scholarly journals Experimental investigation on radiation shielding of high performance concrete for nuclear and radiotherapy facilities

2016 ◽  
Vol 22 (2) ◽  
pp. 41-47 ◽  
Author(s):  
Szymon Domański ◽  
Michał A. Gryziński ◽  
Maciej Maciak ◽  
Łukasz Murawski ◽  
Piotr Tulik ◽  
...  
Keyword(s):  
High Performance ◽  
High Performance Concrete ◽  
Absorbed Dose ◽  
Nuclear Research ◽  
Neutron Radiation ◽  
Radiation Shielding ◽  
Transmitted Radiation ◽  
Radiation Fields ◽  
Shielding Properties ◽  
Set Up

Abstract This paper presents the set of procedures developed in Radiation Protection Measurements Laboratory at National Centre for Nuclear Research for evaluation of shielding properties of high performance concrete. The purpose of such procedure is to characterize the material behaviour against gamma and neutron radiation. The range of the densities of the concrete specimens was from 2300 to 3900 kg/m3. The shielding properties against photons were evaluated using 137Cs and 60Co sources. The neutron radiation measurements have been performed by measuring the transmitted radiation from 239PuBe source. Scattered neutron radiation has been evaluated using the shadow cone technique. A set up of ionization chambers was used during all experiments. The gamma dose was measured using C-CO2 ionization chamber. The neutron dose was evaluated with recombination chamber of REM-2 type with appropriate recombination method applied. The method to distinguish gamma and neutron absorbed dose components in mixed radiation fields using twin detector method was presented. Also, recombination microdosimetric method was applied for the obtained results. Procedures to establish consecutive half value layers and tenth value layers (HVL and TVL) for gamma and neutron radiation were presented. Measured HVL and TVL values were linked with concrete density to highlight well known dependence. Also, influence of specific admixtures to concrete on neutron attenuation properties was studied. The results confirmed the feasibility of approach for the radiation shielding investigations.

Radiation shielding properties of high performance concrete reinforced with basalt fibers infused with natural and enriched boron

2017 ◽  
Vol 313 ◽  
pp. 306-318 ◽  
Author(s):  
Eyüp Zorla ◽  
Cagatay Ipbüker ◽  
Alex Biland ◽  
Madis Kiisk ◽  
Sergei Kovaljov ◽  
...  
Keyword(s):  
High Performance ◽  
High Performance Concrete ◽  
Radiation Shielding ◽  
Basalt Fibers ◽  
Shielding Properties

Effect of addition of molybdenum on photon and fast neutron radiation shielding properties in ceramics

2019 ◽  
Vol 45 (17) ◽  
pp. 23681-23689 ◽  
Author(s):  
Berna Oto ◽  
Esra Kavaz ◽  
Halil Durak ◽  
Aydın Aras ◽  
Zekiye Madak
Keyword(s):  
Fast Neutron ◽  
Neutron Radiation ◽  
Radiation Shielding ◽  
Shielding Properties

Age-Adjusted Effective Modulus Method for Creep of High-Performance Concrete

2006 ◽  
Vol 302-303 ◽  
pp. 693-699
Author(s):  
Bing Han ◽  
Yuan Feng Wang
Keyword(s):  
Experimental Data ◽  
Plastic Flow ◽  
High Performance ◽  
High Performance Concrete ◽  
Effective Modulus ◽  
Relaxation Coefficient ◽  
Modulus Method ◽  
Set Up

This paper discusses the suitability of using several creep theories of common concrete for creep of high-performance concrete (HPC). Based on the Age-Adjusted Effective Modulus method (AEMM) for creep of concrete, Improved Dischinger (ID) method and the Elastic Continuation and Plastic Flow (ECPF) theory for calculating relaxation coefficient and considering characteristics of HPC, a method is set up for calculating the creep of HPC under changing stresses, and comparing results gotten by the method with some experimental data, it can be considered that the above methods are suit for the calculation of creep of HPC.

scholarly journals New Composite Material Based on Heavy Concrete and Basalt-Boron Fiber for Neutron Radiation Shielding Properties

2019 ◽  
pp. 19-25 ◽  
Author(s):  
I. Romanenko ◽  
M. Holiuk ◽  
A. Nosovsky ◽  
T. Vlasenko ◽  
V. Gulik
Keyword(s):  
Composite Material ◽  
Neutron Radiation ◽  
Radiation Shielding ◽  
Nuclear Industry ◽  
Protective Properties ◽  
Horizon 2020 ◽  
Boron Fiber ◽  
Fast Fission ◽  
Fission Neutrons ◽  
Shielding Properties

