Improving of characteristics of composite materials for radiation biological protection

Offered an individual protective system designed for the needs of radiation-biological protection. As the protective layer is applied the polymeric matrix composite material based on aluminum reinforced polystyrene, with the addition of particulate tungsten. The composite was made in the form of fix...

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Published in:Вопросы атомной науки и техники
Date:2013
Main Authors: Prohorenko, E.M., Klepikov, V.F., Lytvynenko, V.V., Skrypnik, A.I., Zaharchenko, A.A., Khazhmuradov, M.A.
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Language:English
Published: Національний науковий центр «Харківський фізико-технічний інститут» НАН України 2013
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Online Access:https://nasplib.isofts.kiev.ua/handle/123456789/112090
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Cite this:Improving of characteristics of composite materials for radiation biological protection / E.M. Prohorenko, V.F. Klepikov, V.V. Lytvynenko, A.I. Skrypnik, A.A. Zaharchenko, M.A. Khazhmuradov // Вопросы атомной науки и техники. — 2013. — № 6. — С. 240-243. — Бібліогр.: 6 назв. — англ.

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Digital Library of Periodicals of National Academy of Sciences of Ukraine
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author Prohorenko, E.M.
Klepikov, V.F.
Lytvynenko, V.V.
Skrypnik, A.I.
Zaharchenko, A.A.
Khazhmuradov, M.A.
author_facet Prohorenko, E.M.
Klepikov, V.F.
Lytvynenko, V.V.
Skrypnik, A.I.
Zaharchenko, A.A.
Khazhmuradov, M.A.
citation_txt Improving of characteristics of composite materials for radiation biological protection / E.M. Prohorenko, V.F. Klepikov, V.V. Lytvynenko, A.I. Skrypnik, A.A. Zaharchenko, M.A. Khazhmuradov // Вопросы атомной науки и техники. — 2013. — № 6. — С. 240-243. — Бібліогр.: 6 назв. — англ.
collection DSpace DC
container_title Вопросы атомной науки и техники
description Offered an individual protective system designed for the needs of radiation-biological protection. As the protective layer is applied the polymeric matrix composite material based on aluminum reinforced polystyrene, with the addition of particulate tungsten. The composite was made in the form of fixed-size granules with a homogeneous distribution of the filling volume. Numerical methods, the efficiency of absorption of ionizing radiation. It is shown that when the thickness of the composite material (protective layer) equal to 1 cm, absorbed all the gamma-quanta with energies up to 70 keV and 70% of the energy flux carried by gamma-quanta with energies up to 200 keV Запропоновано індивідуальний захисний комплекс, призначений для потреб радіаційно-біологічного захисту. В якості захисного прошарку застосовували полімер-матричний композиційний матеріал на основі полістиролу, армованого алюмінієм, з додаванням дрібнодисперсного вольфраму. Композит виготовлявся у вигляді гранул фіксованих розмірів з однорідним розподілом наповнення за об'ємом. За допомогою числових методів перевірена ефективність поглинання іонізуючого випромінювання. Показано, що при товщині композиційного матеріалу (захисного прошарку), рівній 1 см, поглинаються усі гама-кванти з енергією до 70 кеВ і 70% потоку енергії, який переноситься гама-квантами з енергією до 200 кеВ. Предложен индивидуальный защитный комплекс, предназначенный для нужд радиационно-биологической защиты. В качестве защитного слоя применяли полимер-матричный композиционный материал на основе полистирола, армированного алюминием, с добавлением мелкодисперсного вольфрама. Композит изготавливался в виде гранул фиксированных размеров с однородным распределением наполнения по объему. Численными методами проверена эффективность поглощения ионизирующего излучения. Показано, что при толщине композиционного материала (защитного слоя), равной 1 см, поглощаются все гамма-кванты с энергией до 70 кэВ и 70% потока энергии, переносимого гамма-квантами с энергией до 200 кэВ.
