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Статті в журналах з теми "Reactor physic"
Delpech, S., E. Merle-Lucotte, D. Heuer, M. Allibert, V. Ghetta, C. Le-Brun, X. Doligez, and G. Picard. "Reactor physic and reprocessing scheme for innovative molten salt reactor system." Journal of Fluorine Chemistry 130, no. 1 (January 2009): 11–17. http://dx.doi.org/10.1016/j.jfluchem.2008.07.009.
Повний текст джерелаYounan, Simon, and David R. Novog. "Development and Testing of TRACE/PARCS ECI Capability for Modelling CANDU Reactors with Reactor Regulating System Response." Science and Technology of Nuclear Installations 2022 (March 27, 2022): 1–31. http://dx.doi.org/10.1155/2022/7500629.
Повний текст джерелаNguyen, Nhi Dien, Ba Vien Luong, Vinh Vinh Le, Van Dong Duong, Xuan Hai Nguyen, Ngoc Son Pham, and Dong Vu Cao. "Results of Operation and Utilization of the Dalat Nuclear Research Reactor." Nuclear Science and Technology 4, no. 1 (March 30, 2014): 1–9. http://dx.doi.org/10.53747/jnst.v4i1.208.
Повний текст джерелаPascal, V., Y. Gorsse, N. Alpy, K. Ammar, M. Anderhuber, AM Baudron, G. Campioni, et al. "MULTIPHYSICS MODELISATION OF AN UNPROTECTED LOSS OF FLOW TRANSIENT IN A SODIUM COOLED FAST REACTORS USING A NEUTRONIC-THERMAL-HYDRAULIC COUPLING SCHEME." EPJ Web of Conferences 247 (2021): 07001. http://dx.doi.org/10.1051/epjconf/202124707001.
Повний текст джерелаNowak, Agata, Robert Mazur, Ewa Panek, and Joanna Chmist. "Model Studies on the Effectiveness of MBBR Reactors for the Restoration of Small Water Reservoirs." E3S Web of Conferences 30 (2018): 02004. http://dx.doi.org/10.1051/e3sconf/20183002004.
Повний текст джерелаMaria F, Lencina, Robinson Ada J, Rearte Samanta M, and Albarracín Patricia M. "Production of unicelular protein and reduction of contaminating amount of vinasse." Journal of Applied Biotechnology & Bioengineering 9, no. 6 (December 26, 2022): 229–31. http://dx.doi.org/10.15406/jabb.2022.09.00315.
Повний текст джерелаAhmad Latiffi, Nur Atikah, Radin Maya Saphira Radin Mohamed, Najeeha Mohd Apandi, and Amir Hashim Mohd Kassim. "Application of Phycoremediation Using Microalgae Scenedesmus sp. as Wastewater Treatment in Removal of Heavy Metals from Food Stall Wastewater." Applied Mechanics and Materials 773-774 (July 2015): 1168–72. http://dx.doi.org/10.4028/www.scientific.net/amm.773-774.1168.
Повний текст джерелаFoffi, Rachele, Elisa Savuto, Matteo Stante, Roberta Mancini, and Katia Gallucci. "Study of Energy Valorization of Disposable Masks via Thermochemical Processes: Devolatilization Tests and Simulation Approach." Energies 15, no. 6 (March 13, 2022): 2103. http://dx.doi.org/10.3390/en15062103.
Повний текст джерелаСмолин and V. Smolin. "Mathematical Simulation of Biotechnical Scanner to Determine Hydration Degrees a Biological Tissue in Norme and at Different Pathologies." Journal of New Medical Technologies 22, no. 1 (February 11, 2015): 11–16. http://dx.doi.org/10.12737/9068.
Повний текст джерелаKatsioulas, I., I. Savvidis, and C. Eleftheriadis. "Nuclear Reactor Neutrino Detection with the Spherical Proportional Counter." HNPS Proceedings 21 (March 8, 2019): 92. http://dx.doi.org/10.12681/hnps.2010.
