Relevant bibliographies by topics / SPENT FUELS

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  1. Journal articles
  2. Dissertations / Theses
  3. Books
  4. Book chapters
  5. Conference papers
  6. Reports

Academic literature on the topic 'SPENT FUELS'

Author: Grafiati
Published: 4 June 2021
Last updated: 5 February 2022

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Journal articles on the topic "SPENT FUELS"

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Heriyanto, Kuat, Usman Sudjadi, Jaka Rachmadetin, Yuli Purwanto, Pungky Ayu Artiani, and Siti Chotijah. "EVALUATION OF NEUTRON SHIELDING PERFORMANCE OF CD-SS 316L AS A CANDIDATE ALLOY FOR DRY CASK OF RESEARCH REACTOR SPENT FUEL." Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir 27, no. 2 (2021): 103. http://dx.doi.org/10.17146/urania.2021.27.2.6426.

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EVALUATION OF NEUTRON SHIELDING PERFORMANCE OF CD-SS 316L AS A CANDIDATE ALLOY FOR DRY CASK OF RESEARCH REACTOR SPENT FUEL Development of dry casks is necessary to support the national strategy for management of spent fuels. One of the requirements for the dry cask is shielding performance for neutron emitted by the spent fuels to be stored in the dry cask. The objectives of this study are to determine the emitted neutrons by the spent fuel generated from GAS research reactor and to evaluate the neutron shielding performance of Cd-SS316L alloy as a candidate material to be used in dry cask for
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Abdelhady, Amr. "Dose rate profile inside the spent fuel storage pool in case of full capacity storage." Journal of Nuclear Physics, Material Sciences, Radiation and Applications 8, no. 1 (2020): 7–10. http://dx.doi.org/10.15415/jnp.2020.81002.

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This study aims to evaluate the radiation dose rate distribution inside temporary spent fuel open-pool storage. The storage pool is connected to the main pool via transfer channel to facilitate transporting the spent fuel under water that avoiding radiation dose rising in the working area in the reactor. The storage pool was prepared to store 800 spent fuel elements that considering the maximum capacity of storage. The spent fuel elements in the storage pool have different decay times depending on the times of extraction from the core. Assuming conservatively, that the spent fuels of the 5-yea
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Arslan, 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.

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This study presents the time-dependent analyses of transmutations of long-lived fission products (LLFPs) and medium-lived fission products (MLFPs) occurring in thermal reactors in a conceptual helium gas-cooled accelerator-driven system (ADS). In accordance with this purpose, the CANDU-37 and PWR 15 × 15 spent fuels are separately considered. The ADS consists of LBE-spallation neutron target, subcritical fuel zone, and graphite reflector zone. While the considered ADS is fueled with the spent nuclear fuels extracted from each thermal reactor without the use of additional fuel, fission products
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Rezaeian, Mahdi, and Jamshid Kamali. "Radioactive Source Specification of Bushehr’s VVER-1000 Spent Fuels." Science and Technology of Nuclear Installations 2016 (2016): 1–4. http://dx.doi.org/10.1155/2016/4579738.

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Due to high radioactivity and significant content of medium- and long-lived radionuclides, different operations with spent nuclear fuels (e.g., handling, transportation, and storage) shall be accompanied by suitable radiation protections. On the other hand, determination of radioactive source specification is the initial step for any radiation protection design. In this study, radioactive source specification of the spent fuels of Bushehr nuclear power plant, which is a VVER-1000 type pressurized water reactor, was determined. For the depletion and decay calculations, ORIGEN code was utilized.
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Wang, Jong Rong, Hao Tzu Lin, Yung Shin Tseng, and Chun Kuan Shih. "Application of TRACE and CFD in the Spent Fuel Pool of Chinshan Nuclear Power Plant." Applied Mechanics and Materials 145 (December 2011): 78–82. http://dx.doi.org/10.4028/www.scientific.net/amm.145.78.

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In the nuclear power plant (NPP) safety, the safety analysis of the NPP is very important work. In Fukushima NPP event, due to the earthquake, the cooling system of the spent fuel pool failed and the safety issue of the spent fuel pool generated. After Fukushima NPP event, INER (Institute of Nuclear Energy Research, Atomic Energy Council, R.O.C.) performed the safety analysis of the spent fuel pool for Chinshan NPP which also assumed the cooling system of the spent fuel pool failed. The geometry of the Chinshan NPP spent fuel pool is 12.17 m × 7.87 m × 11.61 m and the initial condition is 60 ¢
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Husnayani, Ihda, and Pande Made Udiyani. "RADIONUCLIDE CHARACTERISTICS OF RDE SPENT FUELS." JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA 20, no. 2 (2018): 69. http://dx.doi.org/10.17146/tdm.2018.20.2.4101.

