Literatura académica sobre el tema "NUCLEAR REACTOR SYSTEMS"
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Artículos de revistas sobre el tema "NUCLEAR REACTOR SYSTEMS"
Petti, D., D. Crawford y N. Chauvin. "Fuels for Advanced Nuclear Energy Systems". MRS Bulletin 34, n.º 1 (enero de 2009): 40–45. http://dx.doi.org/10.1557/mrs2009.11.
Texto completoCaciuffo, R., C. Fazio y C. Guet. "Generation-IV nuclear reactor systems". EPJ Web of Conferences 246 (2020): 00011. http://dx.doi.org/10.1051/epjconf/202024600011.
Texto completoLarge, J. H. "Decommissioning of Nuclear Reactor Systems". Proceedings of the Institution of Mechanical Engineers, Part A: Journal of Power and Energy 206, n.º 4 (noviembre de 1992): 273–80. http://dx.doi.org/10.1243/pime_proc_1992_206_044_02.
Texto completoHiscox, Briana, Benjamin Betzler, Vladimir Sobes y William J. Marshall. "NEUTRONIC BENCHMARKING OF SMALL GAS-COOLED SYSTEMS". EPJ Web of Conferences 247 (2021): 10033. http://dx.doi.org/10.1051/epjconf/202124710033.
Texto completoSaha, Dilip y John Cleveland. "Natural Circulation in Nuclear Reactor Systems". Science and Technology of Nuclear Installations 2008 (2008): 1. http://dx.doi.org/10.1155/2008/932319.
Texto completoMoore, Julian. "Upgrading of nuclear reactor display systems". Electronics and Power 32, n.º 10 (1986): 735. http://dx.doi.org/10.1049/ep.1986.0429.
Texto completoBonal, Jean-Pierre, Akira Kohyama, Jaap van der Laan y Lance L. Snead. "Graphite, Ceramics, and Ceramic Composites for High-Temperature Nuclear Power Systems". MRS Bulletin 34, n.º 1 (enero de 2009): 28–34. http://dx.doi.org/10.1557/mrs2009.9.
Texto completoKondylakis, J. S. "Theoretically and under very special applied conditions a nuclear fission reactor may explode as nuclear bomb". HNPS Proceedings 18 (23 de noviembre de 2019): 121. http://dx.doi.org/10.12681/hnps.2558.
Texto completoSutopo, Catur Febriyanto y Arifin M. Susanto. "Kajian pembentukan peraturan mengenai sistem pendingin reaktor dan sistem terkait untuk reaktor berpendingin gas". Jurnal Pengawasan Tenaga Nuklir 1, n.º 2 (15 de diciembre de 2021): 11–19. http://dx.doi.org/10.53862/jupeten.v1i2.014.
Texto completoObaidurrahman, Khalilurrahman y Om Singh. "A comparative study of kinetics of nuclear reactors". Nuclear Technology and Radiation Protection 24, n.º 3 (2009): 167–76. http://dx.doi.org/10.2298/ntrp0903167o.
Texto completoTesis sobre el tema "NUCLEAR REACTOR SYSTEMS"
Anadani, Mohamed. "Decision support systems for nuclear reactor control". Thesis, University of Sheffield, 2000. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.341828.
Texto completoPresby, Andrew L. "Thermophotovoltaic energy conversion in space nuclear reactor power systems". Thesis, Monterey, Calif. : Naval Postgraduate School, 2004. http://edocs.nps.edu/npspubs/scholarly/theses/2004/Dec/04Dec%5FPresby.pdf.
Texto completoThesis Advisor(s): Gopinath, Ashok ; Michael, Sherif. "December 2004." Description based on title screen as viewed on March 13, 2009. Includes bibliographical references (p. 123-127). Also available in print.
CARVALHO, LUIZ S. "Frequencia de danos no nucleo por blecaute em reator nuclear de concepcao avancada". reponame:Repositório Institucional do IPEN, 2004. http://repositorio.ipen.br:8080/xmlui/handle/123456789/11147.
