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Analysis of Fission Fragm.nts Contributors on Total Decay Heat of Therm.l Neutron-Induced Fission of U-235

Journal of Applied m.them.tics and Physics 2022年第11期10卷 3346-3355页

作者： amir m. alramady Deanship of Graduate Studies King Abdulaziz University Jeddah Saudi Arabia

Calculation of the decay heat from.the decay/buildup of radionuclides generated after nuclear fission is one of the highest priorities in the nuclear industry. These calculations becom. m.re im.ortant if they are m.de together with the analysis of the m.st im.ortant isotopes affecting the decay heat. They are useful in designing the necessary nuclear safety for spent fuels, and their im.ortance cannot be overlooked in the designs of transporting fuel storage containers as well as in the m.nagem.nt of the radioactive waste generated. In this paper, by using m.TLAB, the decay heat after the therm.l fission of a U-235 nucleus was num.rically calculated by solving linear differential equations for all the buildups/decays of the fission products. Also, the m.st contribution of radioactive isotopes to the decay heat was analyzed by using m.crosoft Excel. The m.st influential isotopes were deduced in two ways;either by calculating the m.st influential isotopes at specific tim.s, or by determ.ning the largest influences in a cum.lative m.nner. All required nuclear data such as decay constants their branching ratios, independent fission yield, and average α-, β-, and γ-energies released per disintegration of any nuclide, have been extracted from.the latest version of the Evaluated Nuclear Data Files (ENDF) database ENDF/B-VIII.0. The two different m.thods used showed a difference in the contributing isotopes, which is logical for the difference in the m.thod of calculation. The first m.thod is suitable for instantaneous data while the second m.thod is m.re suitable when there is a need to know the cum.lative calculations. In sum. we can say that both m.thods com.lem.nt each other, and neither of them.can be dispensed with in the accurate calculations related to transportation and storage of spent fuel.

关键词： Fission Products Decay/Buildup Fission Yield Decay Heat

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Em.irical Neutron Cross Section Form.lae for (n, p) and (n, d) Reactions of He-3 Target

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Journal of Applied m.them.tics and Physics 2021年第7期9卷 1434-1441页

作者： amir m. alramady King Abdulaziz University Jeddah KSA

In this work, new cross section form.lae for (n, p) and (n, d) reactions of He-3 have been investigated as a function of incident neutron energy. The new Em.irical form.lae were produced by using the least squares m.thod to the experim.ntal cross sections data, which were taken from.Experim.ntal Nuclear Reaction Data EXFOR Database Version of 2021. Several functions were exam.ned to choose the best one that fits the data. Statistical hypothesis testing was used to insure how well the suggested equations fit the set of data. Two statistical indicators were used for each case for goodness-of-fit. Very high com.atibility was found between the em.irical values and the experim.ntal data for both reactions.

关键词： Em.irical Cross Section Form.la (n p) Reaction (n p) Reaction and Goodness-of-Fit

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Prediction of the Average Decay Heat per Fission for m.X Nuclear Fuel

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Journal of Applied m.them.tics and Physics 2022年第3期10卷 887-899页

作者： amir m. alramady Hanan m. Barashed Sherif S. Nafee Deanship of Post Graduate Studies King Abdelaziz University Jeddah Kingdom of Saudi Arabia Departm.nt of Physics Faculty of Science King Abdulaziz University Jeddah Kingdom of Saudi Arabia Departm.nt of Physics Faculty of Science Hadhramout University Mukalla Yemen Departm.nt of Physics Faculty of Science Alexandria University Alexandria Egypt

m.XED Oxide Nuclear fuel (m.X) contains both uranium.and plutonium.in oxidized form. It is im.ortant to calculate the nuclear decay heat due to the single therm.l fission (fission due to 0.0235 eV neutron) for all fissile nuclei in the m.X fuels (U235, Pu239, and Pu241). These fissile nuclei are the m.in source of the decay heat in m.X fuel. Decay heat calculation of the weighted fissile m.terial content in m.X fuel is also im.ortant. A num.rical m.thod was used in this work to calculate the concentrations of all fission products due to the individual therm.l fission of the three fissile m.terials as a function of tim. N(t). The decay heat calculations for the three fissile m.terials are directly calculated using the sum.ation m.thod by knowing the different concentrations of fission products over tim.. The average decay heat of the m.X fuel in induced therm.l fission is also concluded. The m.st influential nuclei in the decay heat were also identified. The m.thod used has been validated by several com.arisons before, but the new in this work is using the m.st recent Evaluated Nuclear Data Library ENDF/B-VIII.0. Calculations of decay heat show very com.on trends for a period of 107 sec after the fission burst of therm.l fissions of individual fissile nuclei. m.reover, the code showed high capability in calculating the fission fragm.nts inventories and decay heats due to the decay of fission fragm.nts of 31 fissionable nuclei.

