Results 41 to 50 of about 143,089 (299)

Mechanochemical Synthesis and Characterization of Nanostructured ErB4 and NdB4 Rare‐Earth Tetraborides

Advanced Engineering Materials, Volume 27, Issue 6, March 2025.
ErB4 and NdB4 nanostructured powders are produced by mechanochemical synthesis. 5 h mechanical alloying and 4 M HCl acid leaching are used in the production. ErB4 and NdB4 powders exhibit maximum magnetization of 0.4726 emu g−1 accompanied with an antiferromagnetic‐to‐paramagnetic phase transition at about TN = 18 K and 0.132 emu g−1 with a maximum at ...
Burçak Boztemur, Faruk Kaya, Bora Derin, Mustafa Lütfi Öveçoğlu, Ju Li, Duygu Ağaoğulları   +5 more
wiley   +1 more source

Neutronic analysis of a heat-pipe cooled reactor

Acta Polytechnica CTU Proceedings, 2023
Heat-pipe cooled reactors belong to the group of nuclear reactors using heat pipes filled with liquid metals (such as sodium or potassium) to cool the core. Due to the passive heat removal system, there is no need to use closed loops with pumps, and the
Josef Sabol, Jan Frýbort
doaj   +1 more source

Neutrino Oscillation Studies with Reactors

, 2015
Nuclear reactors are one of the most intense, pure, controllable, cost-effective, and well-understood sources of neutrinos. Reactors have played a major role in the study of neutrino oscillations, a phenomenon that indicates that neutrinos have mass and ...
Vogel, Petr, Wen, Liangjian, Zhang, Chao
core   +1 more source

Packaging of Macroscopic Material Payloads: Needs, Challenges, Concepts, and Future Directions

Advanced Engineering Materials, EarlyView.
This review introduces a unified framework that decomposes any macroscopic packaging system into the payload, packaging material, and packaging strategy and combines them into a conceptual packaging equation: packaging strategy = payload + packaging material.
Venkata S. R. Jampani, Manos Anyfantakis
wiley   +1 more source

New measurement of the 242Pu(n,γ) cross section at n-TOF-EAR1 for MOX fuels : Preliminary results in the RRR [PDF]

, 2016
The spent fuel of current nuclear reactors contains fissile plutonium isotopes that can be combined with 238U to make mixed oxide (MOX) fuel. In this way the Pu from spent fuel is used in a new reactor cycle, contributing to the long-term sustainability ...
A. Brown, A. Casanovas, A. Ferrari, A. Gawlik, A. Junghans, A. Kalamara, A. Kimura, A. Masi, A. Mazzone, A. Mengoni, A. Musumarra, A. Negret, A. Oprea, A. Pavlik, A. Plompen, A. Saxena, A. Stamatopoulos, A. Tarifeño-Saldivia, A. Ventura, A. Wallner, A.G. Smith, A.R. García, Abbondanno, Agostinelli, B. Fernández-Domínguez, Barbagallo, Belgya, C. Domingo-Pardo, C. Guerrero, C. Lederer, C. Massimi, C. Rubbia, Capote, Chadwick, Colonna, D. Bosnar, D. Cano-Ott, D. Kurtulgil, D. Macina, D. Radeck, D. Schumann, D.G. Jenkins, E. Berthoumieux, E. Chiaveri, E. Dupont, E. González, E. Griesmayer, E. Jericha, E. Leal-Cidoncha, E. Mendoza, E.A. Maugeri, F. Bečvář, F. Calviño, F. Cerutti, F. Gunsing, F. Käppeler, F. Mingrone, F.-J. Hambsch, G. Cortés, G. Tagliente, G. Vannini, Guerrero, Guerrero, H. Harada, H. Leeb, I. Durán, I. Porras, I.F. Gonçalves, J. Andrzejewski, J. Balibrea, J. Billowes, J. Heyse, J. Heyse, J. Lerendegui-Marco, J. Marganiec, J. Perkowski, J. Praena, J.A. Ryan, J.L. Tain, J.M. Quesada, K. Eberhardt, K. Göbel, L. Audouin, L. Cosentino, L. Tassan-Got, L.A. Damone, Lerendegui-Marco, Lo, M. Bacak, M. Barbagallo, M. Caamaño, M. Calviani, M. Diakaki, M. Kokkoris, M. Krtička, M. Mastromarco, M. Sabaté-Gilarte, M.A. Cortés-Giraldo, M.B. Gómez-Hornillos, Macklin, N. Colonna, N. Kivel, N. Patronis, N.V. Sosnin, O. Aberle, P. Ferreira, P. Finocchiaro, P. Kavrigin, P. Mastinu, P. Schillebeeckx, P. Schillebeeckx, P. Siegler, P. Vaz, P. Žugec, P.C. Rout, P.J. Woods, P.M. Milazzo, Plag, Praena, R. Cardella, R. Dressler, R. Nolte, R. Reifarth, R. Vlastou, Reich, S. Gilardoni, S. Heinitz, S. Kopecky, S. Lo Meo, S. Oberstedt, S. Valenta, S. Warren, S.J. Lonsdale, T. Glodariu, T. Martínez, T. Rauscher, T. Wright, V. Variale, V. Vlachoudis, W. Mondelaers, Weiss, Y. Kadi, Y.H. Chen   +142 more
core   +12 more sources

