Academic literature on the topic 'Transmutation of spent nuclear fue'
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Journal articles on the topic "Transmutation of spent nuclear fue"
Yapıcı, Hüseyin. "Burning and/or transmutation of transuraniums discharged from PWR-UO2 spent fuel and power flattening along the operation period in the force free helical reactor." Energy Conversion and Management 44, no. 18 (November 2003): 2893–913. http://dx.doi.org/10.1016/s0196-8904(03)00068-2.
Full textBrolly, Á., and P. Vértes. "Transmutation: Towards Solving Problem of Spent Nuclear Fuel." Acta Physica Hungarica A) Heavy Ion Physics 19, no. 3-4 (April 1, 2004): 263–71. http://dx.doi.org/10.1556/aph.19.2004.3-4.19.
Full textTikhomirov, G. V., and A. S. Gerasimov. "THE MAIN PROBLEMS OF THE MANAGEMENT OF RADIOACTIVE WASTE FROM NPP SPENT FUEL USING NUCLEAR TRANSMUTATION." Professor’s Journal. Series: Technical science 3 (September 1, 2019): 41–56. http://dx.doi.org/10.18572/2686-8598-2019-3-3-41-56.
Full textDurmaz, Busra, Gizem Bakir, Bugra Arslan, and Huseyin Yapici. "Neutronic analysis of an ads fuelled with minor actinide and designed for spent fuel enrichment and fissile fuel production." Nuclear Technology and Radiation Protection 36, no. 4 (2021): 299–314. http://dx.doi.org/10.2298/ntrp2104299d.
Full textSadighi, S. K., and R. Sadighi-Bonabi. "The evaluation of transmutation of hazardous nuclear waste of 90Sr, into valuable nuclear medicine of 89Sr by ultraintense lasers." Laser and Particle Beams 28, no. 2 (April 14, 2010): 269–76. http://dx.doi.org/10.1017/s0263034610000145.
Full textTran, Vinh Thanh, Thanh Mai Vu, Van Khanh Hoang, and Viet Ha Pham Nhu. "Study on transmutation efficiency of the VVER-1000 fuel assembly with different minor actinide compositions." Nuclear Science and Technology 9, no. 4 (September 3, 2021): 16–26. http://dx.doi.org/10.53747/jnst.v9i4.134.
Full textAbderrahim, Hamid Aït. "Realization of a new large research infrastructure in Belgium: MYRRHA contribution for closing the nuclear fuel cycle making nuclear energy sustainable." EPJ Web of Conferences 246 (2020): 00012. http://dx.doi.org/10.1051/epjconf/202024600012.
Full textMcDeavitt, S. M., A. Parkison, A. R. Totemeier, and J. J. Wegener. "Fabrication of Cermet Nuclear Fuels Designed for the Transmutation of Transuranic Isotopes." Materials Science Forum 561-565 (October 2007): 1733–36. http://dx.doi.org/10.4028/www.scientific.net/msf.561-565.1733.
Full textŞahin, Sümer, and Mustafa Übeyli. "LWR spent fuel transmutation in a high power density fusion reactor." Annals of Nuclear Energy 31, no. 8 (May 2004): 871–90. http://dx.doi.org/10.1016/j.anucene.2003.11.003.
Full textArslan, Alper Buğra, İlayda Yilmaz, Gizem Bakir, and Hüseyin Yapici. "Transmutations of Long-Lived and Medium-Lived Fission Products Extracted from CANDU and PWR Spent Fuels in an Accelerator-Driven System." Science and Technology of Nuclear Installations 2019 (October 20, 2019): 1–13. http://dx.doi.org/10.1155/2019/4930274.
Full textDissertations / Theses on the topic "Transmutation of spent nuclear fue"
Sommer, Christopher Michael. "Subcritical transmutation of spent nuclear fuel." Diss., Georgia Institute of Technology, 2011. http://hdl.handle.net/1853/41205.
Full textYee, Shannon K. "Nuclear Fuel Cycle Modeling Approaches For Recycling And Transmutation Of Spent Nuclear Fuel." The Ohio State University, 2008. http://rave.ohiolink.edu/etdc/view?acc_num=osu1213905425.
Full textHoggett-Jones, Craig. "Modelling and assessment of partitioning and transmutation approaches to spent nuclear fuel management." Thesis, University of Strathclyde, 2001. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.248302.
Full textSzakaly, Frank Joseph. "Assessment of uranium-free nitride fuels for spent fuel transmutation in fast reactor systems." Thesis, Texas A&M University, 2003. http://hdl.handle.net/1969.1/31.