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Reaktor Daya Eksperimental (RDE) is a 10 MWth pebble-bed High Temperature Gas-cooled Reactor that is planned to be constructed by National Nuclear Energy Agency of Indonesia (BATAN) in Puspiptek complex, Tangerang Selatan. RDE utilizes low enriched UO2 fuel coated by TRISO layers and loaded into the core by means of multipass loading scheme. Determination of radionuclide characteristics of RDE spent fuel; such as activity, thermal power, neutron and photon release rates; are very important because those characteristics are crucial to be used as a base for evaluating the safety of spent fuel ha
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Thomas, L. E., and R. J. Guenther. "AEM analysis of condensed-phase xenon in UO2 spent fuel." Proceedings, annual meeting, Electron Microscopy Society of America 46 (1988): 512–13. http://dx.doi.org/10.1017/s0424820100104625.

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Release of the abundant fission gases xenon and krypton in UO2 reactor fuels is a limiting factor in normal performance of fuel rods and a concern in possible accidents involving transient overheating of the fuel. Consequently, a knowledge of the fission gas behavior in fuel is of great interest. Although fission gases in fuel are widely believed to exist as gas bubbles or atoms in solution in the UO2, we have obtained evidence by analytical electron microscopy that the xenon and krypton can also exist as a condensed phase, i.e. as a liquid or solid at high internal pressures in the UO2. This
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Khakim, Azizul. "ANALISIS KESELAMATAN TERMOHIDROLIK BULK SHIELDING REAKTOR KARTINI." JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA 17, no. 3 (2015): 115. http://dx.doi.org/10.17146/tdm.2015.17.3.2321.

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ABSTRAK ANALISIS KESELAMATAN TERMOHIDROLIK BULK SHIELDING REAKTOR KARTINI. Bulk shielding merupakan fasilitas yang terintegrasi dengan reaktor Kartini yang berfungsi sebagai penyimpanan sementara bahan bakar bekas. Fasilitas ini merupakan fasilitas yang termasuk dalam struktur, sistem dan komponen (SSK) yang penting bagi keselamatan. Salah satu fungsi keselamatan dari sistem penanganan dan penyimpanan bahan bakar adalah mencegah kecelakaan kekritisan yang tak terkendali dan membatasi naiknya temperatur bahan bakar. Analisis keselamatan paling kurang harus mencakup analisis keselamatan dari sis
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Harkness, Ira, Ting Zhu, Yinong Liang, Eric Rauch, Andreas Enqvist, and Kelly A. Jordan. "Development of Neutron Energy Spectral Signatures for Passive Monitoring of Spent Nuclear Fuels in Dry Cask Storage." EPJ Web of Conferences 170 (2018): 07004. http://dx.doi.org/10.1051/epjconf/201817007004.

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Demand for spent nuclear fuel dry casks as an interim storage solution has increased globally and the IAEA has expressed a need for robust safeguards and verification technologies for ensuring the continuity of knowledge and the integrity of radioactive materials inside spent fuel casks. Existing research has been focusing on “fingerprinting” casks based on count rate statistics to represent radiation emission signatures. The current research aims to expand to include neutron energy spectral information as part of the fuel characteristics. First, spent fuel composition data are taken from the
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Gibb, F. G. F., K. P. Travis, and K. W. Hesketh. "Deep borehole disposal of higher burn up spent nuclear fuels." Mineralogical Magazine 76, no. 8 (2012): 3003–17. http://dx.doi.org/10.1180/minmag.2012.076.8.16.

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AbstractThe heat outputs of higher burn up spent fuels (SF) create problems for disposal in mined repositories, including needs for reduced container loadings and extended pre-disposal cooling. An alternative that is less temperature sensitive is deep borehole disposal (DBD) which offers safety, cost, security and other potential benefits and could be implemented relatively quickly using currently available deep-drilling technology. We have modified our previously proposed version of DBD to be more appropriate for higher burn-up fuels by using smaller (0.36 m diameter) stainless steel containe
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Dissertations / Theses on the topic "SPENT FUELS"

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ROMANATO, LUIZ S. "Armazenagem de combustivel nuclear queimado." reponame:Repositório Institucional do IPEN, 2005. http://repositorio.ipen.br:8080/xmlui/handle/123456789/11204.