Повний текст джерелаДисертації з теми "Reactor physic"
Pope, Michael A. (Michael Alexander). "Reactor physics design of supercritical CO₂-cooled fast reactors." Thesis, Massachusetts Institute of Technology, 2004. http://hdl.handle.net/1721.1/33633.
Повний текст джерелаIncludes bibliographical references (p. 109-113).
Gas-Cooled Fast Reactors (GFRs) are among the GEN-IV designs proposed for future deployment. Driven by anticipated plant cost reduction, the use of supercritical CO₂ (S-CO₂) as a Brayton cycle working fluid in a direct cycle is evaluated. By using S- CO₂ at turbine inlet conditions of 20 MPa and 550⁰C - 700⁰C, efficiencies between 45% and 50% can be achieved with extremely compact components. Neutronic evaluation of candidate core materials was performed for potential use in block-type matrix fueled GFRs with particular concentration on lowering coolant void reactivity to less than $1. SiC cercer fuel was found to have relatively low coolant void worth (+22 cents upon complete depressurization of S-CO₂ coolant) and tolerable reactivity- limited burnup at matrix volume fractions of 60% or less in a 600 MWth core having H/D of 0.85 and titanium reflectors. Pin-type cores were also evaluated and demonstrated higher kff versus burnup, and higher coolant void reactivity than the SiC cercer cores (+$2.00 in ODS MA956-clad case having H/D of 1).
(cont.) It was shown, however, that S-CO₂ coolant void reactivity could be lowered significantly - to less than $1 - in pin cores by increasing neutron leakage (e.g. lowering the core H/D ratio to 0.625 in a pin core with ODS MA956 cladding), an effect not observed in cores using helium coolant at 8 MPa and 500⁰C. An innovative "block"-geometry tube-in-duct fuel consisting of canisters of vibrationally compacted (VIPAC) oxide fuel was introduced and some preliminary calculations were performed. A reference tube-in-duct core was shown to exhibit favorable neutron economy with a conversion ratio (CR) at beginning of life (BOL) of 1.37, but had a coolant void reactivity of +$ 1.4. The high CR should allow designers to lower coolant void worth by increasing leakage while preserving the ability of the core to reach high burnup. Titanium, vanadium and scandium were found to be excellent reflector materials from the standpoint of ... and coolant void reactivity due to their unique elastic scattering cross-section profiles: for example, the SiC cercer core having void reactivity of +$0.22 with titanium was shown to have +$0.57 with Zr₃Si₂.
(cont.) Overall, present work confirmed that the S-CO₂-cooled GFR concept has promising characteristics and a sufficiently broad opion space such that a safe and competitive design could be developed in future work with considerably less than $1 void reactivity and a controllable [delta]k due to burnup.
by Michael A. Pope.
S.M.
Sadeghi, Mohammad Mehdi 1959. "SYMBOLIC MANIPULATION IN REACTOR PHYSICS." Thesis, The University of Arizona, 1986. http://hdl.handle.net/10150/275520.
Повний текст джерелаBora, Pekicten Aziz. "Assembly homogenization of light water reactors by a monte carlo reactor physics method and verification by a deterministic method." Thesis, KTH, Kärnkraftsäkerhet, 2011. http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-34492.
Повний текст джерелаGottfridsson, Filip. "Simulation of Reactor Transient and Design Criteria of Sodium-cooled Fast Reactors." Thesis, Uppsala universitet, Tillämpad kärnfysik, 2010. http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-148572.
Повний текст джерелаGonzalez, Vargas Jose Angel [Verfasser], and R. [Akademischer Betreuer] Stieglitz. "Advanced Reactor Physics Methods for Transient Analysis of Boiling Water Reactors / Jose Angel Gonzalez Vargas ; Betreuer: R. Stieglitz." Karlsruhe : KIT-Bibliothek, 2017. http://d-nb.info/1148551336/34.