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Dissertacao (Mestrado)
IPEN/D
Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP
Kim, Choong Seok. "Reliability assessment of pressurized water reactor auxiliary feedwater systems". Diss., Georgia Institute of Technology, 1985. http://hdl.handle.net/1853/13374.
Texto completoPersson, Carl-Magnus. "Reactivity Assessment in Subcritical Systems". Licentiate thesis, Stockholm : Fysiska institutionen, Kungliga Tekniska högskolan, 2007. http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-4363.
Texto completoWitter, Jonathan Keay. "Modeling for the simulation and control of nuclear reactor rocket systems". Thesis, Massachusetts Institute of Technology, 1993. http://hdl.handle.net/1721.1/12755.
Texto completoWu, Xiao. "Design of a Tritium Mitigation and Control System for Fluoride-salt-cooled High-temperature Reactor Systems". The Ohio State University, 2016. http://rave.ohiolink.edu/etdc/view?acc_num=osu1452249907.
Texto completoJohnson, Kyle D. "High Performance Fuels for Water-Cooled Reactor Systems". Doctoral thesis, KTH, Reaktorfysik, 2016. http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-201604.
Texto completoUnder artionden har forskning om nitridbranseln och dess egenskaper bedrivits pa grundval av nitridbransletsatravarda egenskaper avseende dess hoga metall tathet och hog varmeledningsformaga. Dessa egenskaper besitter vasentliga fordelar avseende prestanda, ekonomi och sakerhet for metallkylda som lattvatten reaktorer. Genom forskning har aven centrala begr ansningar identierats for implementering av nitridbranslen for kommersiellt bruk. Begransningar avser den kemiska interaktionen med luft och vattenanga, en uppmarksammad svarighet att sintring av materialet samt hoga kostnader forknippade med den nodvandiga anrikningen av 15-N. Kombinationen av dessa begransningar resulterade, tidigare, i en valgrundad slutsats att nitridbranslet mest andamalsenliga anvandningsomrade var i karnbranslecykeln for snabba reaktorer. Detta da kostnaderna forenade med implementeringen av branslet ar avsevart lagre. Inom detta sammanhang har majoriteten av forskning avseende nitrider bedrivits och fortskrider an idag. Dock, efter karnkraftsolyckan i Fukushima-Daiichi 2011, inleddes en samlad industriell och statlig anstrangning for att undersoka alternativ till sa kallade \olyckstoleranta" och \hogpresterande" branslen. Dessa branslen skulle samtidigt forbattra reaktionstiden for bransleinkapsling systemet mot allvarliga olyckor samt forbattra driftsekonomin av lattvattenreaktorer. Foreslagna kandidater ar urannitrid, uransilicid och en tredje \uran nitrid-silicid", komposit bestaende av en blandning av de foregaende. Genom denna avhandling har en metod faststallts for syntes, tillverkning och karaktarisering av uran nitrid av hog renhet samt uran nitrid-silicid kompositer, forberedda med tekniken SPS (Spark Plasma Sintering). Ett specikt resultat har varit att isolera eekten av processparametrar pa mikrostrukturen pa representativa branslekutsar. Detta mojliggor, i princip, framstallningen av alla tankbara mikrostrukturer utav intresse for tillverkning. Vidare har detta mojliggjort utvecklingen av en hogeligen reproducerbar teknik for framstallningen av branslekutsar med mikrostrukturer skraddarsydda for onskad porositet mellan 88 och 99.9 % TD, och kornstorlek mellan 6 och 24 μm. Dartill har en metod for att belagga en matris av uran nitrid-silicid framarbetats. Detta har mojliggjort utvarderingen av dessa mikrostrukturella parametrars paverkan pa materialens prestanda, sarskilt avseende dess roll som olyckstoleranta branslen. Detta har genererat resultat som ar tatt sammanlankat nitridbranslets prestanda till kutsens mikrostruktur, med viktiga konsekvenser for den potentiella anvandningen av nitrider i lattvatten reaktorer.