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Made available in DSpace on 2014-10-09T12:49:28Z (GMT). No. of bitstreams: 0<br>Made available in DSpace on 2014-10-09T14:01:16Z (GMT). No. of bitstreams: 0<br>Dissertacao (Mestrado)<br>IPEN/D<br>Instituto de Pesquisas Energeticas e Nucleares, IPEN/CNEN-SP
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ROMANATO, LUIZ S. "Estudo de um casco nacional e sua instalacao para armazenagem seca de combustivel nuclear queimado gerado em reatores PWR." reponame:Repositório Institucional do IPEN, 2009. http://repositorio.ipen.br:8080/xmlui/handle/123456789/9476.

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Made available in DSpace on 2014-10-09T12:27:08Z (GMT). No. of bitstreams: 0<br>Made available in DSpace on 2014-10-09T13:56:18Z (GMT). No. of bitstreams: 0<br>Tese (Doutoramento)<br>IPEN/T<br>Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP
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Zino, John Frederick. "Analysis of subcritical experiments using fresh and spent research reactor fuel assemblies." Diss., Georgia Institute of Technology, 1999. http://hdl.handle.net/1853/17507.

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Araya, Pablo E. "Design of an experiment that simulates spent nuclear fuel within transport casks." abstract and full text PDF (free order & download UNR users only), 2007. http://0-gateway.proquest.com.innopac.library.unr.edu/openurl?url_ver=Z39.88-2004&rft_val_fmt=info:ofi/fmt:kev:mtx:dissertation&res_dat=xri:pqdiss&rft_dat=xri:pqdiss:1442846.

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Sommer, Christopher Michael. "Subcritical transmutation of spent nuclear fuel." Diss., Georgia Institute of Technology, 2011. http://hdl.handle.net/1853/41205.

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A series of fuel cycle simulations were performed using CEA's reactor physics code ERANOS 2.0 to analyze the transmutation performance of the Subcritical Advanced Burner Reactor (SABR). SABR is a fusion-fission hybrid reactor that combines the leading sodium cooled fast reactor technology with the leading tokamak plasma technology based on ITER physics. Two general fuel cycles were considered for the SABR system. The first fuel cycle is one in which all of the transuranics from light water reactors are burned in SABR. The second fuel cycle is a minor actinide burning fuel cycle in which al
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Sommer, Christopher. "Fuel cycle design and analysis of SABR subrcritical advanced burner reactor /." Thesis, Atlanta, Ga. : Georgia Institute of Technology, 2008. http://hdl.handle.net/1853/24720.

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Szakaly, 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.

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The purpose of this work is to investigate the implementation of nitride fuels containing little or no uranium in a fast-spectrum nuclear reactor to reduce the amount of plutonium and minor actinides in spent nuclear fuel destined for the Yucca Mountain Repository. A two tier recycling strategy is proposed. Thermal spectrum transmutation systems converted from the existing LWR fleet were modeled for the first tier, and the Japanese fast reactor MONJU was used for the fast-spectrum transmutation. The modeling was performed with the Monteburns code. Transmutation performance was investigated
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Casella, Andrew M. "Modeling of molecular and particulate transport in dry spent nuclear fuel canisters." Diss., Columbia, Mo. : University of Missouri-Columbia, 2007. http://hdl.handle.net/10355/4695.

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Thesis (Ph. D.)--University of Missouri-Columbia, 2007.<br>The entire dissertation/thesis text is included in the research.pdf file; the official abstract appears in the short.pdf file (which also appears in the research.pdf); a non-technical general description, or public abstract, appears in the public.pdf file. Title from title screen of research.pdf file (viewed on November 26, 2007 Vita. Includes bibliographical references.
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Stevenson, Anthony John. "Development of a novel electrochemical pyroprocessing methodology for spent nuclear fuels." Thesis, University of Nottingham, 2017. http://eprints.nottingham.ac.uk/39300/.