Повний текст джерелаBrinkmann, Torsten. "Use of catalytic membrane reactors for in situ reaction and separation." Thesis, University of Bath, 1999. https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.301546.
Повний текст джерелаEmmett, John Carter Alfred. "A standard neutron spectrum source of application to fast reactor physics." Thesis, Imperial College London, 2000. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.312126.
Повний текст джерелаChristensen, Eric Kurt. "Applications of Neutrino Physics." Diss., Virginia Tech, 2014. http://hdl.handle.net/10919/64864.
Повний текст джерелаPh. D.
MAEDA, REINALDO de M. "Determinação experimental de parâmetros de física de reatores utilizando refletor de água pesada no reator IPEN/MB-01." reponame:Repositório Institucional do IPEN, 2012. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10128.
Повний текст джерелаMade available in DSpace on 2014-10-09T14:00:44Z (GMT). No. of bitstreams: 0
Dissertação (Mestrado)
IPEN/D
Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP
Tuttelberg, Kaur. "STORM in Monte Carlo reactor physics calculations." Thesis, KTH, Fysik, 2014. http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-146284.
Повний текст джерелаКниги з теми "Reactor physic"
Nuclear reactor physics. 2nd ed. Weinheim: Wiley-VCH, 2007.
Знайти повний текст джерелаStacey, Weston M. Nuclear Reactor Physics 3e. Weinheim, Germany: Wiley-VCH Verlag GmbH & Co. KGaA, 2018. http://dx.doi.org/10.1002/9783527812318.
Повний текст джерелаMasterson, Robert E. Introduction to Nuclear Reactor Physics. Boca Raton : Taylor & Francis, a CRC title, part of the Taylor & Francis imprint, a member of the Taylor & Francis Group, the academic division of T&F Informa, plc, [2017]: CRC Press, 2017. http://dx.doi.org/10.1201/9781315118055.
Повний текст джерелаLewis, E. E. Fundamentals of nuclear reactor physics. Amsterdam: Academic Press, 2008.
Знайти повний текст джерелаLewis, E. E. Fundamentals of nuclear reactor physics. Amsterdam: Academic Press, 2008.
Знайти повний текст джерелаLewis, E. E. Fundamentals of nuclear reactor physics. Amsterdam: Academic Press, 2008.
Знайти повний текст джерелаGlasstone, Samuel. Nuclear Reactor Engineering: Reactor Systems Engineering. Boston, MA: Springer US, 1994.
Знайти повний текст джерелаHerman, M., and Nello Paver. Nuclear reaction data and nuclear reactors: [Workshop on Nuclear Reaction Data and Nuclear Reactors: Physics, Design and Safety, 25 February - 28 March 2002]. Trieste: Abdus Salam International Centre for Theoretical Physics, 2005.
Знайти повний текст джерелаCentre, Bhabha Atomic Research, ed. Operational reactor physics analysis codes (ORPAC). Mumbai: Bhabha Atomic Research Centre, 2007.
Знайти повний текст джерелаMarguet, Serge. The Physics of Nuclear Reactors. Cham: Springer International Publishing, 2017. http://dx.doi.org/10.1007/978-3-319-59560-3.
Повний текст джерелаЧастини книг з теми "Reactor physic"
Bignan, Gilles, Philippe Fougeras, Patrick Blaise, Jean-Pascal Hudelot, and Frédéric Mellier. "Reactor Physics Experiments on Zero Power Reactors." In Handbook of Nuclear Engineering, 2053–184. Boston, MA: Springer US, 2010. http://dx.doi.org/10.1007/978-0-387-98149-9_18.
Повний текст джерелаNatelson, Michael. "Fission Reactor Physics fission reactor physics." In Encyclopedia of Sustainability Science and Technology, 3787–820. New York, NY: Springer New York, 2012. http://dx.doi.org/10.1007/978-1-4419-0851-3_18.
