Добірка наукової літератури з теми "Fission Reactor Physic"
Оформте джерело за APA, MLA, Chicago, Harvard та іншими стилями
Ознайомтеся зі списками актуальних статей, книг, дисертацій, тез та інших наукових джерел на тему "Fission Reactor Physic".
Біля кожної праці в переліку літератури доступна кнопка «Додати до бібліографії». Скористайтеся нею – і ми автоматично оформимо бібліографічне посилання на обрану працю в потрібному вам стилі цитування: APA, MLA, «Гарвард», «Чикаго», «Ванкувер» тощо.
Також ви можете завантажити повний текст наукової публікації у форматі «.pdf» та прочитати онлайн анотацію до роботи, якщо відповідні параметри наявні в метаданих.
Статті в журналах з теми "Fission Reactor Physic"
Ripani, M. "Energy from nuclear fission." EPJ Web of Conferences 268 (2022): 00010. http://dx.doi.org/10.1051/epjconf/202226800010.
Повний текст джерелаRipani, M. "Energy from nuclear fission." EPJ Web of Conferences 246 (2020): 00010. http://dx.doi.org/10.1051/epjconf/202024600010.
Повний текст джерелаVerbeke, Jérôme M., Odile Petit, Abdelhazize Chebboubi, and Olivier Litaize. "Correlated Production and Analog Transport of Fission Neutrons and Photons using Fission Models FREYA, FIFRELIN and the Monte Carlo Code TRIPOLI-4® ." EPJ Web of Conferences 170 (2018): 01019. http://dx.doi.org/10.1051/epjconf/201817001019.
Повний текст джерелаBurgio, N., M. Carta, V. Fabrizio, L. Falconi, A. Gandini, R. Gatto, V. Peluso, E. Santoro, and M. B. Sciarretta. "SUBCRITICALITY MONITORING IN FUSION-FISSION HYBRID REACTORS." Problems of Atomic Science and Technology, Ser. Thermonuclear Fusion 44, no. 2 (2021): 27–41. http://dx.doi.org/10.21517/0202-3822-2021-44-2-27-41.
Повний текст джерелаMills, Robert W., David J. Mountford, Jonathon P. Coleman, Carl Metelko, Matthew Murdoch, and Yan-Jie Schnellbach. "Modelling of the anti-neutrino production and spectra from a Magnox reactor." EPJ Web of Conferences 170 (2018): 07008. http://dx.doi.org/10.1051/epjconf/201817007008.
Повний текст джерелаAnastasiou, Maria. "6Li(n,t)α reaction event-identification for the 235U(n,f)/6Li(n,t) cross section ratio measurement in the NIFFTE fissionTPC". HNPS Advances in Nuclear Physics 28 (17 жовтня 2022): 30–35. http://dx.doi.org/10.12681/hnps.3567.
Повний текст джерелаTonchev, Anton P., Jack A. Silano, Chris Hagmann, Roger Henderson, Mark A. Stoyer, Matthew Gooden, Todd Bredeweg, et al. "Toward short-lived and energy-dependent fission product yields from neutron-induced fission." EPJ Web of Conferences 239 (2020): 03001. http://dx.doi.org/10.1051/epjconf/202023903001.
Повний текст джерелаDavies, Sebastian, Dzianis Litskevich, Bruno Merk, Andrew Levers, Paul Bryce, and Anna Detkina. "DYN3D and CTF Coupling within a Multiscale and Multiphysics Software Development (Part II)." Energies 15, no. 13 (July 1, 2022): 4843. http://dx.doi.org/10.3390/en15134843.
Повний текст джерелаWinterberg, F. "Mini Fission-Fusion-Fission Explosions (Mini-Nukes). A Third Way Towards the Controlled Release of Nuclear Energy by Fission and Fusion." Zeitschrift für Naturforschung A 59, no. 6 (June 1, 2004): 325–36. http://dx.doi.org/10.1515/zna-2004-0603.
Повний текст джерелаLi, Jia, and Shanliang Zheng. "Feasibility Study to Byproduce Medical Radioisotopes in a Fusion Reactor." Molecules 28, no. 5 (February 22, 2023): 2040. http://dx.doi.org/10.3390/molecules28052040.
Повний текст джерелаДисертації з теми "Fission Reactor Physic"
ABRATE, NICOLO'. "Methods for safety and stability analysis of nuclear systems." Doctoral thesis, Politecnico di Torino, 2022. http://hdl.handle.net/11583/2971611.
Повний текст джерелаKennedy, William B. (William Blake) 1979. "Analysis of the MIT research reactor fission product and actinide radioactivity inventories." Thesis, Massachusetts Institute of Technology, 2004. http://hdl.handle.net/1721.1/32723.