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Nuclear power remains the most dense and reliable primary form of energy supply worldwide. Electricity generation via fission is also inherently carbon free, with environmental footprints rivalling modern renewable options. However issues arise from the production of highly irradiated spent fuels, with current management options limited to geological repository storage or, more desirably, closing of the fuel cycle by partitioning to recover fissionable species. Extensive research has been pursued over the past half century in an effort to address an accumulating oxide spent fuel inventory and
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Venigalla, Venkata Vijaya Raghava. "Computational fluid dynamic simulations of natural convection/radiation heat transfer within the fuel regions of a truck cask for normal transport." abstract (free order & download UNR users only), 2007. http://0-gateway.proquest.com.innopac.library.unr.edu/openurl?url_ver=Z39.88-2004&rft_val_fmt=info:ofi/fmt:kev:mtx:dissertation&res_dat=xri:pqdiss&rft_dat=xri:pqdiss:1447694.

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Books on the topic "SPENT FUELS"

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Boyd, Christopher F. Predictions of spent fuel heatup after a complete loss of spent fuel pool coolant. Safety Margins and Systems Analysis Branch, Office of Nuclear Regulatory Research, Nuclear Regulatory Commission, 2000.

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Boyd, Christopher Fred. Predictions of spent fuel heatup after a complete loss of spent fuel pool coolant. Safety Margins and Systems Analysis Branch, Office of Nuclear Regulatory Research, Nuclear Regulatory Commission, 2000.

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McIntosh, W. W. Spent fuel from foreign research reactors. Science and Technology, Washington State Institute for Public Policy, 1986.

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Subramaniam, Chitra. Probabilistic safety analysis of transportation of spent fuel. Bhabha Atomic Research Centre, 1999.

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Wasywich, K. M. Characteristics of used CANDU fuel relevant to the Canadian Nuclear Fuel Waste Management Program. Whiteshell Laboratories, 1993.

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Bevard, B. B. Review of information for spent nuclear fuel burnup confirmation. U. S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 2009.

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Ahn, T. M. Dry oxidation and fracture of LWR spent fuels. Division of Waste Management, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, 1996.

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Radiological impacts of spent nuclear fuel management options: A comparative study. Nuclear Energy Agency, Organisation for Economic Co-operation and Development, 2000.

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Huang, F. H. Studies on dry storage of damaged spent fuel. Avante Pub., 1998.

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Scaglione, J. M. A quantitative impact assessment of hypothetical spent fuel reconfiguration in spent fuel storage casks and transportation packages. U.S. Nuclear Regulatory Commission, 2015.

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Book chapters on the topic "SPENT FUELS"

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Duarte, Luís C., Florbela Carvalheiro, Sónia Lopes, Ines Neves, and Francisco M. Gírio. "Yeast Biomass Production in Brewery’s Spent Grains Hemicellulosic Hydrolyzate." In Biotechnology for Fuels and Chemicals. Humana Press, 2007. http://dx.doi.org/10.1007/978-1-60327-526-2_59.

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Sublette, Kerry L. "A Preliminary Cost Analysis of the Biotreatment of Refinery Spent-Sulfidic Caustic." In Biotechnology for Fuels and Chemicals. Humana Press, 1997. http://dx.doi.org/10.1007/978-1-4612-2312-2_62.

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Spink, H. E. "Design of Ships for the Transport of Spent Nuclear Fuels." In Transportation for the Nuclear Industry. Springer US, 1989. http://dx.doi.org/10.1007/978-1-4757-0046-6_11.

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Rodrigues, Rita C. L. B., Chenfeng Lu, Bernice Lin, and Thomas W. Jeffries. "Fermentation Kinetics for Xylitol Production by a Pichia stipitis d-Xylulokinase Mutant Previously Grown in Spent Sulfite Liquor." In Biotechnology for Fuels and Chemicals. Humana Press, 2007. http://dx.doi.org/10.1007/978-1-60327-526-2_66.

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Kolhatkar, Arati, and Kerry L. Sublette. "Biotreatment of Refinery Spent Sulfidic Caustic by Specialized Cultures and Acclimated Activated Sludge." In Seventeenth Symposium on Biotechnology for Fuels and Chemicals. Humana Press, 1996. http://dx.doi.org/10.1007/978-1-4612-0223-3_89.

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Moritz, John W., and J. B. Duff Sheldon. "Ethanol Production from Spent Sulfite Liquor Fortified by Hydrolysis of Pulp Mill Primary Clarifier Sludge." In Seventeenth Symposium on Biotechnology for Fuels and Chemicals. Humana Press, 1996. http://dx.doi.org/10.1007/978-1-4612-0223-3_66.