QC 20170210
CONCEICAO, JUNIOR OSMAR. "Aplicacao da tecnica de analise de modos de falha e efeitos ao sistema de resfriamento de emergencia de uma instalacao nuclear experimental". reponame:Repositório Institucional do IPEN, 2009. http://repositorio.ipen.br:8080/xmlui/handle/123456789/9367.
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Dissertacao (Mestrado)
IPEN/D
Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP
Morrison, Jonathan J. "Corrosion, transport, and deposition in pressurised water nuclear reactor primary coolant systems". Thesis, University of Birmingham, 2016. http://etheses.bham.ac.uk//id/eprint/6816/.
Texto completoLibros sobre el tema "NUCLEAR REACTOR SYSTEMS"
Glasstone, Samuel. Nuclear Reactor Engineering: Reactor Systems Engineering. Boston, MA: Springer US, 1994.
Buscar texto completoZohuri, Bahman. Neutronic Analysis For Nuclear Reactor Systems. Cham: Springer International Publishing, 2019. http://dx.doi.org/10.1007/978-3-030-04906-5.
Texto completoZohuri, Bahman. Neutronic Analysis For Nuclear Reactor Systems. Cham: Springer International Publishing, 2017. http://dx.doi.org/10.1007/978-3-319-42964-9.
Texto completoMyers, Lynne C. Nuclear power systems: Their safety. [Ottawa]: Library of Parliament, Research Branch, 1989.
Buscar texto completoMyers, Lynne C. Nuclear power systems: Their safety. [Ottawa]: Library of Parliament, Research Branch, 1996.
Buscar texto completoUnited States. National Aeronautics and Space Administration., ed. Small space reactor power systems for unmanned solar system exploration missions. [Washington, D.C.]: National Areonautics and Space Administration, 1987.
Buscar texto completoLawrence, J. D. Software reliability and safety in nuclear reactor protection systems. Washington, DC: Division of Reactor Controls and Human Factors, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1993.
Buscar texto completoJalel, N. A. Expert systems for fault diagnosis in nuclear reactor control. Sheffield: University of Sheffield, Dept. of Control Engineering, 1990.
Buscar texto completoLawrence, Jim. Software reliability and safety in nuclear reactor protection systems. Washington, DC: Division of Reactor Controls and Human Factors, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1993.
Buscar texto completoU.S. Nuclear Regulatory Commission. Division of Reactor Controls and Human Factors. y Lawrence Livermore National Laboratory, eds. Reviewing real-time performance of nuclear reactor safety systems. Washington, DC: Division of Reactor Controls and Human Factors, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1993.
Buscar texto completoCapítulos de libros sobre el tema "NUCLEAR REACTOR SYSTEMS"
Glasstone, Samuel y Alexander Sesonske. "Power Reactor Systems". En Nuclear Reactor Engineering, 759–90. Boston, MA: Springer US, 1994. http://dx.doi.org/10.1007/978-1-4615-2083-2_6.
Texto completoGlasstone, Samuel y Alexander Sesonske. "Power Reactor Systems". En Nuclear Reactor Engineering, 759–90. Boston, MA: Springer US, 1994. http://dx.doi.org/10.1007/978-1-4615-7525-2_13.
Texto completoGlasstone, Samuel y Alexander Sesonske. "The Systems Concept, Design Decisions, and Information Tools". En Nuclear Reactor Engineering, 487–500. Boston, MA: Springer US, 1994. http://dx.doi.org/10.1007/978-1-4615-2083-2_1.
Texto completoGlasstone, Samuel y Alexander Sesonske. "The Systems Concept, Design Decisions, and Information Tools". En Nuclear Reactor Engineering, 487–500. Boston, MA: Springer US, 1994. http://dx.doi.org/10.1007/978-1-4615-7525-2_8.