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fulltext ISSN 1562-6016. ВАНТ. 2013. №6(88) 240 IMPROVING OF CHARACTERISTICS OF COMPOSITE MATERIALS FOR RADIATION BIOLOGICAL PROTECTION E.M. Prohorenko, V.F. Klepikov, V.V. Lytvynenko, A.I. Skrypnik*, A.A. Zaharchenko*, M.A. Khazhmuradov* Institute of Electrophysics and Radiation Technologies NAS of Ukraine, Kharkov, Ukraine; *National Science Center “Kharkov Institute of Physics and Technology”, Kharkov, Ukraine Offered an individual protective system designed for the needs of radiation-biological protection. As the protec- tive layer is applied the polymeric matrix composite material based on aluminum reinforced polystyrene, with the addition of particulate tungsten. The composite was made in the form of fixed-size granules with a homogeneous distribution of the filling volume. Numerical methods, the efficiency of absorption of ionizing radiation. It is shown that when the thickness of the composite material (protective layer) equal to 1 cm, absorbed all the gamma-quanta with energies up to 70 keV and 70% of the energy flux carried by gamma-quanta with energies up to 200 keV PACS: 681.2, 615.471 INTRODUCTION The further development of nuclear power and wide application of various sources of ionizing radiation in many areas of a national economy (medicine, defectos- copy etc.) demand presence of radiation-protective ma- terials. Therefore it is impossible to diminish im- portance of questions of creation of new materials, be- havior research under radiation, control of a state of structure, manufacturing techniques development. Now in all these directions the considerable successes are reached. However, requirements shown to protection become more rigid that forces to lead operations on de- velopment of more perfect and effective protective. THE MAIN PART Under the characteristics radiation -protective mate- rials can differ on usage areas, conditions of application, a level of lowering of influence of ionizing radiation, efficiency of absorption. They can be used as stationary security facilities of the equipment and biological ob- jects, components to building materials, individual de- fense means. In our operation the materials intended for individual defense of staff, by the nature of the activity contacting to objects of the raised radiation danger were studied. The given materials can be applied at creation new and finishing of already existing individual protec- tive complexes (IPC). The main requirements shown to IPC, are: high radiation-protective properties, warmly and chemically insulating qualities, low sorption of ra- dioactive substances, the high durability, the reduced weight. Also, for functionality increase, certain flexibil- ity of a protective complex is necessary. Thus, usage of protective elements made of plates, bands, rigid frames, is irrational as reduces overall performance of attend- ants. As basic model IPC it was offered to use modified heat-insulating a waistcoat of the mine-rescuer [1]. It is necessary to carry that the given model already is made. To its advantages, it is widely exploited and can be simply enough advanced for needs of radiation biologi- cal protection. The waistcoat is equipped heat-insulating and cooling elements which allow to be about two hours, at temperature 45°С. Also, it is calculated for maintenance in chemically excited environments. Functionally, it is fitted to layout on it of additional elements in which quality elements of radiation biological protection can be used. However, the construction superimposes certain requirements, to their form and structure. Restrictions on weight of protective elements as us- age IPC implies its durable carrying are one of them. At performance by attendants of some operations mobility and flexibility is necessary. It was offered to use free- flowing materials which were located in special over- lays on a waistcoat. Application of free-flowing materi- als allows to produce protective elements with the raised flexibility, the necessary form and homogeneous for density filling. At filling usage in a free-flowing type, process of manufacture and fixing (fastening) of sepa- rate elements of protection on a waistcoat becomes sim- pler. There is a possibility to make layerwise protection. At the expense of reduction of a thickness of edge areas and their superimposing against each other it is possible to solve a simple method a question of the adjustable thickness, elements weakening ionizing radiation, in various parts IPC. That is essential to the decision of tasks of radiation protection. At a choice of a material for creation of protective elements of radiation protec- tion various variants were considered. As pacing factors posing threat are neutrons and a X-ray-scale radiation materials capable effectively first of all were considered to absorb the given types of radiations. Absorption of a flow of neutrons by most