170 research outputs found
Investigation of different versions of formulation of the problem of soundproofing of rectangular plates surrounded with acoustic media
© 2017 Springer Science+Business Media New York. We consider five different formulations of the stationary problem of passage of plane acoustic waves through a rectangular plate. The first of these formulations corresponds to the application of the inertial mass model based on the hypothesis of the nondeformability of a nonfixed rigid plate in the course of its interaction with incident and plane acoustic waves formed in the surrounding half spaces. The other four statements correspond to taking into account (according to the model of the Winkler base) or neglecting the compliance of the support contour of a hingedly supported rectangular plate deformed according to the Kirchhoff model and to the application one-or three-dimensional wave equations for the description of motions of the acoustic media and the construction of the equation of motion of the plate with regard for its certain external damping. The use of these last four statements enables us to obtain smoothened graphic frequency dependences whose shapes agree with the experimental dependences obtained by testing specimens in the acoustic laboratory aimed at finding the soundproofing index of the plate
Investigation of Different Versions of Formulation of the Problem of Soundproofing of Rectangular Plates Surrounded with Acoustic Media
© 2016 Springer Science+Business Media New YorkWe consider five different formulations of the stationary problem of passage of plane acoustic waves through a rectangular plate. The first of these formulations corresponds to the application of the inertial mass model based on the hypothesis of the nondeformability of a nonfixed rigid plate in the course of its interaction with incident and plane acoustic waves formed in the surrounding half spaces. The other four statements correspond to taking into account (according to the model of the Winkler base) or neglecting the compliance of the support contour of a hingedly supported rectangular plate deformed according to the Kirchhoff model and to the application one- or three-dimensional wave equations for the description of motions of the acoustic media and the construction of the equation of motion of the plate with regard for its certain external damping. The use of these last four statements enables us to obtain smoothened graphic frequency dependences whose shapes agree with the experimental dependences obtained by testing specimens in the acoustic laboratory aimed at finding the soundproofing index of the plate
METROLOGICAL SUPPORT OF DOSIMETRY GAMMA-RAY WITH ENERGY TO 10 MEV FOR RADIATION PROTECTION DEVICES
The field of high-energy gamma-ray for the calibration of radiation protection devices can be obtained by capturing thermal neutrons from titanium target (to 7 MeV) and nickel target (to 10 MeV). The aim of this work was to determine the metrological characteristics of capture gamma-ray fields from titanium target and nickel target obtained at the AT140 Neutron Calibration Facility to provide dosimetry up to 10 MeV.We have chosen energy intervals in which we can calibrate dosimetry devices taking into account the accompanying generation of gamma-ray neutrons by the fast neutron source 238PuBe, the capture radiation of collimator materials and capture radiation from targets.We measured air kerma rate with the aid of the reference AT5350 dosimeter with the ionization chamber TM32002. Using the Monte-Carlo simulation, we obtained the energy distribution of the air kerma rate for targets. We determined the geometric dimensions of the uniform field and the interval of operating distances of the facility.We investigated the metrological characteristics of capture gamma-ray fields from titanium target and nickel target obtained at the AT140 Neutron Calibration Facility for dosimetric radiation protection devices. We showed that in such fields it is possible to calibrate dosimetry devices in the extended energy range up to 10 MeV
Determinant Structure of the Rational Solutions for the Painlev\'e IV Equation
Rational solutions for the Painlev\'e IV equation are investigated by Hirota
bilinear formalism. It is shown that the solutions in one hierarchy are
expressed by 3-reduced Schur functions, and those in another two hierarchies by
