Monte Carlo simulations for optimization of neutron shielding concrete
| Autor: | Aleksander Polański, Janusz Skubalski, D. Tefelski, Tomasz Piotrowski |
|---|---|
| Rok vydání: | 2012 |
| Předmět: |
Neutron transport
Environmental Engineering Materials science Astrophysics::High Energy Astrophysical Phenomena Nuclear engineering Monte Carlo method Aerospace Engineering concrete design and optimization Forensic engineering General Materials Science Neutron Electrical and Electronic Engineering Nuclear Experiment Civil and Structural Engineering Aggregate (composite) monte carlo business.industry Mechanical Engineering Neutron radiation Engineering (General). Civil engineering (General) Neutron temperature Electromagnetic shielding TA1-2040 Radiation protection business radiation protection |
| Zdroj: | Open Engineering, Vol 2, Iss 2, Pp 296-303 (2012) |
| ISSN: | 2391-5439 |
| DOI: | 10.2478/s13531-011-0063-0 |
| Popis: | 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. |
| Databáze: | OpenAIRE |
| Externí odkaz: |
|