effectively light elements (B, H, N, a C, etc.) and their connections. For the decision of tasks of protection from X-ray and gamma of radia- tion on the radiation the absorbing properties heavy metals (Pb, W, Mo, etc.) well approach. Thus, required materials, having in its composition and light and heavy elements. However, products made from these materials are heavy, making them difficult to use in the IPC. For combining these resin materials are used matrix composites. Among the polymers can high- light those which possess improved ductility (non- friable), low thermal conductivity, strength, corrosion resistance and low weight. These features allow opera- tion of the polymers in a wide range of pressures, tem- peratures. They are normally applied in a vacuum may, at high pressure, corrosive environments. To avoid de- struction of polymers increased, which occurs under the influence of ionizing radiation, they are reinforced with various fillers. Given the wide range as the polymeric ISSN 1562-6016. ВАНТ. 2013. №6(88) 241 material and filling material, it is possible purposefully to obtain the necessary properties and characteristics of composite materials. Preparation of the desired proper- ties is achieved by varying the composition ratio, a dis- persion, etc. The principles of the filling Currently works on the production of polymer - composite materi- als based on different bases with a wide range of mate- rials required. In [2], a protective material comprising a matrix of aluminum-magnesium alloy (20…60%) and a filler of finely divided iron- mechanically activated hematite concentrate (40…80%). Its disadvantages in- clude low mechanical strength, due to the low compati- bility of hematite iron concentrate with metallic alumi- num. More and more attention is paid to the develop- ment of composites with filling in the form of na- nopowders. In [3] The characteristics of the protective properties, by X-ray radiation and thermal neutrons, based on the materials for ultrafine based media, which is significantly higher than conventional filling. Also were considered developed and researched in joint-stock company «Research and development and designer in- stitute of mounting technology − Atomstroj» the com- posite materials modified BN or B4C with filling tungsten [4], which effectively weaken ionizing radia- tion along with high strength and rigidity characteris- tics. It is shown that usage nano-sized powder particles of radiation- absorbing materials (BN, B4C, Pb and W) leads to magnification of coefficient of absorption of neutrons in 1.5 time and coefficient of dispersion of gamma radiation on 30…40%. In our operation radiation-protective properties pol- ymer of a composite material on the basis of polysty- rene were researched. Polystyrene usage gives the chance to lower essentially weight of a protective com- plex as because of its low heat conductivity and high thermal insulating properties necessity for layout on IPC a heat-shielding layer disappears. For obtaining of flow- ability polystyrene, was made in the form of balls in diameter from 2.5 to 5 mm. The magnification of effi- ciency of absorption of ionizing radiation was reached by adding of powder tungsten. The composite material was reinforced by aluminum. Manufacture of a compo- site material is carried out by grinding all components with the further hot extrusion that gives uniform enough allocation of particles of the filler in polystyrene. Appli- cation as the filler powder materials gives the chance to change smoothly weight and density of an aggregate and accordingly simplifies research of its properties. For estimation, efficiency of radiation-protective properties of the material offered polymer-composite, researches were led by methods of mathematical model- ing. Originally, for creation of the reference data, as ob- ject of research, pure polystyrene was used. Its thickness was 3 сm. This value was equal to a thickness of protec- tive overlays on IPC. As a composite material in the form of granules there is a possibility to select its densi- ty depending on diameter of a granule. A flow of gam- ma quanta received from a source 57Co. Results of change of a spectrum of gamma quanta from a source 57Co after passage of a layer of pure poly- styrene by them in the thickness of 3 cm received by means of methods of mathematical modeling, are pre- sented in a Fig. 1. For a line 122 keV the initial flow of gamma quanta decreases to 60.5% (55.1%), accordingly. However, because of dominance of Compton scattering for this energy easing of an initial flow of energy appears esen- tially smaller. Fig. 1. Change of a spectrum of gamma quanta, from a source 57Co, depending on energy, after passage of a layer of pure polystyrene by thickness 3 сm Proceeding from the results presented in a Fig. 1, we receive energy reduction at passage of a flow of gamma quanta through a polystyrene layer. For density