Texto completoTodreas, Neil E. y Mujid S. Kazimi. "Reactor Energy Distribution". En Nuclear Systems Volume I, 71–122. Third edition. | Boca Raton : CRC Press, 2021- |: CRC Press, 2021. http://dx.doi.org/10.1201/9781351030502-3.
Texto completoZohuri, Bahman. "Reactor Dynamics". En Neutronic Analysis For Nuclear Reactor Systems, 435–57. Cham: Springer International Publishing, 2016. http://dx.doi.org/10.1007/978-3-319-42964-9_12.
Texto completoZohuri, Bahman. "Reactor Stability". En Neutronic Analysis For Nuclear Reactor Systems, 459–74. Cham: Springer International Publishing, 2016. http://dx.doi.org/10.1007/978-3-319-42964-9_13.
Texto completoZohuri, Bahman. "Reactor Dynamics". En Neutronic Analysis For Nuclear Reactor Systems, 427–49. Cham: Springer International Publishing, 2019. http://dx.doi.org/10.1007/978-3-030-04906-5_12.
Texto completoZohuri, Bahman. "Reactor Stability". En Neutronic Analysis For Nuclear Reactor Systems, 451–65. Cham: Springer International Publishing, 2019. http://dx.doi.org/10.1007/978-3-030-04906-5_13.
Texto completoTodreas, Neil E., Mujid S. Kazimi y Mahmoud Massoud. "Fundamentals of Reactor Transient Simulation". En Nuclear Systems Volume II, 443–75. 2a ed. Boca Raton: CRC Press, 2021. http://dx.doi.org/10.1201/9780429157608-12.
Texto completoActas de conferencias sobre el tema "NUCLEAR REACTOR SYSTEMS"
Yamamoto, Takahisa, Koshi Mitachi y Masatoshi Nishio. "Reactor Controllability of 3-Region-Core Molten Salt Reactor System: A Study on Load Following Capability". En 14th International Conference on Nuclear Engineering. ASMEDC, 2006. http://dx.doi.org/10.1115/icone14-89440.
Texto completoBakhmach, Ievgenii S., Alexander A. Siora, Volodymyr T. Bezsalyi y Mikhail A. Yastrebenetsky. "Digital Systems for Reactor Control: Design, Experience of Operation". En 16th International Conference on Nuclear Engineering. ASMEDC, 2008. http://dx.doi.org/10.1115/icone16-48205.
Texto completoYastrebenetsky, Mikhail A., Alexander A. Siora y Volodymyr I. Tokarev. "Reliability of Reactor Control Digital Systems". En 17th International Conference on Nuclear Engineering. ASMEDC, 2009. http://dx.doi.org/10.1115/icone17-75157.
Texto completoLawrence, Leo A., Bruce J. Makenas y Les L. Begg. "Performance of fast reactor irradiated fueled emitters for thermionic reactors". En Proceedings of the ninth symposium on space nuclear power systems. AIP, 1992. http://dx.doi.org/10.1063/1.41886.
Texto completoGese, Augustin, Michal Kopcek y Alojz Meszaros. "Signal filtering for a nuclear reactor restarting". En 2012 6th IEEE International Conference Intelligent Systems (IS). IEEE, 2012. http://dx.doi.org/10.1109/is.2012.6335162.
Texto completoKononov, V. N., M. V. Bokhovko, P. P. Dyachenko, V. V. Korobkin, Yu A. Prokhorov, V. I. Regushevskiv y V. N. Smolskiy. "Nuclear Reactor Pumped Lasing Experiments on Fast Burst Reactor". En The European Conference on Lasers and Electro-Optics. Washington, D.C.: Optica Publishing Group, 1996. http://dx.doi.org/10.1364/cleo_europe.1996.ctud7.
