Weakening of neutron and gamma radiation from radioisotope sources by material based on modified titanium hydride

2021 ◽  
Vol 9 ◽  
pp. 24-33
Author(s):  
R. N. Yastrebinsky ◽  
◽  
G. G. Bondarenko ◽  
A. A. Karnauhov ◽  
◽  
...  
Keyword(s):  
Gamma Radiation ◽  
Titanium Hydride ◽  
Experimental Studies ◽  
Calculated Data ◽  
Neutron Radiation ◽  
Amplitude Distribution ◽  
Fast Neutrons ◽  
Protective Properties ◽  
The Monte Carlo Method ◽  
Mcnp Program

The paper presents experimental studies of the radiation-protective properties of a material based on a modified titanium hydride with respect to gamma and neutron radiation of point radioisotope sources in barrier and continuous protection geometries. The calculated models of the problem of solving the radiation transfer equation for the Monte Carlo method and a comparative assessment of experimental and calculated results is given. The assessment of the amplitude distribution of gamma radiation in the thickness of the material of protection showed a significant reduction in the power of the equivalent dose of radiation gamma in the energy range of 180 – 250 keV, which is due to the effect of the Compton dispersion. The length relaxation of the dose of γ-radiation in 137Сs by the security material was 4.80 ± 0.18 cm. The length of the density relaxation of fast neutrons from the Pu-α-Be source was 6.20 ± 0.18 cm. Comparative analysis of the experimental and calculated data of the protective properties of the material based on modified titanium hydride In relation to radioisotope sources, showed high convergence of the results obtained and the adequacy of the application of the settlement model of the task for the MCNP program used.

Experimental Studies of Radiation-Protective Properties of a Modified Titanium Hydride

2022 ◽  
Vol 1049 ◽  
pp. 174-179
Author(s):  
A.A. Karnauhov ◽  
R.N. Yastrebinskii
Keyword(s):  
Gamma Radiation ◽  
Dose Rate ◽  
Titanium Hydride ◽  
Nuclear Power ◽  
Power Plants ◽  
High Efficiency ◽  
Experimental Studies ◽  
Point Sources ◽  
Relaxation Length ◽  
Protective Properties

The results of experimental studies of the protective properties of titanium hydride with respect to neutron and gamma radiation in order to determine the optimal conditions for their use in the composition of the structural radiation protection of the nuclear reactor are presented. The weakening of the basic functionals in the thickness of protection, including the density of fast, intermediate and thermal neutrons, and the dose rate of gamma radiation is established. The functions of weakening the density of neutron flow and the dose rate of gamma radiation are measured in the conditions of "barrier" geometry. Determination of the protective properties of the structure was carried out when the modified titanium hydride fraction was placed in aluminum containers with a filling coefficient of a volume of container 0.63. The relaxation lengths for all neutron groups are close and on average are 9.8 cm. The functions of weakening the dose rate of gamma radiation of point sources Cs-137 and Co-60 are exponential. The weakening of radiation occurs with a constant relaxation length. For energy 0.661 MeV, the relaxation length is 7.1 cm, for energy 1.25 MeV, the relaxation length is equal to 10.1 cm. On the basis of the experimental studies, the high efficiency of the modified fraction of titanium hydride was confirmed during its use in protecting nuclear power plants.

scholarly journals MULTI-GROUP MODELING OF PROTECTION AGAINST NEUTRON AND GAMMA RADIATION BY MATERIALS BASED ON TITANIUM HYDRIDE

2020 ◽  
pp. 119-124
Author(s):  
Roman N. Yastrebinsky ◽  
Alexander A. Karnaukhov
Keyword(s):  
Gamma Radiation ◽  
Gamma Rays ◽  
Titanium Hydride ◽  
High Efficiency ◽  
Neutron Radiation ◽  
Fast Neutrons ◽  
Protective Efficiency ◽  
Relaxation Length ◽  
Group Modeling ◽  
Neutron Flux Density

The paper provides a comparative calculation of the radiation protective efficiency of various composite materials based on titanium hydride using multi-group modeling methods using the ANISN program. The calculations showed the high efficiency of titanium hydride composites with respect to neutron and gamma radiation. The relaxation length of the fast neutron flux density in titanium hydride materials is 5.1…7.0 cm. The spatial-energy distribution of neutron radiation in materials is formed by fast neutrons. The dose rate of gamma rays behind the material is determined mainly by capturing gamma rays arising in the initial layer of protection. Introduction to the composition of the protection of boron atoms reduces the level of capture gamma radiation, but does not affect the attenuation of fast neutrons.

