Measurement of the forming limit stress curve using a multi-axial tube expansion test
with a digital image correlation system http://dx.doi.org/10.1063/1.4850053 by Hakoyama, Tomoyuki (Department of Mechanical Systems Engineering, Graduate school
of Engineering, Tokyo University of Agriculture and Technology, 2-24-16, Nakacho,
Koganei-shi, Tokyo, 184-8588 (Japan)); Kuwabara, Toshihiko (Division of Advanced Mechanical
Systems Engineering, Institute of Engineering, Tokyo University of Agriculture and
Technology, 2-24-16, Nakacho, Koganei-shi, Tokyo, 184-8588 (Japan)) Read MoreCollapse
[en]
A servo-controlled tension-internal pressure testing machine with an optical 3D deformation
analysis system (ARAMIS) was used to measure the multi-axial plastic deformation behavior
of a high-strength steel sheet for a range of strain from initial yield to fracture.
The testing machine is capable of applying arbitrary principal stress or strain paths
to a tubular specimen using an electrical, closed-loop servo-control system for axial
force and internal pressure. Tubular specimens with an inner diameter of 44.6 mm were
fabricated from a high-strength steel sheet with a tensile strength of 590 MPa and
a thickness of 1.2 mm by roller bending and laser welding. Several linear and non-linear
stress paths in the first quadrant of the stress space were applied to the tubular
specimens in order to measure the forming limit curve (FLC) and forming limit stress
curve (FLSC) of the as-received test material, in addition to the contours of plastic
work and the directions of plastic strain rates. The contours of plastic work and
the directions of plastic strain rates measured for the linear stress path experiments
were compared with those calculated using selected yield functions in order to identify
the most appropriate yield function for the test material. Moreover, a Marciniak-Kuczyński
type (M-K) forming limit analysis was performed using the most appropriate yield function.
The calculated and measured FLC and FLSC were compared in order to validate the M-K
approach. The path-dependence of the FLC and FLSC was also investigated$$$$
The mathematical formulation of numerous physical problems a results in differential
equations actually partial or ordinary differential equations.In our study we are
interested in solutions of partial differential equations.The aim of this work is
to calculate the concentrations of the pollution, by solving the atmospheric diffusion
equation(ADE) using different mathematical methods of solution. It is difficult to
solve the general form of ADE analytically, so we use some assumptions to get its
solution.The solutions of it depend on the eddy diffusivity profiles(k) and the wind
speed u. We use some physical assumptions to simplify its formula and solve it. In
the present work, we solve the ADE analytically in three dimensions using Green's
function method, Laplace transform method, normal mode method and these separation
of variables method. Also, we use ADM as a numerical method. Finally, comparisons
are made with the results predicted by the previous methods and the observed data.$$$$
The objective of this procedure is to help the user to prepare an COMPSIS report on
an event so that important lessons learned are most efficiently transferred to the
database. This procedure focuses on the content of the information to be provided
in the report rather than on its format. The established procedure follows to large
extend the procedure chosen by the IRS incident reporting system. However this database
is built for I and C equipment with the purpose of the event report database to collect
and disseminate information on events of significance involving Computer-Based Systems
important to safety in nuclear power plants, and feedback conclusions and lessons
learnt from such events. For events where human performance is dominant to draw lessons,
more detailed guidance on the specific information that should be supplied is spelled
out in the present procedure. This guidance differs somewhat from that for the provision
of technical information, and takes into account that the engineering world is usually
less familiar with human behavioural analysis than with technical analysis. The events
to be reported to the COMPSIS database should be based on the national reporting criteria
in the participating member countries. The aim is that all reports including computer
based systems that meet each country reporting criteria should be reported. The database
should give a broad picture of events/incidents occurring in operation with computer
control systems. As soon as an event has been identified, the insights and lessons
learnt to be conveyed to the international nuclear community shall be clearly identified.