Texto completoVijayakumaran, P. M., C. P. Nagaraj, C. Paramasivan Pillai, R. Ramakrishnan y M. Sivaramakrishna. "Nuclear Instrumentation Systems in Prototype Fast Breeder Reactor". En 12th International Conference on Nuclear Engineering. ASMEDC, 2004. http://dx.doi.org/10.1115/icone12-49354.
Texto completoDeffrennes, Marc, Michel Hugon, Panagiotis Manolatos, Georges Van Goethem y Simon Webster. "Euratom Research Framework Programme on Reactor Systems". En 14th International Conference on Nuclear Engineering. ASMEDC, 2006. http://dx.doi.org/10.1115/icone14-89502.
Texto completoCheatham, Jesse, Bao Truong, Nicholas Touran, Ryan Latta, Mark Reed y Robert Petroski. "Fast Reactor Design Using the Advanced Reactor Modeling Interface". En 2013 21st International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2013. http://dx.doi.org/10.1115/icone21-16815.
Texto completoLewis, Bryan R., Ronald A. Pawlowski, Kevin J. Greek y Andrew C. Klein. "Advanced thermionic reactor systems design code". En Proceedings of the eighth symposium on space nuclear power systems. AIP, 1991. http://dx.doi.org/10.1063/1.40043.
Texto completoInformes sobre el tema "NUCLEAR REACTOR SYSTEMS"
Meyer, L. C. Nuclear plant-aging research on reactor protection systems. Office of Scientific and Technical Information (OSTI), enero de 1988. http://dx.doi.org/10.2172/5122402.
Texto completoShannon Bragg-Sitton, J. Michael Doster y Alan Rominger. Reactor Subsystem Simulation for Nuclear Hybrid Energy Systems. Office of Scientific and Technical Information (OSTI), septiembre de 2012. http://dx.doi.org/10.2172/1060985.
Texto completoLawrence, J. D. Software reliability and safety in nuclear reactor protection systems. Office of Scientific and Technical Information (OSTI), noviembre de 1993. http://dx.doi.org/10.2172/10108329.
Texto completoPreckshot, G. G. Reviewing real-time performance of nuclear reactor safety systems. Office of Scientific and Technical Information (OSTI), agosto de 1993. http://dx.doi.org/10.2172/10178197.
Texto completoHawrylak, Peter, John Hale, Mauricio Papa, Donald Wall, Corey Hines, Thomas Edgar y Philip Craig. Cyber Security Analysis for Nuclear Reactor Control Systems. Final Technical Report. Office of Scientific and Technical Information (OSTI), diciembre de 2020. http://dx.doi.org/10.2172/1650024.
Texto completoPalomar, J. y R. Wyman. The Programmable Logic Controller and its application in nuclear reactor systems. Office of Scientific and Technical Information (OSTI), septiembre de 1993. http://dx.doi.org/10.2172/10185827.
Texto completoBrittain, C. R., P. J. Otaduy y R. B. Perez. Development of a general learning algorithm with applications in nuclear reactor systems. Office of Scientific and Technical Information (OSTI), diciembre de 1989. http://dx.doi.org/10.2172/5273390.
Texto completoAnderson, Mark, Kumar Sridharan, Dane Morgan, Per Peterson, Pattrick Calderoni, Randall Scheele, Andrew Casekka y Bruce McNamara. Heat Transfer Salts for Nuclear Reactor Systems - Chemistry Control, Corrosion Mitigation, and Modeling. Office of Scientific and Technical Information (OSTI), enero de 2015. http://dx.doi.org/10.2172/1169921.
Texto completoGallup, D. R. The scalability of OTR (out-of-core thermionic reactor) space nuclear power systems. Office of Scientific and Technical Information (OSTI), marzo de 1990. http://dx.doi.org/10.2172/6923465.
Texto completoProfessor Neill Todreas. Nuclear Systems Enhanced Performance Program, Maintenance Cycle Extension in Advanced Light Water Reactor Design. Office of Scientific and Technical Information (OSTI), octubre de 2001. http://dx.doi.org/10.2172/839057.
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