Works matching DE "NUCLEAR fuel elements"
Results: 253
Anisotropy of the conductivity of carbon fibre materials.
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- Fibre Chemistry, 2009, v. 41, n. 6, p. 360, doi. 10.1007/s10692-010-9205-z
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- Article
Behavior of Impurity Elements at Electrochemical Crystallization of UO<sub>2</sub> from Molten Salt Electrolytes.
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- Radiochemistry, 2003, v. 45, n. 6, p. 562, doi. 10.1023/B:RACH.0000015752.15427.c7
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- Article
КОМПЬЮТЕРНО-ИНТЕГРИРОВАННАЯ СИСТЕМА УПРАВЛЕНИЯ ПЕРЕСТАНОВКАМИ ТВС В АКЗ ВВЭР-1000 С УЧЕТОМ ПОВРЕЖДЕННОСТИ ОБОЛОЧЕК ТВЭЛОВ
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- Automation of Technological & Business Processes / Avtomatizaciâ Tehnologiceskih i Biznes-Processov, 2016, v. 8, n. 1, p. 83, doi. 10.21691/atbp.v8i1.16
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- Article
Application and Development Progress of Cr-Based Surface Coating in Nuclear Fuel Elements: II. Current Status and Shortcomings of Performance Studies.
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- Coatings (2079-6412), 2020, v. 10, n. 9, p. 835, doi. 10.3390/coatings10090835
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Application and Development Progress of Cr-Based Surface Coatings in Nuclear Fuel Element: I. Selection, Preparation, and Characteristics of Coating Materials.
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- Coatings (2079-6412), 2020, v. 10, n. 9, p. 808, doi. 10.3390/coatings10090808
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- Article
Laser transmutation of iodine-129.
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- Applied Physics B: Lasers & Optics, 2003, v. 77, n. 4, p. 387, doi. 10.1007/s00340-003-1306-4
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- Article
Comparison and Screening of Nuclear Fuel Cycle Options in View of Sustainable Performance and Waste Management.
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- Sustainability (2071-1050), 2017, v. 9, n. 9, p. 1623, doi. 10.3390/su9091623
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- Article
On-line prediction of quality and shear strength of spacer pad welds of nuclear fuel pins by applying neural network analysis of acoustic emission signals.
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- Science & Technology of Welding & Joining, 2005, v. 10, n. 1, p. 7, doi. 10.1179/174329305X24307
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- Article
Test example of calculation of thin-walled structures with truncated conical shell.
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- Chemical & Petroleum Engineering, 2013, v. 49, n. 3/4, p. 146, doi. 10.1007/s10556-013-9717-5
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- Article
Preparation of specially pure hydrogen at 500-700°C from methane in high-temperature converter-membrane equipment, combined with a CH conversion catalyst.
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- Chemical & Petroleum Engineering, 2011, v. 47, n. 5/6, p. 327, doi. 10.1007/s10556-011-9469-z
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- Article
Impact of Radiation-Induced Microstructures on the Integrity of Spent Nuclear Fuel (SNF) Elements in Long-Term Storage.
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- Safety of Nuclear Waste Disposal, 2021, v. 1, p. 17, doi. 10.5194/sand-1-17-2021
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- Article
IRRADIATION OF D-³HE FUEL BY D-BEAM TO ENHANCE FUSION ENERGY GAIN VIA ICF USING INNOVATIVE WHISTLER WAVE COLLAPSE BY MCNPX SIMULATION.
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- Recent Contributions to Physics, 2024, v. 91, n. 4, p. 33, doi. 10.26577/RCPh.2024.v91.i4.a4
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- Article
Використання алюмінійового стопу у новітніх ядерних установках
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- Metallophysics & Advanced Technologies / Metallofizika i Novejsie Tehnologii, 2022, v. 44, n. 5, p. 623, doi. 10.15407/mfint.44.05.0623
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- Article
Нанооксидне зміцнення стопів на основі цирконію
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- Metallophysics & Advanced Technologies / Metallofizika i Novejsie Tehnologii, 2021, v. 43, n. 11, p. 1471, doi. 10.15407/mfint.43.11.1471
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- Article
Yield behavior of porous nuclear fuel (UO 2 ).
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- Mechanics of Advanced Materials & Structures, 2016, v. 23, n. 10, p. 1149, doi. 10.1080/15376494.2015.1059529
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- Article
The influence of piperazine diamine templates on the synthesis, structures and properties of uranyl oxalate complex.
