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Distance Learning at the MS and PhD Levels in the nuclear and Radiation engineering program, nuclear and Applied Robotics, Materials science and engineering and Walker Department of Mechanical engineering at the University of Texas at Austin

Distance Learning at the MS and PhD Levels in the Nuclear an...

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2023 Transactions of the American nuclear Society Winter Conference and Expo, ANS 2023

作者： Landsberger1, Sheldon Charlton, William Clamo, Kevin Ezekoye, Ofodike Kovar, Desiderio Haas, Derek Pryor, Mitchell University of Texas at Austin Nuclear and Radiation Engineering Program Nuclear Engineering Teaching Lab 10100 Burnet Road Pickle Research Campus R-9000 AustinTX United States Walker Department of Mechanical Engineering University of Texas at Austin 204.Dean Keeton ETC II 5.160 AustinTX United States The University of Texas at Austin Materials Science and Engineering Walker Department of Mechanical Engineering 204 Dean Keeton ETC II 5.100 AustinTX United States

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Atmospheric clearing of solid-particle debris using femtosecond filaments

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Physical Review Applied 2024年第1期22卷 014075-014075页

作者： Kyle S. Latty Kyle C. Hartig Nuclear Engineering Program Department of Materials Science and Engineering

Through nonlinear self-focusing, femtosecond pulses can propagate several kilometers beyond diffraction limits, forming an ionization channel in air known as a laser filaments. It has been demonstrated that in the wake of the filament, aerosols can be effectively cleared to improve the transmission of subsequent laser pulses or secondary light sources, pertinent to applications in atmospheric sensing. However, the current understanding of aerosol clearing is founded on interactions with droplets to simulate fogs and clouds and thus does not extend to solid particles or atmospheric debris. Using optical trapping, we isolate both graphite and silica microparticles and directly measure the subsequent displacement caused by the filament using time-resolved shadowgraphy. The shock wave from the filament is demonstrated to propel particles away from the filament, directly contributing to atmospheric debris clearing. Particles exposed to the laser light in either the intense filament core or the surrounding energy reservoir are axially displaced along the beam path. It is found that the optomechanical properties of the particle largely influence the axial displacement induced by laser exposure through mechanisms such as radiation pressure, mass ejection from ablation or optical damage, and particle deagglomeration.

关键词： Atmospheric science Light-matter interaction Microparticles Self-focusing Shock waves & discontinuities in plasma Aerosols Femtosecond laser irradiation Optical tweezers

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Historical, Contemporary, and Future Perspectives on Fuel Qualification

Historical, Contemporary, and Future Perspectives on Fuel Qu...

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2024 Annual Conference on Transactions of the American nuclear Society, ANS 2024

作者： Mika, Mitch Aitkaliyeva, Assel University of Florida Department of Materials Science Nuclear Engineering Program GainesvilleFL United States

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Automating selective area electron diffraction phase identification using machine learning

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Journal of Materiomics 2024年第4期10卷 896-905页

作者： M.Mika N.Tomczak C.Finney J.Carter A.Aitkaliyeva Nuclear Engineering Program in Department of Materials Science University of Florida100 Rhines HallGainesville32611FLUSA Department of Materials Science&Engineering Case Western Reserve University2111 Martin Luther King Jr DrCleveland44106OHUSA

Selective area electron diffraction(SAED)patterns can provide valuable insight into the structure of a ***,the manual identification of collected patterns can be a significant bottleneck in the overall phase classification *** this work,we utilize the recent advances in computer vision and machine learning(ML)to automate the indexing of SAED *** performance of six different ML algorithms is demonstrated using metallic plutonium-zirconium *** most successful approach trained a neural network(NN)to make a classification of the phase and zone axis,and then utilized a second NN to synthesize multiple independent predictions of different tilts in a single sample to make an overall phase *** results demonstrate that automated SAED phase identification using ML is a viable route to accelerate materials characterization.

关键词： Selective area electron diffraction Machine learning Phase identification Metallic fuels Pu alloys

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Direct Multi-group Cross-sections via NJOY+OJOYU for PWR and FLiBe-MSR Reactor Systems

Direct Multi-group Cross-sections via NJOY+OJOYU for PWR and...

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2023 Transactions of the American nuclear Society Annual Meeting and Technology Expo, ANS 2023

作者： Wang, Meng-Jen Simpson, Michael Sjoden, Glenn E. Nuclear Engineering Program Department of Civil and Environmental Engineering University of Utah United States Department of Material Science and Engineering University of Utah United States

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Neutronic and Proliferation Resistance Analysis of Small Modular Pressurized Water Reactor with Various Fuel Types using SRAC 2006 10

Neutronic and Proliferation Resistance Analysis of Small Mod...