Повний текст джерелаMIT Institute Archives copy: leaves 92-111 bound in reverse order.
Includes bibliographical references (leaf 57).
The current analysis of the MITR core radioactivity inventory eliminates unnecessary assumptions made in previous estimates of the inventory, and revises the list of contributory isotopes to include all actinide and fission product isotopes necessary for a proper accident source term calculation. The result is a power-history-dependent inventory that increases with bum-up, and comprises 41 actinide isotopes and 596 fission product isotopes. The analysis uses the ORIGEN2 depletion code to calculate the activity of actinide and fission product isotopes for eight MITR input models at 32 intervals over a period of 5376MWD. The input models simulate a MITR core loaded with high- enrichment, U-Alx cermet fuel or low-enrichment, monolithic U-Mo fuel, and operated at 6MW with a continuous-burn-up or cyclic-burn-up-and-decay power history. Reorganization of the ORIGEN2 output file, and application of an element reduction criterion creates the condensed matrix file for each MITR input model. This file lists the contribution of each isotope to the core radioactivity inventory at each output interval, and is the basis for all inventory analysis. The inventory analysis yields three important conclusions. First, the assumption of an equilibrium inventory of isotopes in the fuel is accurate to within 3% for all time after 10% fuel bum-up, and conservative over the entire fuel cycle. The equilibrium fuel assumption is invalid for the actinides due to a slow rate of inventory growth. Second, the cyclic-bum-up-and-decay power history yields a lower core inventory than the continuous-burn-up power history for both fuel enrichments. The difference is minimized by increasing the ratio of irradiation time to decay time.
(cont.) Finally, the analysis indicates that conversion to a U-Mo fuel will produce an actinide inventory 18 times greater than that of the current U-Alx fuel, with no significant change in the fission product inventory. However, the actinide inventory is a small fraction of the fission product inventory. The worst-case core inventory available for release is 2.91 E+7Ci for the high-enrichment fuel, and 2.94E+7Ci for the low-enrichment fuel, with a core loading of 24 elements in each case. The best-estimate core inventory available for release is 2.83E+7Ci, and 2.82E+7Ci respectively, and accounts for typical cyclic operation of the MITR.
by William B. Kennedy.
S.B.
Lapinski, Felicia. "Experimental studies at CERN-nTOF of the 230Th(n,f) reaction." Thesis, Uppsala universitet, Tillämpad kärnfysik, 2020. http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-417867.
Повний текст джерелаDetta projekt undersöker genomförbarheten av ett experiment vid CERN n_TOF för att mäta tvärsnittet och fördelningen av emissionsvinklar av fissionsfragment (FFAD) från 230Th(n,f)-reaktionen. En analys av energiförlusterna av fissionsfragment inuti torium-provet resulterade i en optimal provtjocklek på 0.1 µm (100 µg/cm2 ), vilket medför att fissionsfragment som emitteras i vinklar upp till 45° från provets normal har hög sannolikhet att transmitteras ut ur provet. En detektionsuppställning med tio PPAC-detektorer med nio toriumprov mellan dem undersöktes, där detektorerna och proven antogs vara snedställda med 45° från neutronstrålens riktning. Detta möjliggör detektion av fissionsfragment i alla vinklar som är nödvändiga för att kunna mäta hela FFAD. För experimentanläggningen EAR2 vid n_TOF, resulterade en uppskattning av antalet detekterade fissionsevent per sekund i låga mätosäkerheter efter ett par veckor av mättid, vilket antyder att experimentet är görbart.
Kern, Kilian [Verfasser]. "Advanced Treatment of Fission Yield Effects and Method Development for Improved Reactor Depletion Calculations / Kilian Kern." Karlsruhe : KIT Scientific Publishing, 2019. http://www.ksp.kit.edu.
Повний текст джерелаKern, Kilian [Verfasser], and R. [Akademischer Betreuer] Stieglitz. "Advanced Treatment of Fission Yield Effects and Method Development for Improved Reactor Depletion Calculations / Kilian Kern ; Betreuer: R. Stieglitz." Karlsruhe : KIT-Bibliothek, 2018. http://d-nb.info/1174252227/34.
Повний текст джерелаTodd, Jamie R. D. (James Robert Drysdale). "Angular distributions and kinetic energies of fission products from the 238U(12C,f) reaction." Thesis, McGill University, 1991. http://digitool.Library.McGill.CA:80/R/?func=dbin-jump-full&object_id=59911.