关键词： Nuclear Decay Heat Fission Burst Fission Fragm.nts m.X Fuel m.TLAB

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Fission Fragm.nt Decay Heat by Using the m.st Recent Evaluated Nuclear Data Library ENDF/B-VIII

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Journal of Applied m.them.tics and Physics 2022年第4期10卷 1182-1190页

作者： amir m. alramady Hanan m. Barashed Sherif S. Nafee Deanship of Post Graduate Studies King Abdulaziz University Jeddah KSA Departm.nt of Physics Faculty of Science King Abdulaziz University Jeddah KSA Departm.nt of Physics Faculty of Science Hadhramout University Mukalla Yemen Departm.nt of Physics Faculty of Science Alexandria University Alexandria Egypt

In this paper, a hom.-m.de code was designed to calculate the decay heat em.tted by fission fragm.nts as a result of successive radioactive em.ssions after a fission burst. The nuclear data necessary for the calculations was extracted from.the latest version of the Evaluated Nuclear Data Library ENDF/B-VIII.0. The code can calculate the decay heat of therm.l and fast neutron-induced fission reactions on the isotopes of Thorium. Protactinium. Uranium. Neptunium. Plutonium. Am.ricium. Curium. California, Einsteinium. and Ferm.um. A num.rical m.thod was used in this work to calculate the decay heat of all fission fragm.nts due to the individual therm.l or fast fissions of the isotopes of the previous ten actinides. The m.st influential nuclei in the decay heat were also identified at different tim.s after the fission event. m.reover, the code showed high capability in calculating the fission fragm.nts inventories and decay heats due to the decay of fission fragm.nts of 31 fissionable nuclei.

关键词： Nuclear Decay Heat Fission Burst Fission Fragm.nts m.TLAB

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m.deling of UTSG in the Pressurized Water Reactor Using Accurate Form.lae of Therm.dynam.c Properties

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Journal of Applied m.them.tics and Physics 2021年第5期9卷 947-967页

作者： amir m. alramady Sheikha Al-Sharif Sherif S. Nafee Deanship of Graduate Studies King Abdulaziz University Jeddah Kingdom of Saudi Arabia Physics Departm.nt Faculty of Science King Abdulaziz University Jeddah Kingdom of Saudi Arabia Physics Departm.nt Faculty of Science Alexandria University Alexandria Egypt

In nuclear power plants, steam.generators are im.ortant parts. This paper introduces a U-tube steam.generator (UTSG) m.del im.lem.nted com.letely using m.TLAB environm.nt. The UTSG consists of four regions: upward and downward prim.ry regions, upward and downward m.tal tube regions, and secondary regions, which contain heat transfer region, steam.separation region, and subcooled water region. Governing equations are derived by applying energy and m.ss conservation equations in all regions. Accurate functions that describe the relationships between therm.dynam.c properties of the saturated steam.are introduced instead of interpolation m.thod that is widely used. Steady state and one transient case are presented as well.

关键词： UTSG m.deling Steam.Tables Therm.dynam.c Properties

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Seism.c isolation effect of lined circular tunnels with dam.ing treatm.nts

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Earthquake Engineering and Engineering Vibration 2008年第3期7卷 305-319页

作者： Seyyed m. Hashem.nejad amir K. m.ri Acoustics Research Laboratory Department of Mechanical Engineering Iran University of Science and Technology Narmak Tehran 16844 Iran

The Havriliak-Negam. m.del for dynam.c viscoelastic m.terial behavior and Biot＇s theory of poroelasticity are em.loyed to develop an exact solution for three-dim.nsional scattering effect of harm.nic plane P-SV waves from.a circular cavity lined with a m.ltilayered fluid-filled shell of infinite length containing viscoelastic dam.ing m.terials and em.edded within a fluid-saturated perm.able surrounding soil m.dium. The analytical results are illustrated with num.rical exam.les where the effects of liner/coating structural arrangem.nt, viscoelastic m.terial properties, liner-soil interface bonding condition, seism.c excitation frequency, and angle of incidence on the induced dynam.c stress concentrations are evaluated and discussed to obtain representative values of the param.ters that characterize the system. It is dem.nstrated that incorporating viscoelastic dam.ing m.terials with a low shear m.dulus in the constrained layer configuration is an efficient m.ans of enhancing the overall seism.c isolation perform.nce, especially for near-norm.lly incident seism.c shear waves where the am.litudes of induced dynam.c stresses m.y be reduced by up to one-third of those without isolation in a relatively wide frequency range. Som. additional cases are considered and good agreem.nts with solutions available in the literature are obtained.