Polymers in Concrete – The Shielding against Neutron Radiation

2015 ◽  
Vol 1129 ◽  
pp. 131-138 ◽  
Author(s):  
Tomasz Piotrowski ◽  
Dariusz B. Tefelski ◽  
Michał Mazgaj ◽  
Janusz Skubalski ◽  
Andrzej Żak ◽  
...  
Keyword(s):  
Monte Carlo ◽  
Monte Carlo Simulations ◽  
Experimental Studies ◽  
Neutron Radiation ◽  
High Energy ◽  
Fast Neutrons ◽  
Final Conclusion ◽  
Concrete Technology ◽  
Neutron Shielding ◽  
Neutron Attenuation

Concrete has been used as a shield against high-energy photons (gamma) and neutrons since the beginning of use of nuclear reaction in energy, medicine and research. State of knowledge in shielding concrete technology is that while in case of protection against gamma radiation an increase in density caused by change of aggregate type for heavy-weight one is usually an efficient solution, the 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 cross-sections for different reactions of the component atoms of the cement paste and the aggregate. The paper presents the results of the project NGS-Concrete - New-Generation Shielding Concrete. The aim is to design the composition of concrete against ionizing radiation, achieved by the use of experiment based on multi-criteria optimization of materials supported by the Monte Carlo simulations. Better concrete is the one that absorbs more thermal neutrons and slows down more fast neutrons at the same time. In the paper both results of Monte Carlo simulations and experimental studies on ordinary and heavyweight concrete containing epoxy polymer additive are presented. Close values of thermal neutron attenuation coefficients proved good accordance between simulation and experiment. The final conclusion is that epoxy resin is an efficient additive for neutron shielding concretes improving its ability to protect mainly against low energy neutrons. In experimental measurement there has not been observed an improvement of fast neutron attenuation due to increase of hydrogen atom content introduced with epoxy.

scholarly journals THE STUDY OF PHYSICAL PROCESSES AND THE OPTIMIZATION OF THE COMPOSITION OF THE RADIATION-SHIELD LAYER OF THE PRODUCT PKN-1A

2020 ◽  
pp. 97-104
Author(s):  
Y.V. Rudychev ◽  
S.I. Prokhorets ◽  
M.A. Khazhmuradov
Keyword(s):  
Experimental Studies ◽  
Three Dimensional ◽  
Neutron Radiation ◽  
Point Of View ◽  
Fast Neutrons ◽  
Radiation Shield ◽  
Physical Processes ◽  
Three Dimensional Model ◽  
Equivalent Dose Rate ◽  
Good Agreement

The work is devoted to the analysis of the transportation features of isotopic fast neutrons sources from the point of view of the used radiation-shield materials and their compositions. A three-dimensional model of the portable container of the packaging set PKN-1A was developed, and neutron irradiation of the container was simulated under conditions of transportation of the neutron source IBN-8-5. The equivalent dose rate (EDR) values on the surface of containers with different composition of the radiation-shield material are calculated. Experimental studies of the EDR attenuation of neutron radiation from isotopic sources of fast neutrons for samples of various radiation-shield material compositions have been carried out. The results of mathematical modeling are in good agreement with experimental data.

Experimental and Analytical Assessment of the Power Parameters of the Combined Rolling-Extruding Process Using a Round Billet from Alloy 01417 Obtained Using an Electromagnetic Mold

2021 ◽  
Vol 887 ◽  
pp. 300-305
Author(s):  
S. Sidelnikov ◽  
D. Voroshilov ◽  
M. Motkov ◽  
V. Bespalov ◽  
M. Voroshilova
Keyword(s):  
Experimental Studies ◽  
Calculated Data ◽  
Laboratory Unit ◽  
Round Billet ◽  
Power Load ◽  
Industrial Unit ◽  
Analytical Assessment

Analytical and experimental studies have been carried out, which made it possible to propose new technological modes of combined rolling-extruding for the production of rods from alloy 01417 for the further drawing of wire for electrical purposes. The force parameters on the rolls and the die are calculated when extruding a rod with a diameter of 5 mm on the laboratory unit CRE-200 and the industrial unit CRE-400. The obtained values of the forces on the rolls and the die do not exceed the permissible values of the power load of the units. Therefore the selected parameters are suitable for conducting experiments on the manufacture of prototypes of rods. To verify the conclusions made, experimental studies were carried out on the CRE-200 unit at a temperature of 320 oC and a drawing coefficient μ = 12.1. The results of experimental studies in comparison with the calculated data showed that the deviation of the calculated data does not exceed 15%.

Neutron Radiation Effects on Lubricants and O-Rings for Target and Accelerator Applications

2021 ◽  
Vol 1024 ◽  
pp. 127-133
Author(s):  
Matteo Ferrari ◽  
Aldo Zenoni ◽  
Yong Joong Lee ◽  
Alberto Andrighetto
Keyword(s):  
Gamma Radiation ◽  
Radiation Damage ◽  
Radiation Effects ◽  
Nuclear Reactor ◽  
Neutron Radiation ◽  
Radioactive Isotopes ◽  
Structural Level ◽  
Radiation Resistant ◽  
Under Construction ◽  
Neutron Radiation Effects

Lubricants and O-rings are necessarily used for the construction of many accelerator-driven facilities as spallation sources or facilities for the production of radioactive isotopes. During operation, such component will absorb high doses of mixed neutron and gamma radiation, that can degrade their mechanical and structural properties. Experimental radiation damage tests of these components are mandatory for the construction of the facility. Methodologies for irradiation in nuclear reactor mixed fields and post-irradiation examination of lubricating oils, greases and O-rings were developed and are here presented. Samples were characterized with standard mechanical and physical-chemical tests. Parametric studies on the dose rate effects have been performed on O-rings. A case studies for a specific O-ring application in a gate valve has been developed. Some of the tested samples showed a dramatic change of their properties with dose, while others remain stable. Results were collected on nine commercial greases, on one oil and on four commercial elastomeric O-rings. The most radiation resistant among the selected products are now considered for application in facilities under construction. The main mechanisms of neutron and gamma radiation damage on these polymers were investigated at the mechanical and structural level.