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- Radiochimica Acta, 2021, v. 109, n. 9, p. 661, doi. 10.1515/ract-2021-1058
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- Article
Dosimetry and methodology of gamma irradiation for degradation studies on solvent extraction systems.
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- Radiochimica Acta, 2021, v. 109, n. 1, p. 61, doi. 10.1515/ract-2020-0040
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- Article
Corrosion of non-irradiated UAl<sub>x</sub>-Al fuel in the presence of clay pore solution: a quantitative XRD secondary phase analysis applying the DDM method.
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- Radiochimica Acta, 2017, v. 105, n. 2, p. 85, doi. 10.1515/ract-2016-2625
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- Article
Plant flammability experiments offer limited insight into vegetation-fire dynamics interactions.
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- New Phytologist, 2012, v. 194, n. 3, p. 606, doi. 10.1111/j.1469-8137.2012.04065.x
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- Article
Water Quality and Corrosion: Considerations for Nuclear Reactor Systems.
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- Journal of the South Carolina Academy of Science, 2011, v. 9, n. 1, p. 43
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- Article
Design of an on-line detection system for fuel rod failure in a pressurized water reactor.
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- Journal of Radioanalytical & Nuclear Chemistry, 2016, v. 307, n. 1, p. 471, doi. 10.1007/s10967-015-4205-3
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- Article
Diverse active well neutron coincidence counter utility at the Savannah River National Laboratory.
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- Journal of Radioanalytical & Nuclear Chemistry, 2008, v. 277, n. 2, p. 281, doi. 10.1007/s10967-007-7078-2
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- Article
Estimation of <sup>235</sup>U concentration in some depleted uranium samples by high resolution gamma-ray spectrometry using 185 keV and 1001 keV gamma-energies of <sup>235</sup>U and <sup>234m</sup>Pa.
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- Journal of Radioanalytical & Nuclear Chemistry, 2007, v. 274, n. 1, p. 1, doi. 10.1007/s10967-006-6852-x
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- Article
Determination of plutonium and <sup>90</sup>Sr in air particulate samples.
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- Journal of Radioanalytical & Nuclear Chemistry, 2007, v. 271, n. 2, p. 475, doi. 10.1007/s10967-007-0233-y
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- Article
Two CdZnTe detector-equipped gamma-ray spectrometers for attribute measurements on irradiated nuclear fuel.
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- Journal of Radioanalytical & Nuclear Chemistry, 2005, v. 264, n. 1, p. 127, doi. 10.1007/s10967-005-0705-x
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- Article
Batch sequential design of optimal experiments for improved predictive maturity in physics-based modeling.
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- Structural & Multidisciplinary Optimization, 2013, v. 48, n. 3, p. 549, doi. 10.1007/s00158-013-0915-8
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- Article
EXTENDED KALMAN FILTER CONTROLLER: FIRST PRINCIPLES MODELS TO NEURAL NETWORKS*.
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- Chemical Engineering Communications, 2006, v. 193, n. 10, p. 1294, doi. 10.1080/00986440500511304
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- Article
BUILDING A MODEL OF DAMAGE TO THE FRACTAL STRUCTURE OF THE SHELL OF THE FUEL ELEMENT OF A NUCLEAR REACTOR.
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- Eastern-European Journal of Enterprise Technologies, 2022, v. 118, n. 8, p. 60, doi. 10.15587/1729-4061.2022.263374
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RECUPERAÇÃO DOS TERMOPARES DO ELEMENTO COMBUSTÍVEL INSTRUMENTADO DO REATOR NUCLEAR TRIGA IPR-R1.
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- Revista Iberoamericana de Ingeniería Mecánica, 2010, v. 14, n. 1, p. 41, doi. 10.5944/ribim.14.1.42986
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- Article
USE OF THE "HOTSPOT" CODE FOR SAFETY AND SECURITY ANALYSIS IN NUCLEAR POWER PLANTS: A CASE STUDY.
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- 2016
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- Case Study
Ceramic Materials for Nuclear Energy Applications.
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- 2019
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- Editorial
Effect of High Si Content on USi Fuel Microstructure.
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- JOM: The Journal of The Minerals, Metals & Materials Society (TMS), 2018, v. 70, n. 2, p. 209, doi. 10.1007/s11837-017-2654-6
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- Article
Studying Zirconium Surface Oxidation by Active Thermal Method.