On the basis of the description of the event, the event shall be analyzed in detail
under the aspect of direct and potential impact to plant safety functions. The first
part should show the common involvement of operation and safety systems and the second
part should show the special aspects of I and C functions, hardware and software$$$$
Reports are on: - Measurement of Cross-Sections for Neutron Induced Reactions at 14
MeV. - Level Schemes and Gamma Ray Angular Distribution Measurements in ^{28}Si,
^{46}Ti, and ^{53}Mn. - A Study of Neutron-Induced Reaction ''1''2C
(n.n')3α at E_{n} =17.4 MeV. - A Study on Nuclear Evaporation in Nuclear Emulsion
Exposed to 3.0 GeV/c Mesons. - Spectroscopy of ^{64}Cu using the (^{3}He,p)
Reaction at 18 MeV.$$$$
The depth-concentration distributions for 20 keV titanium ions implanted into color
cotton seed and peanut seed were calculated in one and two dimensional models using
the Monte Carlo method. Compared with the computational results of TRIM procedure
and Gaussian fitting, the computational results of the two dimensional model proposed
by this study were well matched with experiment results. The depth-concentration distributions
for 110 keV iron ion under the different doses implanted into the color cotton seed
and the peanut seed were calculated using the two dimensional models. The computational
results were analyzed and discussed. The depth-concentration distributions were predicted
respectively for iron and nitrogen ions with 20 keV energy implanted into color cotton
seed and peanut seed using this model, and the results showed that the two dimensional
computational model in this study was relatively reasonable and provided a theoretical
calculation method for the interaction mechanism of the implantation ions and seed
material. (authors)$$$$
Prognosis data on the production and consumption of electricity in Ukraine were used
to development of nuclear generation for Ukraine after 2030. The calculation was performed
using the MESSAGE computer code provided within Ukrainian activities in the IAEA INPRO
project, Assessments were carried out for the period till 2100 and for the open nuclear
fuel cycle (NFC) with advanced light-water reactors, partially closed NFC with CANDU
reactors and closed NFC with fast reactor$$$$
Russian 2013 p. 121 Russian Federation Zhuchkov, AA Kul'shin, AV Al'masri,
Kh.F. Natsional'nyj Issledovatel'skij Yadernyj Univ. ...$$$$ Orig. TitleTipovye zadachi nechetkogo upravleniya, kontrolya i prognoza v ASU TP teplovykh i
atomnykh ob''ektov SubjectMATHEMATICAL METHODS AND COMPUTING (S97) Source/ReportMinisterstvo Obrazovaniya i Nauki Rossijskoj Federatsii, Moscow (Russian Federation); Gosudarstvennaya Korporatsiya po Atomnoj Ehnergii Rosatom, Moscow (Russian Federation); Natsional'nyj Issledovatel'skij Yadernyj Univ. MIFI, Moscow (Russian Federation); 300 p; ISBN 978-5-7262-1786-4; ; 2013; p. 121; Scientific session of NRNU MEPHI-2013; Nauchnaya sessiya NIYaU MIFI-2013; Moscow (Russian Federation); 2013 Record TypeBook Country/Org.Russian Federation DECMATHEMATICAL LOGIC DEIALGORITHMS, COMPUTER CODES, CONTROL SYSTEMS, EFFICIENCY, FUZZY LOGIC, OPERATION, REACTORS LanguageRussian Ref. Number45109449 Rel. Record45109312 Publ. Year2013 INIS Volume45 INIS Issue48
Heavy steel reflector evaluation using diffusion theory 242 KB - http://www.iaea.org/inis/collection/NCLCollectionStore/_Public/45/091/45091439.pdf - Text Version by Piovezan, Pamela; Carluccio, Thiago (Centro Tecnologico da Marinha (CTMSP), Sao Paulo,
SP (Brazil). Dept. de Neutronica e Blindagem); Abe, Alfredo; Santos, Adimir dos (Instituto
de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)), E-mail:
pamela.piovezan@ctmsp.mar.mil.br, E-mail: thiago.carluccio@ctmsp.mar.mil, E-mail:
alfredo@ctmsp.mar.mil.br, E-mail: asantos@ipen.br; Associacao Brasileira de Energia Nuclear (ABEN), Rio de Janeiro, RJ (Brazil) Read MoreCollapse
[en]
A new component named heavy reflector that did not exist in actual nuclear power plants
was introduced recently by the EPR reactor. The component was designed to partially
reflect neutrons inside the core to increase fuel efficiency and protect the vessel
during its 60-year operational life. Recently, an experiment was designed and performed
to address the real neutron reflector contribution due to the stainless steel in the