Casorati determinant of the Hermite polynomials, or by special case of the
Schur polynomials.Comment: 19 pages, Latex, using theorem.st
The Hamiltonian Structure of the Second Painleve Hierarchy
In this paper we study the Hamiltonian structure of the second Painleve
hierarchy, an infinite sequence of nonlinear ordinary differential equations
containing PII as its simplest equation. The n-th element of the hierarchy is a
non linear ODE of order 2n in the independent variable depending on n
parameters denoted by and . We introduce new
canonical coordinates and obtain Hamiltonians for the and
evolutions. We give explicit formulae for these Hamiltonians showing that they
are polynomials in our canonical coordinates
Rational Solutions of the Painleve' VI Equation
In this paper, we classify all values of the parameters , ,
and of the Painlev\'e VI equation such that there are
rational solutions. We give a formula for them up to the birational canonical
transformations and the symmetries of the Painlev\'e VI equation.Comment: 13 pages, 1 Postscript figure Typos fixe
ИСТОЧНИК ЗАХВАТНОГО ГАММА-ИЗЛУЧЕНИЯ С ЭНЕРГИЯМИ ДО 7 МэВ И ДО 10 МэВ НА ОСНОВЕ ПОВЕРОЧНОЙ УСТАНОВКИ НЕЙТРОННОГО ИЗЛУЧЕНИЯ
Wide spread of technogenic sources of ionizing radiation such as particle accelerators and nuclear reactors leads to appearance of a number of applied metrological tasks aimed at providing spectrometric and dosimetric ionization measurement instruments, located in photon radiation fields with energy to 10 MeV. Gamma rays with energy higher 3 MeV may be acquired using radioactive thermal neutron capture on target, i.e. (n, γ)-nuclear reaction. Titanium is used in the range of energies to 7 MeV; nickel – to 10 MeV. A simplest source of instantaneous neutron capture gamma-ray should consist of fast neutron source, neutron moderator and a target irradiated with thermal neutrons. The collimator with thermal neutron geometry of АТ140 neutron calibration facility with 238Pu–Be fast neutron source may be used (IBN–8–6) as a source of gamma-ray with energy to 10 MeV. Monte-Carlo models of thermal neutrons geometry, facility and 238Pu–Be fast neutron source were built using MCNP–4b code. Energy distribution of flux density of neutron capture gamma–ray for titanium and nickel targets was defined. A spectrometric detector based on LaBr3(Ce) crystal Ø 38×38 mm with non-linear characteristics of channel-energy transformation in the range up to 10 MeV, was specifically manufactured for instrumental support of the experiment at SPE “ATOMTEX”. The results for Ti, Ni, and for bare 238Pu–Be neutron source were acquired. During the experiment a possibility to use neutron capture gamma-ray field formed by thermal neutrons geometry of АТ140 neutron calibration facility with 238Pu–Be-fast neutron source with Ti and Ni targets for calibration LaBr3(Ce) spectrometers for energy to 10 MeV was confirmed. Closely stationing polyethylene plate in collimator channel provides significant increase in output of reference radiation from target simultaneously decreasing unneeded parts of the spectrum. Широкое распространение и использование техногенных источников ионизирующих излучений, в частности таких, как ускорители заряженных частиц и ядерные реакторы, приводит к появлению ряда прикладных задач по метрологическому обеспечению спектрометрической и дозиметрической аппаратуры, работающей в полях фотонного излучения с энергией до 10 МэВ. Контейнер-коллиматор с геометрией тепловых нейтронов установки поверочной нейтронного излучения (УПН- АТ140, УП «АТОМТЕХ») формирует коллимированный пучок нейтронов со значительной составляющей нейтронов тепловых энергий. Расположение в потоке тепловых нейтронов диска из титана позволяет получить поле захватного гамма-излучения до 7 МэВ, а диска из никеля – до 10 МэВ. Для экспериментального изучения спектральных характеристик поля захватного излучения использовался специализированный спектрометрический блок детектирования на основе кристалла LaBr3(Ce) с размерами Ø 38×38 мм с нелинейной характеристикой преобразования канал-энергия в диапазоне до 10 МэВ. На спектрах хорошо различимы основные линии захватного излучения от водорода, бора, титана и никеля. По полученным на блоке детектирования спектрам можно сделать вывод о возможности калибровки спектрометрических блоков в поле захватного гамма-излучения до 10 МэВ.