Повний текст джерелаBirgersson, Evert. "Determination of binary fission-fragment yields in the reaction 251Cf(nth, f) and Verification of nuclear reaction theory predictions of fission-fragment distributions in the reaction 238U(n, f)." Doctoral thesis, Örebro : Institutionen för naturvetenskap Department of Natural Sciences, 2007. http://urn.kb.se/resolve?urn=urn:nbn:se:oru:diva-1474.
Повний текст джерелаProkofiev, Alexander. "Nucleon-Induced Fission Cross Sections of Heavy Nuclei in the Intermediate Energy Region." Doctoral thesis, Uppsala : Acta Universitatis Upsaliensis : Univ.-bibl. [distributör], 2001. http://publications.uu.se/theses/91-554-5009-1/.
Повний текст джерелаDufek, Jan. "Development of New Monte Carlo Methods in Reactor Physics : Criticality, Non-Linear Steady-State and Burnup Problems." Doctoral thesis, Stockholm : Skolan för teknikvetenskap, Kungliga Tekniska högskolan, 2009. http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-10602.
Повний текст джерелаSkwarcan-Bidakowski, Alexander. "Nuclear reactor core model for the advancednuclear fuel cycle simulator FANCSEE. Advanceduse of Monte Carlo methods in nuclear reactorcalculations." Thesis, Institutionen för Reaktorfysik, 2017. http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-324260.
Повний текст джерелаFANCSEE
Книги з теми "Fission Reactor Physic"
Nuclear reactor physics. 2nd ed. Weinheim: Wiley-VCH, 2007.
Знайти повний текст джерелаG, McHugh, Merrick A. R, and Royal Society (Great Britain), eds. The Fast-neutron-breeder fission reactor. London: Royal Society, 1990.
Знайти повний текст джерелаSlugeň, Vladimír. Safety of VVER-440 reactors: Barriers against fission products release. London: Springer, 2011.
Знайти повний текст джерелаMeeting, Royal Society (Great Britain) Discussion. The fast-neutron breeder fission reactor: Proceedings of a Royal Society dicussion meeting held on 24 and 25 May 1989. London: Royal Society, 1990.
Знайти повний текст джерелаNapoli, Museo nazionale di. Complete Unified Theory, Nirmalendu Das: Key words: mass of a photon & a graviton, unification of physics, value of Pi at excited state, unknown weight of radioactive elements, fission reaction of uranium, gamma ray burst, black hole properties through complete unified theory. Edited by De Petra Giulio and Italy Ministero dell'educazione nazionale. Bani Prokash (P) Limited, Panbazar, Guwahati -781001, Assam, India: G.P.Dev Choudhury, Bani Prokash (P) Limited, Panbazar, Guwahati - 781001, Assam, India in G.P.Dev Choudhury, Bani Prokash (P) Limited, Panbazar, Guwahati - 781001, Assam, India ., 1998.
Знайти повний текст джерелаStacey, Weston M. Nuclear Reactor Physics. Wiley & Sons, Limited, John, 2018.
Знайти повний текст джерелаNuclear Reactor Physics. Wiley-Interscience, 2001.
Знайти повний текст джерелаStacey, Weston M. Nuclear Reactor Physics. Wiley & Sons, Incorporated, John, 2018.
Знайти повний текст джерелаStacey, Weston M. Nuclear Reactor Physics. Wiley & Sons, Incorporated, John, 2018.
Знайти повний текст джерелаStacey, Weston M. Nuclear Reactor Physics. Wiley & Sons, Incorporated, John, 2018.
Знайти повний текст джерелаЧастини книг з теми "Fission Reactor Physic"
Natelson, 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 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 джерелаMasterson, Robert E. "Nuclear Fission and Nuclear Energy Production." In Introduction to Nuclear Reactor Physics, 319–65. 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/10.1201/9781315118055-7.
Повний текст джерелаMasterson, Robert E. "Fission Products, Xenon Transients, and Reactor Accidents." In Introduction to Nuclear Reactor Physics, 877–910. 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/10.1201/9781315118055-21.
Повний текст джерелаKessler, Günter. "Some Basic Physics of Converters and Breeder Reactors." In Sustainable and Safe Nuclear Fission Energy, 25–57. Berlin, Heidelberg: Springer Berlin Heidelberg, 2012. http://dx.doi.org/10.1007/978-3-642-11990-3_3.
Повний текст джерелаSekine, T., and T. Aoyama. "Fission Rate Analysis of a Fast Reactor Fuel Performance Test Using MCNP." In Advanced Monte Carlo for Radiation Physics, Particle Transport Simulation and Applications, 737–42. Berlin, Heidelberg: Springer Berlin Heidelberg, 2001. http://dx.doi.org/10.1007/978-3-642-18211-2_117.
