Discussionmentioning

confidence: 99%

Monte-Carlo aided design of neutron shielding concretes

Tefelski

Piotrowski²,

Polański³

et al. 2013

Bulletin of the Polish Academy of Sciences: Technical Sciences

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“…The source was simulated inside the sample and the outer surface was treated as a detector. First MCNP simulations were performed for a neutron flux from a light water reactor (LWR) core with total flux of 4.64 × 10 9 n/(cm 2 s) calculated using APOLLO 2 [4]. By the use of this neutron source first the influence of gadolinium oxide content in 1, 2 and 5% in relation to cement was analysed by the comparison of neutron flux on the different levels of energy counted in the detector.…”

Section: Methodsmentioning

confidence: 99%

“…Preliminary studies of Piotrowski et al [4] were based on Monte Carlo computer simulations and it was indicated that both the compressive strength and type of concretes (normal and heavy-weight) have a significant effect on the shielding against neutron. It was concluded that the decrease in the neutron dose detected behind the concrete shielding was proportional to the concrete (B-9) strength and an increase in the cement content in the mixture and the associated mass of bound water as a result of its hydration.…”

Section: Introductionmentioning

confidence: 99%

NGS-Concrete - New Generation Shielding Concrete against Ionizing Radiation - the Potential Evaluation and Preliminary Investigation

et al. 2015

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Concrete is a common material used as a shielding against ionizing radiation due to the relatively low cost and the ability to meet the structural function. State of the art in concrete shielding is that while in case of gamma radiation an increase in density by a change of aggregate is usually efficient enough, protection against neutrons is more complex. It is due to the differences in interactions of neutrons with the matter, depending on their kinetic energy and reaction cross-sections with the component atoms of the cement paste and the aggregate. Last progress in concrete evolution due to use of polymer additives (e.g. superplasticizers) together with reactive additions (e.g. silica fume) allows for a new look at the concrete design for radiation shielding purposes. One of the main advantages of concrete is its composite-type and there is a potential for the optimization of its constituents as well as mixture proportions. The paper presents the preliminary results of the project NGS-Concrete -newgeneration shielding concrete against ionizing radiation. The aim of the project is to design the composition of concrete against ionizing radiation, achieved by the use of experiment based multi-criteria optimization of materials supported by the Monte Carlo simulations. The purpose of presented studies was to evaluate neutron shielding properties of ordinary and heavy-weight magnetite concrete modified with epoxy resin and gadolinium oxide. At first the shielding efficiency against neutrons from LWR neutron flux source and Pu-Be was simulated in MCNP code. At the end the comparison of MCNP simulated results and real experiment was presented. It was proved that both methods of modification can improve neutron shielding properties concrete but gadolinium oxide is an efficient additive only for low energy neutron attenuation.

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“…First studies carried out by Piotrowski et al [9] in this field using Monte Carlo computer simulations indicate that both the compressive strength and type of concrete have a significant effect on the shielding against neutron. The decrease in the dose is proportional to the strength and an increase in the cement content and the associated mass of bound water as a result of its hydration.…”

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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Monte Carlo simulations for optimization of neutron shielding concrete

Cited by 31 publications

References 12 publications

Monte-Carlo aided design of neutron shielding concretes

Monte-Carlo aided design of neutron shielding concretes

NGS-Concrete - New Generation Shielding Concrete against Ionizing Radiation - the Potential Evaluation and Preliminary Investigation

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

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