Microstructural Evolution and Vacancy Defect Formation in Mn–Mo–Ni RPV Steel Under Low Cycle Fatigue: Insights From EBSD and PALS

Advanced Engineering Materials, EarlyView.
Low‐cycle fatigue damage in Mn–Mo–Ni reactor pressure vessel steel is examined using a combined electron backscatter diffraction and positron annihilation lifetime spectroscopy approach. The study correlates texture evolution, dislocation substructure development, and vacancy‐type defect formation across uniform, necked, and fracture regions, providing
Apu Sarkar, Dhanadeep Dutta, G. Bharat Reddy   +2 more
wiley   +1 more source

Deriving formula to simulate the radiological behavior during LOCA in open pool type reactor

Brazilian Journal of Radiation Sciences, 2022
This study aims to model the radiological consequences that result from loss of coolant accident in open pool research reactor of 22 MW power. The loss of coolant accident results from rupture in the cooling systems of the reactor and consequently ...
Amr Abdelhady
doaj   +1 more source

Sol–Gel Derived Polymer Precursors for Stereolithography of ZrC

Advanced Engineering Materials, EarlyView.
ZrC is a critical material target for extreme temperature conditions. This report describes a protocol for preparing ZrC ceramics via stereolithography and examines the impact of the polymer matrix on carbothermal reduction and mechanical stability of 3D printed ZrC.
Charles J. Rafalko, Evelyn Wang, Michael A. Hickner   +2 more
wiley   +1 more source

Corrosion and Process Analysis of a Preoxidized MgO Recyclate‐Based Cermet Anode in Laboratory‐Scale Na‐Cryolite Molten Salt Electrolysis of Aluminum at 1000°C

Advanced Engineering Materials, EarlyView.
EDX elemental map of the pre‐oxidized MgO–steel cermet anode cross section after electrolysis. The development of inert anodes for aluminum electrolysis remains challenging due to the high corrosivity of cryolite‐based melts at 950°C–1000°C. This study investigates the corrosion and process behavior of a carbon‐free MgO–steel cermet anode derived from ...
Alexander Adamczyk, Farhan Hossain, Felipe A. Garcia Paz, Serhii Yaroshevskyi, Felix Drechsler, Daniel Vogt, Christos G. Aneziris, Alexandros Charitos   +7 more
wiley   +1 more source

Fission chambers for space effect reduction in the application of the area method: A new approach

Nukleonika, 2020
The possibility of preparing fission chambers for the experimental determination of subcriticality without time-consuming corrections has been presented. The reactor detectors set consists of monoisotopic chambers. Each chamber is intended for a specific
Janczyszyn Jerzy A., Domańska Grażyna, Stanisz Przemysław   +2 more
doaj   +1 more source