Strength and Deformation of Combined Beams with Side Reinforced Plates

2019 ◽  
Vol 968 ◽  
pp. 234-239
Author(s):  
Talyat Azizov ◽  
Oleksii Melnik ◽  
Oleksandr Myza
Keyword(s):  
Experimental Data ◽  
Reinforced Concrete ◽  
Experimental Studies ◽  
Calculated Data ◽  
Concrete Plate ◽  
Combined Action ◽  
Strength And Deformation ◽  
Concrete Plates ◽  
Good Agreement

The results of experimental studies of combined beams consisting of a stone part, reinforced with side reinforced concrete plates are given. Experimentally shown the viability of the proposed structures. The conditions for ensuring the combined action of a stone beam and a reinforced concrete plate are given. Cases are shown when one-sided plates can be used and when double-sided reinforced concrete plates can be used. A comparison of experimental data with the data calculated by the authors developed methods is given. A good agreement between theoretical and calculated data is shown.

scholarly journals The gasoline vapors spread from “small” spills in an urban environment at low wind speeds

2020 ◽  
Vol 164 ◽  
pp. 01006
Author(s):  
Ruslan Khrestenko ◽  
Ekaterina Sokolova ◽  
Dmitrii Okulovsky ◽  
Valeri Azarov
Keyword(s):  
Wind Speed ◽  
Urban Environment ◽  
Surface Area ◽  
Experimental Studies ◽  
Calculated Data ◽  
Hazardous Substances ◽  
Ethyl Benzene ◽  
Atmospheric Air ◽  
Wind Speeds ◽  
Low Wind Speeds

It is noted that the urban environment is polluted by oil products; in particular, there is a large pollution of atmospheric air. It is indicated that one of the pollution sources is the “small” spills, which are characteristic of urban areas. Experimental studies have been carried out on the gasoline distribution in atmospheric air at “small” spills. A single experiment at a low wind speed is considered. Data were obtained on the dependence of gasoline concentration in atmospheric air on the distance from the spill, the height above the level of the spill and the time of the spill. The component composition was studied using chromatographic studies. It is indicated that the distribution of gasoline vapors in the atmosphere is influenced by the ambient temperature, wind speed, surface area of the spill, time from the moment of spilling and the distance above the level of the spill. The gasoline dispersion in atmospheric air was calculated with the software using experimental and calculated data on the surface area of the spill. It is indicated that at low wind speeds (up to 0.5 m/s) from “small” spills of gasoline (up to 3 liters), significant excesses of standards for the content of harmful substances in the atmospheric air can be observed. It was determined that during spilling there is an excess of maximum permissible concentrations of single, hazardous substances such as ethyl benzene, m-xylene and amyl alcohol in the air.

scholarly journals Experimental studies on changes in mechanical properties of polymer composites under impact of thermal load determined based on compression testing

2018 ◽  
Vol 247 ◽  
pp. 00027
Author(s):  
Agata Walczak ◽  
Ireneusz Naworol ◽  
Daniel Pieniak ◽  
Kamil Pasierbiewicz ◽  
Grzegorz Dzień
Keyword(s):  
Mechanical Properties ◽  
Polymer Composites ◽  
Thermal Load ◽  
Experimental Studies ◽  
Thermal Exposure ◽  
Protective Properties ◽  
Trade Name ◽  
Young Module ◽  
In Fire ◽  
Compressive Tests

The objective of the study was to carry out an analysis of changes in mechanical properties of polymer composites in conditions of thermal load. Such an analysis may allow an initial verification of possibilities of deploying new composites in production of fire helmet shells. The reference material chosen for testing was the Ultramid composite, which is currently used for the production of fire helmet shells. In addition three different materials were selected that contained reinforcement by glass fibres bearing the trade name of Tarnamid, which are not used in manufacturing of shells. Testing was conducted in conditions of quasi-static load, during which compressive tests were performed. Mechanical loads were applied at different levels of thermal exposure, which was to simulate presence in fire conditions. Results of tests indicated that the Tarnamid composites are characterised by better compressive strength and rigidity determined on the basis of the Young module value than Ultramid PA66 GF25 used in the production of head protective shells. It has also been proven that thermal loads contribute to significant degradation in strength and rigidity of tested materials, which affects adversely protective properties of the helmet.

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