It is necessary to have reliable radiation protection for safe operation of different radiation sources. Radiation shielding properties have been studied for a long time both in our country and abroad. However, there is a strong necessity to develop new composite materials, which will provide protection against radiation and have improved mechanical and economic characteristics. The paper describes a new composite material for neutron radiation shielding properties based on heavy concrete with serpentinite aggregate and with basalt-boron fiber with different concentrations of fiber boron oxide for using in biological shielding in nuclear industry. Protective properties of the new composite material were investigated with different neutron sources: 1) neutrons with 14 MeV energy; 2) fast fission neutrons for U-235; 3) fast fission neutrons for U-235 after passing a water layer. The simulation of the neutron radiation in presented composite material with adding crushed stone aggregate and serpentinite aggregate is performed by Monte Carlo Serpent code. It is shown that basalt-boron fibers in concrete improve the protective properties of concrete against neutron irradiation for neutrons with different energies, but the most effective is the addition of a basalt-boron fiber in the case of thermal neutrons. This research was supported by Horizon 2020 ERA-NET Support Programme, Research Grant Agreement No 7.9-3/18/7 (“Development of Boron-Infused Basalt-Fiber Reinforced Concrete for Nuclear and Radioactive Waste Management Applications”). Implementation of activities described in the Roadmap to Fusion during Horizon 2020 through a joint programme of the members of the EUROfusion consortium (2014-2020), Work Package PMI. Also, this research was carried out with the financial support of the IAEA, within the terms and conditions of the Research Contract20638 in the framework of the Coordinated Research Project (CRP) “Accelerator Driven Systems (ADS) Applications and Use of Low-Enriched Uranium in ADS (T33002)’’ within the Project “The Two-Zone Subcritical Systems with Fast and Thermal Neutron Spectra for Transmutation of Minor Actinides and Long-Lived Fission Products”.

scholarly journals RADIATION SHIELDING AND DOSE ASSESSMENT OF THE CYCLOTRON FACILITY AT INRNE-BAS

2021 ◽  
Vol 2021 (2/2021) ◽  
pp. 61-65
Author(s):  
Anguel Demerdjiev ◽  
Dimitar Tonev ◽  
Nikolai Goutev
Keyword(s):  
Monte Carlo ◽  
Nuclear Research ◽  
Radiation Shielding ◽  
Dose Assessment ◽  
Bulgarian Academy ◽  
Radiation Fields ◽  
Site Planning ◽  
Academy Of Sciences ◽  
Shielding Design ◽  
Monte Carlo Transport

The Institute for Nuclear Research and Nuclear Energy at the Bulgarian Academy of Sciences is working on the construction of a cyclotron centre. The facility is on a design level. At this stage of the project, an important task is the radiation shielding assessment of the facility. Nowadays, the Monte Carlo transport codes have become the tool of choice for solving this type of problem. In the current paper, the transport code FLUKA is used for the calculations. It is widely applied for shielding design and analysis of accelerators and their components. The distributions of the radiation fields inside and outside the cyclotron bunker are presented in this paper. Both different irradiation scenarios and bunker configurations are considered in the conducted Monte Carlo simulations. These results will be used as a guidance in site planning.

Permeability Measurement of High Performance Concrete at Elevated Temperature Employing a New Test Set-Up

2015 ◽  
Vol 1124 ◽  
pp. 288-293
Author(s):  
Michaela Fiedlerová ◽  
Johannes Kirnbauer ◽  
Heinrich Bruckner
Keyword(s):  
Elevated Temperature ◽  
High Performance ◽  
Building Materials ◽  
High Performance Concrete ◽  
Gas Permeability ◽  
Permeability Measurement ◽  
Test Set ◽  
Testing Procedures ◽  
Heating And Cooling ◽  
Set Up

This paper is focused on clarifying behaviour of concrete at elevated temperature with employing new test set-up constructed at Institute of Building Construction and Technology, Vienna University of Technology. This unique test set-up allows measuring gas permeability of different building materials such as concrete or ceramic at both high temperature (up to 400°C) and pressure (up to 6 bars). Present paper illustrates a new set up for permeability measurement during the heating and cooling and different testing procedures and evaluation of their influence on results.

scholarly journals Optimizing the shielding properties of strength-enhanced concrete containing marble

2020 ◽  
Vol 12 ◽  
pp. 120005
Author(s):  
Ahmed ABDEL-LATIF ◽  
Maged Kassab ◽  
M. I. Sayyed ◽  
H. O. Tekin
Keyword(s):  
Compressive Strength ◽  
Gamma Ray ◽  
Low Cost ◽  
Effective Atomic Number ◽  
Neutron Radiation ◽  
Mean Free Path ◽  
Strength Properties ◽  
Radiation Shielding ◽  
Removal Cross Section ◽  
Shielding Properties

The purpose of this study is to develop a low cost, locally produced concrete mixture with optimum marble content. The resulting mixture would have enhanced strength properties compared to the non-marble reference concrete, and improved radiation shielding properties. To accomplish these goals five concrete mixtures were prepared, containing 0, 5, 10, 15, and 20% marble waste powder as a cement replacement on the basis of weight.These samples were subjected to a compressive strength test. The shielding parameters such as mass attenuation coefficients μm, mean free path MFP, effective atomic number $Z_{eff}$ and exposure build-up factors EBF were measured, and results were compared with those obtained using the WinXcom program and MCNPX code in the photon energy range of 0.015 - 3 MeV. Moreover, the macroscopic fast neutron removal cross-section (neutron attenuation coefficient) was calculated and the results presented. The results show that the sample which contains 10% marble has the highest compressive strength and potentiallygood gamma ray and neutron radiation shielding properties.

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