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10th Asian Physics Symposium 2023, APS 2023

作者： Amatullah, Amila Permana, Sidik Pramuditya, Syeilendra Master Program in Nuclear Science and Engineering Faculty of Mathematics and Natural Sciences Bandung Institute of Technology Ganesha No. 10 Bandung Indonesia Graduate Program in Nuclear Science and Engineering Faculty of Mathematics and Natural Sciences Bandung Institute of Technology Ganesha No. 10 Bandung Indonesia Graduate Program in Physics Faculty of Mathematics and Natural Sciences Bandung Institute of Technology Ganesha No. 10 Bandung Indonesia

One strategy for emission reduction in Indonesia is the dedieselization program, replacing diesel power plants with renewables. Pressurized Water Reactor (PWR) type Small Modular Reactor (SMR) is also a consideration. This study aims to compare fuel performance in SMRs. Four fuel types with varying fissile and fertile nuclides but equal fissile mass percentages were assessed: U235- U238, U235-Th232, U233-U238, and U233-Th232, using PIJ SRAC 2006 and JENDL 4.0. Parameters include neutron multiplication factor, conversion ratio, and isotope production. Results indicated that U233-U238 has a highest initial neutron multiplication factor, 1.55. Substituting uranium-238 with thorium-232 boosts neutron flux and conversion, reducing nuclear proliferation risk. While initial neutron multiplication may not be highest, thorium-232 can produce uranium-233 with high initial neutron multiplication factor. This research aids fuel selection for Indonesia SMR dedieselization program. © Published under licence by IOP Publishing Ltd.

关键词： Thorium

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Multi-criteria decision making for nuclear power plant selection using fuzzy AHP:Evidence from Indonesia

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Energy and AI 2023年第4期14卷 99-111页

作者： Ade Gafar Abdullah Mohammad Ali Shafii Syeilendra Pramuditya Topan Setiadipura Kurnia Anzhar Electrical Engineering Study Program Universitas Pendidikan IndonesiaBandungIndonesia Physics Department Andalas UniversityPadangIndonesia Nuclear Science and Engineering Study Program Bandung Institute of TechnologyIndonesia Research Center for Nuclear Reactor Technology National Research and Innovation AgencyIndonesia Pusat Unggulan Ipteks Perguruan Tinggi Technical and Vocational Education and Training Research Center(TVET RC)Universitas Pendidikan IndonesiaIndonesia

In terms of planning aspect,nuclear power plant(NPP)development needs analyses,consideration,and right decision making due to multi criteria *** study prioritizes the best site development of Indonesian NPPs in terms of 21 social,economic,and technical perspectives which comprise transmission network,oper-ating cost,economic impact,geology,geotechnic,seismology,population density,environment,cooling water,meteorology,hydrology,proximity to hazardous facilities,topography,land use,proximity to wetland,evacu-ation route,security,transportation network,legal consideration,impact of tourism,land ownership,historical places,and public acceptance,all identified to be considerations for the best *** Fuzzy algorithms(Chang’s Extent Analysis and Buckley’s Fuzzy AHP)were used to determine the criteria priorities as well as NPP site feasibility of two locations in *** results found that geology,geotechnic,and seismology(SA1);security(SO1),population density(SA2),environment(SA3),and cooling water(SA4)had the highest priorities among the 21 *** on the 5 top priority criteria,West Kalimantan and East Kalimantan provinces serve as the best candidates for the NPP *** an innovative and novel multi criteria Fuzzy AHP–based decision making(MCDM)approach has been proven to become a useful reference to select NPP sites in Indonesia.

关键词： Analytical hierarchy process Fuzzy AHP Multi-criteria decision making nuclear power plant

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Investigation of He retention in W through combined He characterization methods and cluster dynamics model

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nuclear science and Techniques 2025年第3期36卷 201-213页

作者： Jie Qiu Xun-Xiang Hu Cong-Yi Li Wendy Garcia Tan Shi Sha Xue Jamie L.Weaver HHeather Chen-Mayer Brian D.Wirth SJTU Paris Elite Institute of Technology Shanghai Jiao Tong UniversityShanghai 200240China Department of Nuclear Engineering University of TennesseeKnoxvilleTN 37996USA School of Physics Sichuan UniversityChengdu 610065China Oak Ridge National Laboratory Oak RidgeTN 37830USA Global Institute of Future Technology Shanghai Jiao Tong UniversityShanghai 200240China School of Nuclear Science and Technology Xi’an Jiaotong UniversityXi’an 710049China Nuclear Engineering Program The Ohio State UniversityColumbusOH 43210USA Material Measurement Laboratory National Institute of Standards and TechnologyGaithersburgMD 20899USA