of a protective layer of 1100 kg/m3 this value makes value of 87.9 % from an initial flow. With magnification of den- sity of polystyrene the amount of the last gamma quanta decreases even more and for value of density of 1300 kg/m3 makes value of 86.2% from the initial. It is necessary to pay attention on two special points on the schedule where we watch intensity races (points in the field of lines of energy 14.4 and 122 keV). Analyzing results, we receive that in the field of energies 14.4 keV, there is an easing of intensity of falling gamma quanta more than on the order. Numerically it makes: 4.7% from an initial flow for density of 1100 kg/m3, 7.5% for density of 1300 kg/m3. Thus almost all energy is ab- sorbed in a protective layer. For a line 122 keV easing of an initial flow makes almost half (60.5 and 55.1%, accordingly). But in the field of the given energies Compton scattering, therefore easing of an initial flow of energy prevails it appears much more smaller. Creation on the basis of polystyrene of a composite material with switching-on of dispersible tungsten and aluminum allows, at the same thickness, it is essential to refine efficiency of absorption of ionizing radiation. Results of the numerical account are resulted in a Fig. 2. Let's compare energetic dependences of mass trans- mission ratio of energy of gamma quanta for polysty- rene and a researched protective material. In case of polystyrene usage, the small magnification of value of this coefficient in the field of energies of gamma quanta above 100 keV is watched. Given coefficient increase it is connected to growth of section of the Compton effect [5]. Apparently from 2 schedules resulted in a Fig. 2, adding of metals (Al and W) increases more than by the order in comparison with pure polystyrene efficiency of absorption of energy of gamma quanta a composite ma- ISSN 1562-6016. ВАНТ. 2013. №6(88) 242 terial in the field of energies to 300 keV where the max- imum of the gamma radiation dispersed by environment is normally allocated. Fig. 2. Dependence of mass transmission ratio of energy (mass energy transfer coefficient) from energy of gamma quanta for a composite material At a following stage comparing of rated values of ef- ficiency of absorption of gamma quanta by layers of a protective material with various thickness was led. En- ergy of gamma quanta changed to value of 3 MeV. A thickness of a protective material varied in the range from 0.5 to 3 сm. For modeling of efficiency of absorp- tion packet Geant4 v 4.9.6p02 [6] was used. Fig. 3. Efficiency of absorption of gamma quanta layers of protection of a various thickness For thickness of polystyrene of 1 and 3 cm distinc- tion in absorption makes a maximum of 10% on all in- terval of energies from 10 keV to 3 MeV. The increase of efficiency of defence requires the increase of thick- ness of protective layer in times, that unacceptable in our case is creation of individual protective complexes. Calculation of absorbing characteristics of the offered composite material showed that at a thickness of 1 cm, a composite material absorbs all gamma quanta with en- ergy to 70 keV and more than 70% of a flow of the en- ergy transferred in gamma quanta with energy from 70 to 200 keV. Mass density of a composite material of 1 cm is almost equal in the thickness to mass density of polystyrene of 3 cm (Fig. 3). Thus efficiency of absorp- tion of gamma-quanta energy in area from 20 to 500 keV for the investigated composite is more than 2 times exceeds efficiency of absorption for radiation defence from clean polystyrene. At higher energies effi- ciency of absorption decreases, and in region 1 МeV composite material makes 10% from the general flow that is comparable with a polystyrene layer. As the free-flowing filler balls from an aggregate (Fig. 4) were applied. Fig. 4. Balls from a composite material for protective layer filling Experiments were conducted to determine the optimal size of balls required. Diameter changed in the range from 30 to 2 mm. Most effectively filled volume balls with a diameter from 3 to 8 mm. Manufacture pol- ystyrene full-spheres of such size, also, is not problem. As aggregate filling powder aluminum and tungsten were used. For uniformity of their allocation on a full- sphere body, in the heated up capacity agitation was produced. Frequency of rotation changed in the range from 10 to 90 min-1. Uniformity of allocation was checked by means of microscopy. A photo on a cutoff of the received aggregate it is presented in a Fig. 5. Fig. 5. Cutoff of a composite material The most homogeneous allocation, for the data at us the sizes of particles of aluminum and tungsten, was reached at frequency of turns of blades equal 50 min-1. Faster rotation of the warmed-up compound creates dispersion of a dispersible powder on compound edges. At slow rate happensслипание комкование aluminum filling and drop-out of a tungsten component