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- Russian Journal of Nondestructive Testing, 2021, v. 57, n. 12, p. 1120, doi. 10.1134/S1061830921120032
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- Article
An ultrasonic method for the detection of leaking fuel elements in nuclear reactors.
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- Russian Journal of Nondestructive Testing, 2011, v. 47, n. 5, p. 311, doi. 10.1134/S106183091105007X
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- Article
Computer panoramic tomography for industrial application.
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- Russian Journal of Nondestructive Testing, 2008, v. 44, n. 9, p. 607, doi. 10.1134/S1061830908090039
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- Article
German minister takes on greens.
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- Nature, 1994, v. 369, n. 6475, p. 6, doi. 10.1038/369006b0
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- Article
Reflooding investigation on light water reactor model fuel assemblies and debris under the loss of coolant accident simulation.
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- High Temperature, 2017, v. 55, n. 6, p. 914, doi. 10.1134/S0018151X17060037
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- Article
Calculation of heat transfer from a bed of spherical fuel elements to two-phase liquid.
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- High Temperature, 2008, v. 46, n. 4, p. 523, doi. 10.1134/S0018151X08040123
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- Article
Radiological effect of cask-drop accident in open-pool spent fuel storage.
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- Radiation Protection & Environment, 2018, v. 41, n. 4, p. 197, doi. 10.4103/rpe.RPE_67_18
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- Article
Modeling of Dynamic Operation Modes of IVG.1M Reactor.
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- Energies (19961073), 2023, v. 16, n. 2, p. 932, doi. 10.3390/en16020932
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- Article
Behavior of Zr--1Nb alloy in coarse- and ultrafine-grain states under laser-induced shock wave loading.
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- Fracture & Structural Integrity, 2023, n. 66, p. 164, doi. 10.3221/IGF-ESIS.66.10
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- Article
Investigation of natural convection heat transfer in a unique scaled-down dual-channel facility.
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- AIChE Journal, 2017, v. 63, n. 1, p. 387, doi. 10.1002/aic.15583
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- Article
Describing oxygen self-diffusion in PuO by connecting point defect parameters with bulk properties.
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- Journal of Materials Science: Materials in Electronics, 2015, v. 26, n. 5, p. 3287, doi. 10.1007/s10854-015-2829-2
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- Article
Effect of Thermochemical Treatment in Regulated Gas Media on the Thermal Resistance of Zr1%Nb Alloy.
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- Materials Science, 2016, v. 52, n. 2, p. 209, doi. 10.1007/s11003-016-9945-x
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- Article
Plane deformation of a body containing a ribbon fuel element.
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- Materials Science, 2012, v. 48, n. 1, p. 20, doi. 10.1007/s11003-012-9468-z
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- Article
Nonideal Thermal Contact Problem.
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- Differential Equations, 2023, v. 59, n. 6, p. 810, doi. 10.1134/S0012266123060095
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- Article
MODEL FOR CALCULATING THE TEMPERATURE IN THE FUEL RODS OF THE FA-X FUEL ASSEMBLY PRODUCED FOR SUBCRITICAL INSTILLATION AND REACTOR WWR-M.
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- Proceedings of Odessa Polytechnic University / Odes'kyi Politechnichnyi Universytet Pratsi, 2020, v. 61, n. 2, p. 31, doi. 10.15276/opu.2.61.2020.04
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- Article
U and Pu Isotopic Correlations to Check Consistency of Seized Nuclear Material Against a Known Inventory: Team Sweden Effort to Create and Use a Virtual National Nuclear Forensic Library (NNFL) in the Galaxy Serpent Tabletop Exercise.
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- Journal of the Institute of Nuclear Materials Management, 2014, v. 42, n. 4, p. 70
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- Article
Galaxy Serpent Virtual Tabletop Exercise: Canada's Approach, Findings, and Lessons Learned.
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- Journal of the Institute of Nuclear Materials Management, 2014, v. 42, n. 4, p. 31
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- Article
The Use of a National Nuclear Forensic Library in Order to Identify Unknown Seized Nuclear Material: Brazil's Participation in the Galaxy Serpent Exercise.
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- Journal of the Institute of Nuclear Materials Management, 2014, v. 42, n. 4, p. 24
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- Article