ФОРМИРОВАНИЕ ПОЛЯ ЗАХВАТНОГО ГАММА-ИЗЛУЧЕНИЯ ДО 10 МэВ ДЛЯ МЕТРОЛОГИЧЕСКОГО ОБЕСПЕЧЕНИЯ ПРИБОРОВ РАДИАЦИОННОЙ ЗАЩИТЫ
Medical, and technological linear particle accelerators, and nuclear reactors are vastly widespread worldwide today. These facility generate fields of secondary gamma radiation with energy to 10 MeV. Therefore, we have a need to calibrate spectrometric and dosimetric ionization measurement instruments for the energies to 10 MeV. The aim of this work is to determine possibility to use thermal neutron collimator of АТ140 Neutron Calibration Facility with 238Pu-Be fast neutron source (IBN-8-6) for this. Below 3 MeV we use a set of point gamma standard spectrometry sources OSGI. We can acquire gamma rays with energies above 3 MeV using radioactive thermal neutron capture on target, i.e. (n, γ)-nuclear reaction. We can use neutron capture gamma-ray from titanium target (to 7 MeV) or nickel target (to 10 MeV) situated in thermal neutron field for calibration. We can use thermal neutron collimator of АТ140 Neutron Calibration Facility with 238Pu-Be fast neutron source (IBN-8-6) for slowing down neutrons from radionuclide fast neutron sources to thermal energies in polyethylene. Thermal neutron collimator forms a beam from radionuclide source with a significant amount of neutrons with thermal energies. We placed Ti and Ni targets in collimator’s canal. We got experimental spectral data on detection unit BDKG-19M NaI(Tl) 63 × 160 mm with nonlinear channel-energy conversion characteristic in range to 10 MeV. For additional filtration we proposed to use polyethylene neutron reflector and lead discs. We experimentally determined that placement of lead discs in collimator in front of the target allows to filter all spectrum while insignificantly weakening target’s emission. Using theoretical and experimental data we proved the ability to calibrate gamma-ray spectrometers in the range to 10 MeV. Развитие и распространение техногенных источников высокоэнергетического вторичного гаммаизлучения приводит к ряду прикладных задач радиационной защиты, в которых спектрометрические и дозиметрические измерительные приборы используются в фотонных полях в диапазоне энергий от 4 до 10 МэВ. Целью данной работы являлась проверка возможности формирования эталонных полей захватного гамма-излучения при помощи источника быстрых нейтронов и мишеней из титана и никеля с энергиями до 10 МэВ. Корректная калибровка предполагает наличие в эталонном спектре излучения одиночных линий с известной энергией. До 3 МэВ задача решается при помощи набора радионуклидных источников ОСГИ. Для формирования эталонного фотонного поля с энергиями до 10 МэВ можно использовать захватное гамма-излучение от мишеней из титана и никеля, находящихся в поле тепловых нейтронов. Поток нейтронов с тепловыми энергиями может быть получен замедлением быстрых нейтронов от радионуклидных источников 238Pu-Be, 252Cf, 241Am-Be. В качестве замедлителя нейтронов обычно используются водородосодержащие материалы (полиэтилен и парафин). Коллиматор тепловых нейтронов установки поверочной нейтронного излучения (УПН-АТ140, УП «АТОМТЕХ») формирует пучок от радионуклидного источника со значительной составляющей нейтронов тепловых энергий. Размещение мишеней в канале коллиматора позволило получить поле гамма-излучения с характерными для материала мишени энергиями. Экспериментальные спектры получены на спектрометрическом блоке детектирования БДКГ-19М NaI(Tl) 63 × 160 мм с нелинейной характеристикой преобразования канал-энергия в диапазоне до 10 МэВ. На спектрах хорошо различимы основные линии захватного излучения от водорода, титана и никеля. В качестве дополнительной фильтрации предложено использовать отражатель нейтронов из полиэтилена и свинцовые диски. Показано, что размещение дисков из свинца в коллиматоре перед мишенью позволяет фильтровать весь спектр, при этом незначительно ослабляя излучение именно от мишени. На основании теоретических и экспериментальных данных подтверждена возможность калибровки спектрометров гамма-излучения в диапазоне до 10 МэВ в поле мгновенного захватного гамма-излучения.