Повний текст джерелаLakey, J. R. A., and R. E. Alexander. "Developments in Health Physics Dosimetry." In Reactor Dosimetry, 951–58. Dordrecht: Springer Netherlands, 1985. http://dx.doi.org/10.1007/978-94-010-9726-0_44.
Повний текст джерелаLakey, J. R. A., and R. E. Alexander. "Developments in Health Physics Dosimetry." In Reactor Dosimetry, 951–58. Dordrecht: Springer Netherlands, 1985. http://dx.doi.org/10.1007/978-94-009-5378-9_96.
Повний текст джерелаMikityuk, K. "Fast Reactor Physics." In Thorium Energy for the World, 215–21. Cham: Springer International Publishing, 2016. http://dx.doi.org/10.1007/978-3-319-26542-1_33.
Повний текст джерелаWakabayashi, Genichiro, Takahiro Yamada, Tomohiro Endo, and Cheol Ho Pyeon. "Reactor Physics Experiments." In Introduction to Nuclear Reactor Experiments, 47–85. Singapore: Springer Nature Singapore, 2022. http://dx.doi.org/10.1007/978-981-19-6589-0_2.
Повний текст джерелаNatelson, Michael. "Fission Reactor Physics." In Nuclear Energy, 5–40. New York, NY: Springer New York, 2018. http://dx.doi.org/10.1007/978-1-4939-6618-9_18.
Повний текст джерелаNatelson, Michael. "Fission Reactor Physics." In Nuclear Energy, 7–57. New York, NY: Springer New York, 2012. http://dx.doi.org/10.1007/978-1-4614-5716-9_2.
Повний текст джерелаNatelson, Michael. "Fission Reactor Physics." In Encyclopedia of Sustainability Science and Technology, 1–38. New York, NY: Springer New York, 2016. http://dx.doi.org/10.1007/978-1-4939-2493-6_18-3.
Повний текст джерелаFabry, A., and A. Lowe. "Workshop “LWR-PV Physics, Dosimetry, Damage Correlation and Materials Problems”." In Reactor Dosimetry, 999. Dordrecht: Springer Netherlands, 1985. http://dx.doi.org/10.1007/978-94-010-9726-0_49.
Повний текст джерелаТези доповідей конференцій з теми "Reactor physic"
Cerba, Š., V. Necas, and J. Lüley. "Determination of the Dosimetry Situation in Reactor Physic Laboratory of SUT in Bratislava." In 2020 ANS Virtual Winter Meeting. AMNS, 2020. http://dx.doi.org/10.13182/t123-33337.
Повний текст джерелаAtong, Duangduen, and Viboon Sricharoenchaikul. "Thermal Conversion of Mixed Wastes From Biodiesel Manufacturing for Production of Fuel Gas." In ASME 2009 3rd International Conference on Energy Sustainability collocated with the Heat Transfer and InterPACK09 Conferences. ASMEDC, 2009. http://dx.doi.org/10.1115/es2009-90200.
Повний текст джерелаDeng, Jiaolong, Xiang Chai, Tengfei Zhang, and Xiaojing Liu. "Conceptual Multi-Physic Coupling Simulation on Transient Operations Of a He-Xe Cooled Mobile Nuclear Power Plant." In 2022 29th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2022. http://dx.doi.org/10.1115/icone29-92247.
Повний текст джерелаLin, Bo, Sui-zheng Qiu, Guang-hui Su, Wen-xi Tian, and Ya-pei Zhang. "Simulation of Molten Corium Concrete Interaction With the MOCO Code." In 2014 22nd International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2014. http://dx.doi.org/10.1115/icone22-30345.
Повний текст джерелаObložinský, P., and A. Gandini. "Nuclear Reaction Data and Nuclear Reactors – Physics, Design and Safety." In Workshop on Nuclear Reaction Data and Nuclear Reactors. WORLD SCIENTIFIC, 1999. http://dx.doi.org/10.1142/9789814527392.