in the low- er part. Faster rotation heated mixture produces a spread of dispersed powder mixture to the edges. At low speed sticking occurs aluminum content and the tungsten component coming into the bottom of. In picture mark- ers define separate particles. Square − aluminum parti- cles, oval − tungsten. The size of aluminum is 10…20 microns, tungsten 30…40 microns. As, balls intend for filling of plates of protection they are not exposed to physical activities. Therefore the strength characteristics (hardness, integrity), can be weakened. Thus, mi- crocracks of a material which are watched in a photo, do not render the considerable influence on necessary radi- ation protective characteristics. ISSN 1562-6016. ВАНТ. 2013. №6(88) 243 All resulted values of easing of a flow of gamma quanta are maximum. In a real case they are reduced for following reasons: gap presence between balls; mi- crocracks and cavities which are formed at pouring out; heterogeneity of allocation of aluminum and tungsten on volume of balls. CONCLUSIONS 1. For needs of radiation -biological protection usage polymer of a matrix composite material, on the basis of polystyrene reinforced by aluminum, with filling partic- ulate tungsten is offered. 2. Numerical methods, check up efficiency of ab- sorption of ionizing radiation with reference to a basis of a composite material. 3. Easing of a flow of gamma quanta at passage of a layer of a composite material is shown. 4. The form of objects of filling of elements of pro- tection is offered. 5. The aggregate structure is considered. REFERENCES 1. E.M. Prohorenko, E.L. Zavjalova, V.F. Klepikov, V.V. Kolesnikova. Perfection of isolation properties anti thermal clothes//Mountain-saving business. 2010, № 47, p. 127-133. 2. The request for the invention of the Russian Federa- tion 2001119709/06 (020835), МПК7 G21F 1/10. A composite material for radiation protec- tion / O.A. Marakin, V.I. Pavlenko, I.I. Kirijak, A.A. Lysenko, P.V. Matjuhin / the request 2001119709/06; id. 7/16/2001; publ. 2/20/2002. 3. V.A. Artemyev. About easing of X-ray radiation by the ultradispersible environments. Technologies of materials // JTF. 1997, v. 23, № 6, p. 167-175. 4. V.N. Gulbin. Development of the composite materi- als modified by nano powders, for radiation protec- tion in atomic engineering // IX All-Russia confer- ence «Physics chemistry ultradispersible (nano-) systems». Izhevsk, 2010, p. 88-95. 5. R. Nowotny. XMuDat: Photon attenuation data on PC // IAEA-NDS-195, International Atomic Energy Agency. Vienna, Austria, 1998. <http://www- nds.iaea.org/publications/iaea-nds/iaea-nds- 0195.htm>. 6. J. Allison, K. Amako, J. Apostolakis, H. Araujo, et al. Geant4 developments and applications // IEEE Transactions on Nuclear Science. 2006, v. 53, p. 270-278. Article received 11.10.2013 УЛУЧШЕНИЕ ХАРАКТЕРИСТИК КОМПОЗИЦИОННЫХ МАТЕРИАЛОВ ДЛЯ РАДИАЦИОННОЙ БИОЛОГИЧЕСКОЙ ЗАЩИТЫ Е.М. Прохоренко, В.Ф. Клепиков, В.В Литвиненко, А.И. Скрыпник, А.А. Захарченко, М.А. Хажмурадов Предложен индивидуальный защитный комплекс, предназначенный для нужд радиационно- биологической защиты. В качестве защитного слоя применяли полимер-матричный композиционный мате- риал на основе полистирола, армированного алюминием, с добавлением мелкодисперсного вольфрама. Композит изготавливался в виде гранул фиксированных размеров с однородным распределением наполне- ния по объему. Численными методами проверена эффективность поглощения ионизирующего излучения. Показано, что при толщине композиционного материала (защитного слоя), равной 1 см, поглощаются все гамма-кванты с энергией до 70 кэВ и 70% потока энергии, переносимого гамма-квантами с энергией до 200 кэВ. ПОЛІПШЕННЯ ХАРАКТЕРИСТИК КОМПОЗИЦІЙНИХ МАТЕРІАЛІВ ДЛЯ РАДІАЦІЙНО-БІОЛОГІЧНОГО ЗАХИСТУ Є.М. Прохоренко, В.Ф. Клепіков, В.В. Литвиненко, А.I. Скрипник, О.О. Захарченко, М.А. Хажмурадов Запропоновано індивідуальний захисний комплекс, призначений для потреб радіаційно-біологічного за- хисту. В якості захисного прошарку застосовували полімер-матричний композиційний матеріал на основі полістиролу, армованого алюмінієм, з додаванням дрібнодисперсного вольфраму. Композит виготовлявся у вигляді гранул фіксованих розмірів з однорідним розподілом наповнення за об'ємом. За допомогою число- вих методів перевірена ефективність поглинання іонізуючого випромінювання. Показано, що при товщині композиційного матеріалу (захисного прошарку), рівній 1 см, поглинаються усі гама-кванти з енергією до 70 кеВ і 70% потоку енергії, який переноситься гама-квантами з енергією до 200 кеВ. Introduction The main part Conclusions References
id nasplib_isofts_kiev_ua-123456789-112090
institution Digital Library of Periodicals of National Academy of Sciences of Ukraine
issn 1562-6016
language English
last_indexed 2025-12-07T16:22:46Z
publishDate 2013
publisher Національний науковий центр «Харківський фізико-технічний інститут» НАН України
record_format dspace
spelling Prohorenko, E.M.