关键词： underground tunnel perm.able soil seism.c wave scattering flee/constrained layer dam.ing

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Invariant G^(2)V algorithm.for com.uting SAGBI-Grobner bases

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Science China m.them.tics 2013年第9期56卷 1781-1794页

作者： HASHEm. amir m.-ALIZADEH Benyam.n RIAHI m.nireh Departm.nt of m.them.tical Sciences Isfahan University of Technology Young Researchers Club Science and Research BranchIslamic Azad University Departm.nt of m.them.tics Damghan University

Faugère and Rahm.ny have presented the invariant F5 algorithm.to com.ute SAGBI-Grbner bases of ideals of invariant rings. This algorithm.has an increm.ntal structure, and it is based on the m.trix version of F5 algorithm.to use F5 criterion to rem.ve a part of useless reductions. Although this algorithm.is m.re efficient than the Buchberger-like algorithm. however it does not use all the existing criteria (for an increm.ntal structure) to detect superfluous reductions. In this paper, we consider a new algorithm. nam.ly, invariant G2V algorithm. to com.ute SAGBI-Grbner bases of ideals of invariant rings using m.re criteria. This algorithm.has a new structure and it is based on the G2V algorithm. a variant of the F5 algorithm.to com.ute Grbner bases. We have im.lem.nted our new algorithm.in m.ple , and we give experim.ntal com.arison, via som. exam.les, of perform.nce of this algorithm.with the invariant F5 algorithm.

关键词： G^(2)V algorithm invariant F5 algorithm invariant G^(2)V algorithm SAGBI-Grobner bases

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Deform.tion and failure in nanom.terials via a data driven m.delling approach

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Theoretical & Applied m.chanics Letters 2020年第4期10卷 249-252页

作者： m.amir Siddiq School of Engineering University of AberdeenAB243UEAberdeenUK

A data driven com.utational m.del that accounts for m.re than two m.terial states has been presented in this work. Presented m.del can account for m.ltiple state variables, such as stresses,strains, strain rates and failure stress, as com.ared to previously reported m.dels with two *** is used to perform.deform.tion and failure sim.lations of carbon nanotubes and carbon nanotube/epoxy nanocom.osites. The m.del capability of capturing the strain rate dependent deform.tion and failure has been dem.nstrated through predictions against uniaxial test data taken from.literature. The predicted results show a good agreem.nt between data set taken from.literature and sim.lations.

关键词： Data driven com.utational m.chanics Nanom.terials Carbon nanotubes Nanocom.osites

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Quasi-inverse Pendulum.m.del of 12 DoF Bipedal Walking

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International Journal of Autom.tion and com.uting 2017年第2期14卷 179-190页

作者： m. Akhtaruzzam.n amir A. Shafie m.. Raisuddin Khan Departm.nt of m.chatronics Engineering Kulliyyah of Engineering International Islamic University Malaysia Kuala Lumpur 53100 Malaysia

This paper presents m.deling of a 12-degree of freedom.（DoF） bipedal robot, focusing on the lower lim.s of the system. and trajectory design for walking on straight path. Gait trajectories are designed by m.deling of center of m.ss （Com. trajectory and swing foot ankle trajectory based on stance foot ankle. The dynam.c equations of m.tion of the bipedal robot are derived by considering the system.as a quasi inverted pendulm. （QIP） m.del. The direction and acceleration of Com.m.vem.nt of the QIP m.del is determ.ned by the position of Com.relative to the centre of pressure （COP）. To determ.ne heel-contact and toe-off, two custom.designed switches are attached with heel and toe positions of each foot. Four force sensitive resistor （FSR） sensors are also placed at the plantar surface to m.asure pressure that is induced on each foot while walking which leads to the calculation of CoP trajectory. The paper also describes forward kinem.tic （FIK） and inverse kinem.tic （IK） investigations of the biped m.del where Denavit-Hartenberg （D-H） representation and Geom.tric-Trigonom.tric （G-T） form.lation approach are applied. Experim.nts are carried out to ensure the reliability of the proposed m.del where the links of the bipedal system.follow the best possible trajectories while walking on straight path.

关键词： Hum.noid robot quasi-inverse pendulum gait trajectory planning Anthropoid.

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Effect of foundation flexibility on ductility reduction factors for R/C stack-like structures

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Earthquake Engineering and Engineering Vibration 2011年第2期10卷 277-290页

作者： amir m.Halabian Shabnam.Kabiri Faculty of Civil Engineering Isfahan University of Technology

The m.st im.ortant param.ter used to determ.ne force reduction factors in force-based design procedures adopted in the current seism.c codes is the structural ductility. For a structure supported on a flexible foundation, the ductility factor could be affected by foundation com.liances. The ductility factors given in the current codes are m.stly assigned ignoring the effect of SSI and therefore the objective of this research is to assess the significance of SSI phenom.non on ductility factors of stack-like structures. The deform.d configuration of stack-fike structures is idealized as an assem.lage of beam.elem.nts considering nonlinear m.m.nt-curvature relations, while a linear sway-rocking m.del was im.lem.nted to m.del the supporting soil. Using a set of artificial records, repeated linear and nonlinear analyses were perform.d by gradually increasing the intensity of acceleration to a level where the first yielding of steel in linear and nonlinear analyses is observed and a level corresponding to the stack collapse in the nonlinear analysis. The difference between inelastic and elastic resistance in term. of displacem.nt ductility factors has been quantified. The results indicate that foundation flexibility can decrease the ductility of the system.and neglecting this phenom.non m.y lead to erroneous conclusions in the prediction of the seism.c perform.nce of flexibly-supported R/C stack-like structures.

关键词： soil-structure interaction R/C stack-like structures ductility

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