Повний текст джерелаPyeon, Cheol Ho. "Neutron Spectrum." In Accelerator-Driven System at Kyoto University Critical Assembly, 125–56. Singapore: Springer Singapore, 2021. http://dx.doi.org/10.1007/978-981-16-0344-0_5.
Повний текст джерелаTzykanov, V. A., V. N. Golovanov, V. K. Shamardin, F. N. Kryukov, and A. V. Povstyanko. "Corrosion of Fast-Reactor Claddings by Physical and Chemical Interaction with Fuel and Fission Products." In NATO Science for Peace and Security Series C: Environmental Security, 281–93. Dordrecht: Springer Netherlands, 2007. http://dx.doi.org/10.1007/978-1-4020-5903-2_19.
Повний текст джерелаТези доповідей конференцій з теми "Fission Reactor Physic"
Pal, Usha, and V. Jagannathan. "Physics Principles to Achieve Comparable Fission Power From Fertile and Fissile Rods of the Conceptual ATBR/FTBR Reactors." In 16th International Conference on Nuclear Engineering. ASMEDC, 2008. http://dx.doi.org/10.1115/icone16-48381.
Повний текст джерелаPahladsingh, Remond R. "Possibility of Using Gamma Radiation From HTR Reactors for Processing of Food and Medical Products." In 12th International Conference on Nuclear Engineering. ASMEDC, 2004. http://dx.doi.org/10.1115/icone12-49316.
Повний текст джерелаYan, Xuesong, Yaling Zhang, Yucui Gao, and Lei Yang. "Conceptual Study of Neutron Physics of Nuclear Fuel Cycle for Ceramic Fast Reactor." In 2021 28th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2021. http://dx.doi.org/10.1115/icone28-65406.
Повний текст джерелаSchmidt, J. J. "NUCLEAR DATA - THEIR IMPORTANCE AND APPLICATION IN FISSION REACTOR PHYSICS CALCULATIONS." In Proceedings of the Workshop. WORLD SCIENTIFIC, 1991. http://dx.doi.org/10.1142/9789814439398_0001.
Повний текст джерелаVerfondern, Karl, and Heinz Nabielek. "Fission Product Release From HTGR Fuel Under Core Heatup Accident Conditions." In Fourth International Topical Meeting on High Temperature Reactor Technology. ASMEDC, 2008. http://dx.doi.org/10.1115/htr2008-58160.
Повний текст джерелаOttewitte, E. H. "Large scale positron production for physics needs via fission reactors." In AIP Conference Proceedings Volume 156. AIP, 1987. http://dx.doi.org/10.1063/1.36457.
Повний текст джерелаChen, Xiaoliang, Zhendong Fan, Xiaoxian Chen, and Dingsheng Hu. "Measurement of Reaction Rate Distribution and Neutron Spectrum in China Experimental Fast Reactor." In 2013 21st International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2013. http://dx.doi.org/10.1115/icone21-16413.
Повний текст джерелаBakharev, N. N., F. V. Chernyshev, V. V. Dyachenko, V. K. Gusev, N. A. Khromov, E. O. Kiselev, A. N. Konovalov, et al. "Globus-M2 experiments in scope of fusion-fission reactor development." In PROCEEDINGS OF THE INTERNATIONAL CONFERENCE ON ADVANCES AND APPLICATIONS IN PLASMA PHYSICS (AAPP 2019). AIP Publishing, 2019. http://dx.doi.org/10.1063/1.5135474.
Повний текст джерелаLiu, Rong, and Wenzhong Zhou. "Fully Coupled Multiphysics Simulation of Enhanced Thermal Conductivity UO2-BeO Fuel Behavior." In ASME 2015 International Mechanical Engineering Congress and Exposition. American Society of Mechanical Engineers, 2015. http://dx.doi.org/10.1115/imece2015-52504.
Повний текст джерелаZhou, Jianjun, Suizheng Qiu, Zhangpeng Guo, and Guanghui Su. "The Optimization Design of Lower Plenum and Distribution Plates in MSR." In 2013 21st International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2013. http://dx.doi.org/10.1115/icone21-16436.
Повний текст джерелаЗвіти організацій з теми "Fission Reactor Physic"
Kaganas, G., and J. Rest. A physical description of fission product behavior fuels for advanced power reactors. Office of Scientific and Technical Information (OSTI), October 2007. http://dx.doi.org/10.2172/919331.
Повний текст джерелаYouinou, Gilles Jean-Michel. MANTA. An Integral Reactor Physics Experiment to Infer the Neutron Capture Cross Sections of Actinides and Fission Products in Fast and Epithermal Spectra. Office of Scientific and Technical Information (OSTI), October 2015. http://dx.doi.org/10.2172/1261040.
Повний текст джерела