Повний текст джерелаKemah, Elif, Recep Akkaya, and Seyit Rıza Tokgöz. "Comparing the new generation accelerator driven subcritical reactor system (ADS) to traditional critical reactors." In TURKISH PHYSICAL SOCIETY 32ND INTERNATIONAL PHYSICS CONGRESS (TPS32). Author(s), 2017. http://dx.doi.org/10.1063/1.4976409.
Повний текст джерелаLevine, S. H. "Basic Reactor Physics." In Proceedings of the Workshop. WORLD SCIENTIFIC, 1991. http://dx.doi.org/10.1142/9789814439398_0007.
Повний текст джерелаJoseph, Jofred, Satish Kumar, Tanmay Vasal, and N. Theivarajan. "Brayton Cycle As an Alternate Power Conversion Option for Sodium Cooled Fast Reactor." In ASME 2019 Gas Turbine India Conference. American Society of Mechanical Engineers, 2019. http://dx.doi.org/10.1115/gtindia2019-2455.
Повний текст джерелаBrown, N., E. Duchnowski, L. Snead, and J. Trelewicz. "Preliminary Reactor Physics Analysis of Alternative Moderators for Modular High Temperature Gas-Cooled Reactors." In Tranactions - 2019 Winter Meeting. AMNS, 2019. http://dx.doi.org/10.13182/t31307.
Повний текст джерелаRastogi, B. P. "REACTOR PHYSICS IN INDIA." In ACIF's First Course on Nuclear Physics and Reactors. WORLD SCIENTIFIC, 1986. http://dx.doi.org/10.1142/9789814415569_0003.
Повний текст джерелаЗвіти організацій з теми "Reactor physic"
Cleveland, J. (Safety related reactor physics calculation for HTGR type reactors). Office of Scientific and Technical Information (OSTI), October 1989. http://dx.doi.org/10.2172/5381930.
Повний текст джерелаSanchez, Rene, Travis Grove, and William Myers. Module 10 Reactor Physics. Office of Scientific and Technical Information (OSTI), January 2021. http://dx.doi.org/10.2172/1756787.
Повний текст джерелаBrady, M. (Physics of reactors). Office of Scientific and Technical Information (OSTI), May 1990. http://dx.doi.org/10.2172/6986759.
Повний текст джерелаPetrie, L., and G. Whitesides. (Reactor physics and criticality safety). Office of Scientific and Technical Information (OSTI), June 1990. http://dx.doi.org/10.2172/6841470.
Повний текст джерелаIlas, Germina, Joseph Burns, Briana Hiscox, and Ugur Mertyurek. SCALE 6.2.4 Validation: Reactor Physics. Office of Scientific and Technical Information (OSTI), November 2022. http://dx.doi.org/10.2172/1902818.
Повний текст джерелаPerry, R. T., and G. H. Meriwether. A WIMS-NESTLE reactor physics model for an RBMK reactor. Office of Scientific and Technical Information (OSTI), August 1996. http://dx.doi.org/10.2172/266875.
Повний текст джерелаSims, C. S., and G. E. Ragan. Health physics research reactor reference dosimetry. Office of Scientific and Technical Information (OSTI), June 1987. http://dx.doi.org/10.2172/6440156.
Повний текст джерелаAuthor, Not Given. Technical specifications: Health Physics Research Reactor. Office of Scientific and Technical Information (OSTI), March 1986. http://dx.doi.org/10.2172/6249628.
Повний текст джерелаPope, Chad L., Edward S. Lum, Ryan Stewart, Bilguun Byambadorj, and Quinton Beaulieu. EBR-II Reactor Physics Benchmark Evaluation Report. Office of Scientific and Technical Information (OSTI), December 2017. http://dx.doi.org/10.2172/1415120.
Повний текст джерелаWachs, Daniel. Transient Test Reactor Physics Workshop - May 2016. Office of Scientific and Technical Information (OSTI), May 2016. http://dx.doi.org/10.2172/1504917.
Повний текст джерела