Radiation shielding of high-energy neutrons in SAD

Seltborg, Per; Polański, A.; Petrochenkov, S.; Lopatkin, A. V.; Gudowski, Wacław; Швецов, В. Н.

doi:10.1016/j.nima.2005.04.071

Cited by 9 publications

(6 citation statements)

References 8 publications

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“…In Poland SAMSY [5] numerical programs as well as ANISN [6], DOT [7], MORSE [8] and MCNP/MCNPX [9] have been the most commonly used to design the shield against the radiation of nuclear facilities, such as the MARIA nuclear reactor in Świerk and The Żarnowiec nuclear power plant [1], the accelerator in the SINS and sub-critical assembly SAD [10]. These programs allow for the solution of Boltzmann transport equation using removediffusion method (SAMSY), discrete ordinates method (ANISN, DOT) or the Monte Carlo (MC) method (MORSE, MCNP).…”

Section: Monte Carlo Simulationsmentioning

confidence: 99%

Monte Carlo simulations for optimization of neutron shielding concrete

et al. 2012

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Concrete is one of the main materials used for gamma and neutron shielding. While in case of gamma rays an increase in density is usually efficient enough, protection against neutrons is more complex. The aim of this paper is to show the possibility of using the Monte Carlo codes for evaluation and optimization of concrete mix to reach better neutron shielding. Two codes (MCNPX and SPOT -written by authors) were used to simulate neutron transport through a wall made of different concretes. It is showed that concrete of higher compressive strength attenuates neutrons more effectively. The advantage of heavyweight concrete (with barite aggregate), usually used for gamma shielding, over the ordinary concrete was not so clear. Neutron shielding depends on many factors e.g. neutron energy, barrier thickness and atomic composition. All this makes a proper design of concrete as a very important issue for nuclear power plant safety assurance.

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Section: Monte Carlo Simulationsmentioning

confidence: 99%

Monte Carlo simulations for optimization of neutron shielding concrete

et al. 2012

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“…Natural or artificial shielding can further reduce the neutron flux. For example, 2 m of concrete will reduce the impact of 10 Mev neutron radiation by three orders of magnitude (Seltborg et al, 2005); less energetic neutrons are attenuated much more. On the other hand, neutrons with energies above 10 MeV carry a very small fraction of the total energy of cosmic-ray neutrons (Hess et al, 1959).…”

Section: Shieldingmentioning

confidence: 99%

Addressing failures in exascale computing

Snir

Wisniewski

Abraham

et al. 2014

The International Journal of High Performance Computing Applica

282

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We present here a report produced by a workshop on 'Addressing failures in exascale computing' held in Park City, Utah, 4-11 August 2012. The charter of this workshop was to establish a common taxonomy about resilience across all the levels in a computing system, discuss existing knowledge on resilience across the various hardware and software layers of an exascale system, and build on those results, examining potential solutions from both a hardware and software perspective and focusing on a combined approach.The workshop brought together participants with expertise in applications, system software, and hardware; they came from industry, government, and academia, and their interests ranged from theory to implementation. The combination allowed broad and comprehensive discussions and led to this document, which summarizes and builds on those discussions.

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“…8 and 9 there are effective dose rates calculated for hypothetical human body behind the shield wall. Doses were calculated with factors obtained from [23] with the use of neutron and secondary gamma production in material due to nuclear reactions. Generally, it is clear that the borated concretes are better shielding than others.…”

Section: Simulation Set Up For Lwr Reactor Neutron Fluxmentioning

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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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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Radiation shielding of high-energy neutrons in SAD

Cited by 9 publications

References 8 publications

Monte Carlo simulations for optimization of neutron shielding concrete

Monte Carlo simulations for optimization of neutron shielding concrete

Addressing failures in exascale computing

Monte-Carlo aided design of neutron shielding concretes

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