IPEN/MB-01 research reactor. The experiment consisted of several plates of stainless
steel which were conveniently positioned at water reflector region of the reactor
core. The main experimental results were the critical control bank positions and reactivity
as a function of the number of stainless steel plates. The main outcome of the experimental
results showed a quite clear effect on neutron absorption and neutron reflection due
to the stainless steel plates. The objective of this preliminary work is to address
theoretically this experiment using the diffusion theory code CITATION, besides existing
evaluation using Monte Carlo (MCNP and Tripoli) and transport (TORT) codes, in order
to verify the performance of diffusion theory for the reflector region. (author)$$$$
Russian 2012 p. 48 Ukraine Stets, MV Pop, OM Maslyuk, VT Institut ehlektronnoj
fiziki NAN UKrainy, Uzhgorod (Ukraine ...$$$$ Orig. TitleRazrabotka algoritma pooucheniya soglasovannykh znachenij yadernykh konstant v raschetakh
tsepej radioaktivnogo raspada s povyshennoj tochnost'yu SubjectMATHEMATICAL METHODS AND COMPUTING (S97) Source/ReportNatsional'naya Akademiya Nauk Ukrainy, Kyiv (Ukraine); Natsional'nyj Nauchnyj Tsentr Khar'kovskij Fiziko-Tekhnicheskij Institut , Khar'kov
(Ukraine); Institut Fiziki Vysokikh Ehnergij i Yadernoj Fiziki, Khar'kov (Ukraine); 113 p; 2012; p. 48; 10. Conference on High Energy Physics, Nuclear Physics and Accelerators; Tezisy dokladov 10-j konferentsii po fizike vysokikh ehnergij, yadernoj fizike i uskoritelyam; Kharkov (Ukraine); 27 Feb - 2 Mar 2012; INIS-UA--189; Available from Ukrainian INIS Centre Record TypeMiscellaneous Country/Org.Ukraine DECCROSS SECTIONS, DECAY, MATHEMATICAL LOGIC, PARTICLE DECAY DEIALGORITHMS, CALCULATION METHODS, GROUP CONSTANTS, NUCLEAR DATA COLLECTIONS, RADIATIVE DECAY LanguageRussian Ref. Number45058773 Rel. Record45058714 Publ. Year2012 INIS Volume45 INIS Issue22
A GPU-based Monte Carlo dose calculation code for photon transport in a voxel phantom 360 KB - http://www.iaea.org/inis/collection/NCLCollectionStore/_Public/45/089/45089780.pdf - Text Version by Bellezzo, M.; Do Nascimento, E.; Yoriyaz, H. (Instituto de Pesquisas Energeticas e
Nucleares / CNEN, Av. Lineu Prestes 2242, Cidade Universitaria, 05508-000 Sao Paulo
(Brazil)), E-mail: mbellezzo@gmail.br; Sociedad Peruana de Radioproteccion, Lima (Peru); Sociedad Mexicana de Irradiacion
y Dosimetria, Mexico D. F. (Mexico). Funding organisation: Organizacion Panamericana
de la Salud, Washington D. C. (United States); Universidad Nacional de San Antonio
de Abad del Cusco, Cusco (Peru); Instituto Peruano de Energia Nuclear, Lima (Peru);
Elekta AB (Sweden); RadPro International GmbH (Germany); ThermoFisher Scientific,
Inc. (United States); Varian Medical Systems (United States) Read MoreCollapse
[en]
As the most accurate method to estimate absorbed dose in radiotherapy, Monte Carlo
method has been widely used in radiotherapy treatment planning. Nevertheless, its
efficiency can be improved for clinical routine applications. In this paper, we present
the CUBMC code, a GPU-based Mc photon transport algorithm for dose calculation under
the Compute Unified Device Architecture platform. The simulation of physical events
is based on the algorithm used in Penelope, and the cross section table used is the
one generated by the Material routine, als present in Penelope code. Photons are transported
in voxel-based geometries with different compositions. To demonstrate the capabilities
of the algorithm developed in the present work four 128 x 128 x 128 voxel phantoms
have been considered. One of them is composed by a homogeneous water-based media,
the second is composed by bone, the third is composed by lung and the fourth is composed
by a heterogeneous bone and vacuum geometry. Simulations were done considering a 6
MeV monoenergetic photon point source. There are two distinct approaches that were
used for transport simulation. The first of them forces the photon to stop at every
voxel frontier, the second one is the Woodcock method, where the photon stop in the
frontier will be considered depending on the material changing across the photon travel
line. Dose calculations using these methods are compared for validation with Penelope
and MCNP5 codes. Speed-up factors are compared using a NVidia GTX 560-Ti GPU card
against a 2.27 GHz Intel Xeon CPU processor. (Author)$$$$