Full textОнисимчук, Тетяна Михайлівна. "Трансмутація радіоактивних відходів з удосконаленням системи сповільнення швидких нейтронів." Master's thesis, Київ, 2018. https://ela.kpi.ua/handle/123456789/25799.
Full textThe dissertation is devoted to the introduction of a fast neutron slowdown system in subcritical nuclear installations controlled by an external source made from recycled polyethylene terephthalate. The dissertation defines the performance indicators of subcritical systems with plastic moderator, proved the possibility of using the secondary polymer as a moderator of fast neurons, and the dependence of the ionizing radiation transmittance coefficient on the cycle of processing the material of the protective layer has been established. It is determined that the economic efficiency of the use of secondary raw materials, taking into account the increase in the amount of polymer in 1,3 times compared with the reference polyethylene, is defined by the savings of investments in the amount of 1 197 683 UAH at the time of calculation. The dependence of transmittance coefficient of ionizing radiation on the thickness of the outer layer of the retarder after the cyclic stages of processing, which is described by the polynomial of the 3rd order, is obtained.It was found that the permissible number of recycling cycles for polyethylene terephthalate is three, in which the thickness of the moderator will be 750 mm. In subsequent cycles of recycling, the use of secondary raw materials will be economically impractical. The developed start-up project of technology implementation on the domestic market predicts a one-time profit of about 800 thousand UAH for 1 year from the date of receipt of the certificate of conformity.
Диссертация посвящена внедрению системы замедления быстрых нейтронов в подкритических ядерных установках, управляемых внешним источником, выполненной из вторично переработанного полиэтилентерефталата. В диссертации определены показатели безопасности функционирования подкритических систем с пластиковым замедлителем, доказана возможность применения вторичного полимера в качестве замедлителя быстрых нейронов и установлена зависимость коэффициента пропускания ионизирующего излучения от цикла переработки материала защитного слоя. Определено, что экономическая эффективность использования вторичного сырья с учетом увеличения количества полимера в 1,3 раза в сравнении с эталонным полиэтиленом, определяется экономией капиталовложений в размере 1 197 683 грн на момент проведения расчета. Получена зависимость коэффициента пропускания ионизирующего излучения от толщины внешнего слоя замедлителя после циклических этапов переработки, которая описывается полиномом 3-го порядка. Выявлено, что допустимое количество циклов переработки для полиэтилентерефталата составляет три, при котором толщина замедлителя составит 750 мм. При последующих циклах переработки использование вторичного сырья экономически нецелесообразно. Разработанстартап-проект реализации технологии на отечественном рынке прогнозирует получение разового дохода в размере около 800 тыс. грн в течение 1 года от даты получения сертификата соответствия.
Jarchovský, Petr. "Výpočetní simulace urychlovačem řízeného jaderného reaktoru pro transmutaci vyhořelého jaderného paliva." Master's thesis, Vysoké učení technické v Brně. Fakulta elektrotechniky a komunikačních technologií, 2015. http://www.nusl.cz/ntk/nusl-221209.
Full textAlajo, Ayodeji Babatunde. "Fission Product Impact Reduction via Protracted In-core Retention in Very High Temperature Reactor (VHTR) Transmutation Scenarios." Thesis, 2010. http://hdl.handle.net/1969.1/ETD-TAMU-2010-05-7809.
Full textBook chapters on the topic "Transmutation of spent nuclear fue"
Yim, Man-Sung. "Spent Fuel Reprocessing and Nuclear Waste Transmutation." In Lecture Notes in Energy, 341–84. Dordrecht: Springer Netherlands, 2021. http://dx.doi.org/10.1007/978-94-024-2106-4_8.
Full textVerma, Vinod Kumar, and Karel Katovsky. "Spent Nuclear Fuel and Alternative Methods of Transmutation." In Spent Nuclear Fuel and Accelerator-Driven Subcritical Systems, 1–19. Singapore: Springer Singapore, 2018. http://dx.doi.org/10.1007/978-981-10-7503-2_1.
Full textVerma, Vinod Kumar, and Karel Katovsky. "Transmutation of Spent Nuclear Fuel and Extension of a Fuel Cycle." In Spent Nuclear Fuel and Accelerator-Driven Subcritical Systems, 67–80. Singapore: Springer Singapore, 2018. http://dx.doi.org/10.1007/978-981-10-7503-2_5.