Tungsten(W)is the leading plasma-facing candidate material for the International Thermonuclear Experimental Reactor and next-generation fusion *** impact of synergistic helium(He),irradiation-induced microstructural changes,and the corresponding thermal-mechanical property degradation of W are critically important but are not well understood *** the performance of W in fusion environments requires understanding the fundamentals of He-defect interactions and the resultant He bubble nucleation and growth in *** this study,He retention in helium-ion-implanted W was assessed using neutron depth profiling(NDP),laser ablation mass spectrometry(LAMS),and thermal desorption spectroscopy(TDS)following 10 keV room-temperature He implantation at various *** three experimental techniques enabled the determination of the He depth profile and retention in He-implanted W.A cluster dynamics model based on the diffusion-reaction rate theory was applied to interpret the experimental *** model successfully predicted the He spatial depth-dependent profile in He-implanted W,which was in good agreement with the LAMS *** model also successfully captured the major features of the He desorption spectra observed in the THDS *** NDP quantified total He concentration values for the samples;they were similar to those estimated by ***,the depth profiles from NDP and LAMS were not comparable due to several *** combination of modeling and experimentation enabled the identification of possible trapping sites for He in W and the evolution of He-defect clusters during the TDS thermal annealing process.

关键词： Tokamak nuclear reactor Nondestructive detection

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Evaluated Material Attractiveness of Plutonium Composition from Economic Simplified Boiling Water Reactor (ESBWR) 10

Evaluated Material Attractiveness of Plutonium Composition f...

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10th Asian Physics Symposium 2023, APS 2023

作者： Nasyidiah, Fungky Iqlima Permana, Sidik Pramuditya, Syeilendra Master Program in Nuclear Science and Engineering Faculty of Mathematics and Natural Sciences Institute Technology of Bandung Ganesa 10th Street Bandung40132 Indonesia Department of Nuclear Science and Engineering Faculty of Mathematics and Natural Sciences Institute Technology of Bandung Ganesa 10th Street Bandung40132 Indonesia

The potential for misuse of nuclear fuel has prompted many to make efforts to prevent a country from acquiring nuclear explosive devices (weapons). Weapon utility equated with nuclear material attractiveness when applied to protection and security. Material attractiveness evaluated using an equation first developed by Masaki Saito, namely ATTR. ESBWR is one of the reactors of the BWR reactor type that is still operating. The purpose of this study is to evaluate Material Attractiveness based on the composition of plutonium in the ESBWR reactor, during reactor operation and after reactor operation. The ATTR concept utilizes the plutonium isotope composition to evaluate the material attractiveness aspect. Parameters such as BCM, Rossi-alpha, and neutron prompt life become additional aspects in evaluating material attractiveness. In the research results, the ATTR value decreased from the beginning of reactor operation until the reactor stopped operating. At the beginning of the reactor operation, it was categorizing as a weapon-grade with an ATTR value of 0.19 and when the reactor stopped operating it was categorizing as an unusable grade with an ATTR value of 0.012. At the time of cooling time up to 1x106 (one million) cooling time, the ATTR value increases by 0.019 which was categorizing as an unusable grade. After a cooling time of 1x106 (one million) years up to 1x107 (ten million) years, the ATTR value was 0.001 which categorized as an exempt level. This states that the increasing burnup value will further reduce the ATTR value. Likewise with the Rossi-Alpha and Bare Critical Mass values. Conversely, it will decrease the value of neutron lifetime. The ATTR value after the reactor operates up to one hundred years of cooling time increases and then decreases significantly after 1x106 (one million) years due to the half-life of plutonium isotopes. Likewise, the Rossi-Alpha and Bare critical mass values. However, it is different with the neutron fast lifetime. © Publis

关键词： Boiling water reactors

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Na-22 for Safeguarding and Mass Accounting of Molten Salt Systems

Na-22 for Safeguarding and Mass Accounting of Molten Salt Sy...

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2023 Transactions of the American nuclear Society Winter Conference and Expo, ANS 2023

作者： Zile, Matthew Van Kauffman, Andrew Herminghuysen, Kevin Li, Shelly Simpson, Michael Kandlakunta, Praneeth Cao, Guoping Cao, Lei R. Nuclear Engineering Program Department of Mechanical and Aerospace Engineering Ohio State University United States Nuclear Reactor Laboratory College of Engineering Ohio State University United States Department of Materials Science and Engineering University of Utah.Idaho National Laboratory United States

The Na-22based radioactive tracer dilution (RTD) technique has been previously demonstrated for mass accounting in small quantities of clean molten salt for bench top testing. While the concept of RTD has proven to be a promising method, it has lacked further validation in large-scale quantities and in fuel-bearing salt. Towards that end, two research initiatives are on-going at The Ohio State University (OSU) and Idaho National Laboratory (INL) to address these challenges. Current work at OSU is focused on evaluating the RTD using the full gamma-ray spectrum of fission products produced by irradiating fuel bearing salt, i.e., UCl3-MgCl2-KCl in a 500-kW research reactor. The INL team has successfully demonstrated the RTD for mass determination using an 8-kg LiCl-KCl-UCl3salt for uranium electrorefining and is currentlyseeking to validate the tracer method with large(about 60 kg)molten salt system(bearing fission products) in an oxide reduction (OR) facility for spent nuclear fuel (SNF) reprocessing. © 2023 American nuclear Society. All rights reserved.

关键词： Fission products

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