Klepikov, V.F.
Lytvynenko, V.V.
Skrypnik, A.I.
Zaharchenko, A.A.
Khazhmuradov, M.A.
2017-01-17T15:28:56Z
2017-01-17T15:28:56Z
2013
Improving of characteristics of composite materials for radiation biological protection / E.M. Prohorenko, V.F. Klepikov, V.V. Lytvynenko, A.I. Skrypnik, A.A. Zaharchenko, M.A. Khazhmuradov // Вопросы атомной науки и техники. — 2013. — № 6. — С. 240-243. — Бібліогр.: 6 назв. — англ.
1562-6016
PACS: 681.2, 615.471
https://nasplib.isofts.kiev.ua/handle/123456789/112090
Offered an individual protective system designed for the needs of radiation-biological protection. As the protective layer is applied the polymeric matrix composite material based on aluminum reinforced polystyrene, with the addition of particulate tungsten. The composite was made in the form of fixed-size granules with a homogeneous distribution of the filling volume. Numerical methods, the efficiency of absorption of ionizing radiation. It is shown that when the thickness of the composite material (protective layer) equal to 1 cm, absorbed all the gamma-quanta with energies up to 70 keV and 70% of the energy flux carried by gamma-quanta with energies up to 200 keV
Запропоновано індивідуальний захисний комплекс, призначений для потреб радіаційно-біологічного захисту. В якості захисного прошарку застосовували полімер-матричний композиційний матеріал на основі полістиролу, армованого алюмінієм, з додаванням дрібнодисперсного вольфраму. Композит виготовлявся у вигляді гранул фіксованих розмірів з однорідним розподілом наповнення за об'ємом. За допомогою числових методів перевірена ефективність поглинання іонізуючого випромінювання. Показано, що при товщині композиційного матеріалу (захисного прошарку), рівній 1 см, поглинаються усі гама-кванти з енергією до 70 кеВ і 70% потоку енергії, який переноситься гама-квантами з енергією до 200 кеВ.
Предложен индивидуальный защитный комплекс, предназначенный для нужд радиационно-биологической защиты. В качестве защитного слоя применяли полимер-матричный композиционный материал на основе полистирола, армированного алюминием, с добавлением мелкодисперсного вольфрама. Композит изготавливался в виде гранул фиксированных размеров с однородным распределением наполнения по объему. Численными методами проверена эффективность поглощения ионизирующего излучения. Показано, что при толщине композиционного материала (защитного слоя), равной 1 см, поглощаются все гамма-кванты с энергией до 70 кэВ и 70% потока энергии, переносимого гамма-квантами с энергией до 200 кэВ.
en
Національний науковий центр «Харківський фізико-технічний інститут» НАН України
Вопросы атомной науки и техники
Применение ускоренных пучков. Детекторы и детектирование ядерных излучений
Improving of characteristics of composite materials for radiation biological protection
Поліпшення характеристик композиційних матеріалів для радіаційно-біологічного захисту
Улучшение характеристик композиционных материалов для радиационной биологической защиты
Article
published earlier
spellingShingle Improving of characteristics of composite materials for radiation biological protection
Prohorenko, E.M.
Klepikov, V.F.
Lytvynenko, V.V.
Skrypnik, A.I.
Zaharchenko, A.A.
Khazhmuradov, M.A.
Применение ускоренных пучков. Детекторы и детектирование ядерных излучений
title Improving of characteristics of composite materials for radiation biological protection
title_alt Поліпшення характеристик композиційних матеріалів для радіаційно-біологічного захисту
Улучшение характеристик композиционных материалов для радиационной биологической защиты
title_full Improving of characteristics of composite materials for radiation biological protection
title_fullStr Improving of characteristics of composite materials for radiation biological protection
title_full_unstemmed Improving of characteristics of composite materials for radiation biological protection
title_short Improving of characteristics of composite materials for radiation biological protection
title_sort improving of characteristics of composite materials for radiation biological protection
topic Применение ускоренных пучков. Детекторы и детектирование ядерных излучений
topic_facet Применение ускоренных пучков. Детекторы и детектирование ядерных излучений
url https://nasplib.isofts.kiev.ua/handle/123456789/112090
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