Full textSuyama, Kenya, Gunzo Uchiyama, Hiroyuki Fukaya, Miki Umeda, Toru Yamamoto, and Motomu Suzuki. "Development of the Method to Assay Barely Measurable Elements in Spent Nuclear Fuel and Application to BWR 9 × 9 Fuel." In Nuclear Back-end and Transmutation Technology for Waste Disposal, 47–56. Tokyo: Springer Japan, 2014. http://dx.doi.org/10.1007/978-4-431-55111-9_6.
Full textAbbasi, Akbar. "Nuclear Fuel Transmutation." In Nuclear Power Plants - The Processes from the Cradle to the Grave. IntechOpen, 2021. http://dx.doi.org/10.5772/intechopen.94065.
Full textSalvatores, M. "Partitioning and transmutation of spent nuclear fuel and radioactive waste." In Nuclear Fuel Cycle Science and Engineering, 501–30. Elsevier, 2012. http://dx.doi.org/10.1533/9780857096388.4.501.
Full textHill, C. "Development of highly selective compounds for solvent extraction processes: partitioning and transmutation of long-lived radionuclides from spent nuclear fuels." In Advanced Separation Techniques for Nuclear Fuel Reprocessing and Radioactive Waste Treatment, 311–62. Elsevier, 2011. http://dx.doi.org/10.1533/9780857092274.3.311.
Full textConference papers on the topic "Transmutation of spent nuclear fue"
Chen, Shengli, Cenxi Yuan, Jingxia Wu, and Yaolei Zou. "Study of Minor Actinides Transmutation in PWR MOX Fuel." In 2017 25th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2017. http://dx.doi.org/10.1115/icone25-66250.
Full textBergelson, B. R., A. S. Gerasimov, and G. V. Tikhomirov. "Application of Power Reactors for Transmutation of Actinides." In 12th International Conference on Nuclear Engineering. ASMEDC, 2004. http://dx.doi.org/10.1115/icone12-49049.
Full textZhang, Wenxin, Haoyang Yu, Bin Liu, Jin Cai, and Shuangshuang Cui. "The Effect of Minor Actinide Transmutation on Temperature Coefficient in PWR." In 2017 25th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2017. http://dx.doi.org/10.1115/icone25-67649.
Full textGerasimov, Aleksander S., Gennady V. Kiselev, Lidia A. Myrtsymova, and Tamara S. Zaritskaya. "Cyclic Mode of Transmutation of Minor Actinides in Heavy-Water Reactor." In 10th International Conference on Nuclear Engineering. ASMEDC, 2002. http://dx.doi.org/10.1115/icone10-22668.
Full textBalas (Ghizdeanu), Nineta, and Petre Ghitescu. "Transmutation Efficiency of Plutonium and Minor Actinides in PHWR." In 16th International Conference on Nuclear Engineering. ASMEDC, 2008. http://dx.doi.org/10.1115/icone16-48570.
Full textAndrello, Concettina, Daniel Freis, Rosa Lo Frano, Dimitri Papaioannou, and Fabienne Delage. "Characterization of FUTURIX-FTA Irradiated Nuclear Fuel Samples." In 2017 25th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2017. http://dx.doi.org/10.1115/icone25-67252.
Full textHyland, Bronwyn, and Brian Gihm. "Scenarios for the Transmutation of Actinides in CANDU Reactors." In 18th International Conference on Nuclear Engineering. ASMEDC, 2010. http://dx.doi.org/10.1115/icone18-30123.
Full textYu, Haoyang, Bin Liu, Wenxin Zhang, and Jin Cai. "The Effect of MA Transmutation in the PWR on Fuel Cycle." In 2017 25th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2017. http://dx.doi.org/10.1115/icone25-67787.
Full textSun, Lijian, Haritha Royyuru, Hsuan-Tsung Hsieh, Yitung Chen, George Vandegrift, Jackie Copple, and James Laidler. "Development of Systems Engineering Model for Spent Fuel Extraction Process." In ASME 2004 International Mechanical Engineering Congress and Exposition. ASMEDC, 2004. http://dx.doi.org/10.1115/imece2004-60178.
Full textGerasimov, Aleksander S., Boris R. Bergelson, and Tamara S. Zaritskaya. "Two Periods of Long-Term Storage of Thorium Spent Fuel." In ASME 2001 8th International Conference on Radioactive Waste Management and Environmental Remediation. American Society of Mechanical Engineers, 2001. http://dx.doi.org/10.1115/icem2001-1219.
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