Mesozoic fossils (>145 Mya) suggest the antiquity of the subgenera of Daphnia and their coevolution with chaoborid predators
<p>Abstract</p> <p>Background</p> <p>The timescale of the origins of <it>Daphnia </it>O. F. Mueller (Crustacea: Cladocera) remains controversial. The origin of the two main subgenera has been associated with the breakup of the supercontinent Pangaea. This vicariance hypothesis is supported by reciprocal monophyly, present day associations with the former Gondwanaland and Laurasia regions, and mitochondrial DNA divergence estimates. However, previous multilocus nuclear DNA sequence divergence estimates at < 10 Million years are inconsistent with the breakup of Pangaea. We examined new and existing cladoceran fossils from a Mesozoic Mongolian site, in hopes of gaining insights into the timescale of the evolution of <it>Daphnia</it>.</p> <p>Results</p> <p>We describe new fossils of ephippia from the Khotont site in Mongolia associated with the Jurassic-Cretaceous boundary (about 145 MYA) that are morphologically similar to several modern genera of the family Daphniidae, including the two major subgenera of <it>Daphnia</it>, i.e., <it>Daphnia </it>s. str. and <it>Ctenodaphnia</it>. The daphniid fossils co-occurred with fossils of the predaceous phantom midge (Chaoboridae).</p> <p>Conclusions</p> <p>Our findings indicate that the main subgenera of <it>Daphnia </it>are likely much older than previously known from fossils (at least 100 MY older) or from nuclear DNA estimates of divergence. The results showing co-occurrence of the main subgenera far from the presumed Laurasia/Gondwanaland dispersal barrier shortly after formation suggests that vicariance from the breakup of Pangaea is an unlikely explanation for the origin of the main subgenera. The fossil impressions also reveal that the coevolution of a dipteran predator (Chaoboridae) with the subgenus <it>Daphnia </it>is much older than previously known -- since the Mesozoic.</p
МЕТРОЛОГИЧЕСКОЕ ОБЕСПЕЧЕНИЕ ДОЗИМЕТРИИ ГАММА-ИЗЛУЧЕНИЯ С ЭНЕРГИЕЙ ДО 10 МЭВ ДЛЯ ПРИБОРОВ РАДИАЦИОННОЙ ЗАЩИТЫ
The field of high-energy gamma-ray for the calibration of radiation protection devices can be obtained by capturing thermal neutrons from titanium target (to 7 MeV) and nickel target (to 10 MeV). The aim of this work was to determine the metrological characteristics of capture gamma-ray fields from titanium target and nickel target obtained at the AT140 Neutron Calibration Facility to provide dosimetry up to 10 MeV.We have chosen energy intervals in which we can calibrate dosimetry devices taking into account the accompanying generation of gamma-ray neutrons by the fast neutron source 238PuBe, the capture radiation of collimator materials and capture radiation from targets.We measured air kerma rate with the aid of the reference AT5350 dosimeter with the ionization chamber TM32002. Using the Monte-Carlo simulation, we obtained the energy distribution of the air kerma rate for targets. We determined the geometric dimensions of the uniform field and the interval of operating distances of the facility.We investigated the metrological characteristics of capture gamma-ray fields from titanium target and nickel target obtained at the AT140 Neutron Calibration Facility for dosimetric radiation protection devices. We showed that in such fields it is possible to calibrate dosimetry devices in the extended energy range up to 10 MeV. Поле высокоэнергетического захватного гамма-излучения для калибровки приборов радиационной защиты можно получить в результате захвата тепловых нейтронов на мишенях из титана (до 7 МэВ) и никеля (до 10 МэВ). Целью данной работы являлось исследование полей захватного гаммаизлучения от мишеней из титана и никеля, полученных с использованием облучателя поверочной установки нейтронного излучения УПН-АТ140 для обеспечения дозиметрии до 10 МэВ.В ходе работы определены энергетические интервалы, в которых можно калибровать дозиметрические приборы с учетом сопутствующего выходу нейтронов источника 238PuBe гамма-излучения захватного излучения материалов коллиматора и захватного излучения от мишеней.Для измерения мощности кермы в воздухе гамма-излучения использовался эталонный дозиметр ДКС-АТ5350 с ионизационной камерой ТМ32002. С помощью Монте-Карло моделирования получено энергетическое распределение мощности кермы в воздухе для мишеней. Установлены геометрические размеры равномерного поля и интервал рабочих расстояний установки.Исследованы характеристики полей захватного излучения от мишеней из титана и никеля, полученных на поверочной установке нейтронного излучения УПН-АТ140 с целью метрологического обеспечения дозиметрических приборов радиационной защиты. Показана возможность проведения калибровки дозиметрических приборов в таких полях в расширенном энергетическом диапазоне до 10 МэВ.
- …