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Conner, Julie A., Robert R. Beitle, Kathleen Duncan, Ravi Kolhatkar, and Kerry L. Sublette. "Biotreatment of Refinery Spent-Sulfidic Caustic Using an Enrichment Culture Immobilized in a Novel Support Matrix." In Twenty-First Symposium on Biotechnology for Fuels and Chemicals. Humana Press, 2000. http://dx.doi.org/10.1007/978-1-4612-1392-5_54.

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Koyama, Tadafumi, and Masatoshi Iizuka. "Pyrochemical fuel cycle technologies for processing of spent nuclear fuels." In Reprocessing and Recycling of Spent Nuclear Fuel. Elsevier, 2015. http://dx.doi.org/10.1016/b978-1-78242-212-9.00018-6.

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Natarajan, R. "Reprocessing of spent fast reactor nuclear fuels." In Reprocessing and Recycling of Spent Nuclear Fuel. Elsevier, 2015. http://dx.doi.org/10.1016/b978-1-78242-212-9.00009-5.

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Ekberg, Christian. "Developments in reprocessing of spent nuclear fuels for the thorium fuel cycle." In Reprocessing and Recycling of Spent Nuclear Fuel. Elsevier, 2015. http://dx.doi.org/10.1016/b978-1-78242-212-9.00024-1.

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Conference papers on the topic "SPENT FUELS"

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Christensen, Allan B., and Kraig M. Wendt. "Drying of Spent Nuclear Fuels and Fuel Debris Dried in a Vacuum Furnace." 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/icem2001-1215.

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Abstract Spent nuclear fuels and fuel debris stored underwater must eventually be prepared for dry storage (e.g., repository disposition). This preparation involves some degree of fuel drying. Primary considerations for a fuel drying process are the containment configuration of the spent fuel material and the type of fuel material (e.g., oxide, metal, hydride, alloy, carbide, epoxied, debris). The Idaho National Engineering and Environmental Laboratory has built and operated three heated vacuum drying systems and placed into interim dry storage all of these fuel types. The drying systems and p
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Lee, Yi-Kang, and Kabir Sharma. "Tripoli-4 Gamma-Ray Dose Calculation for Spent PWR Fuels." In 2013 21st International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2013. http://dx.doi.org/10.1115/icone21-15498.

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The gamma-ray dose calculation is essential for the radiation shielding of pressurized water reactor (PWR) spent fuels. Homogenization modeling of fuel pin lattices for typical PWR spent fuel pins is regularly applied on the radiation protection calculation of gamma-ray dose in an air medium. However, depending on the size of the homogenized lattice and the location of the detectors, under-estimation or over-estimation of the gamma-ray dose due to the homogenization modeling can be obtained with respect to the detailed heterogeneous model. In previous published results from MCNP-4A and 4C calc
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Kook, Donghak, Jongwon Choi, Heuijoo Choi, and Dongkeun Cho. "Characteristics of the Spent Fuel Generated in Korea." In ASME 2009 12th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2009. http://dx.doi.org/10.1115/icem2009-16227.

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Nuclear power has satisfied the national electric power demand for three decades, and there are only two reactor types in Korea. The nuclear fuel species, however, have a large variety of fuel types, dimensions, initial enrichment, and fuel supply vendors. A spent fuel accumulation problem has arisen like any other country that uses nuclear power. The spent fuel wet storage capacity in the reactor pool is getting close to its limit, and so hence, short &amp; long-term solutions are being actively proposed. First the general status for the nuclear industries and spent fuels will be introduced,
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Sun, Hongchao, Guoqiang Li, Xuexin Wang, et al. "Study on Periodic Shielding Performance Measurements of Spent Fuel Transportation Package." In 2017 25th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2017. http://dx.doi.org/10.1115/icone25-66036.

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The radioactive activity of spent nuclear fuel is high, and the transportation safety is concerned by public and specialist. The periodic radiation shielding performance measurements of spent fuels package is important content to ensure transportation safety of spent fuels. The radiation shielding performance of package must meet the requirements of “Regulations for the safe transport of radioactive material” (GB11806-2004). However, some of the problems and difficulties reflected in practice need to be solved, such as the measurements results of neutron radiation level of spent fuels package
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Wantz, Olivier, Olivier Smidts, Alain Dubus, and R. Beauwens. "Long-Term In-Package Spent Fuel Criticality Calculations." In ASME 2003 9th International Conference on Radioactive Waste Management and Environmental Remediation. ASMEDC, 2003. http://dx.doi.org/10.1115/icem2003-4575.

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This paper presents MCNP criticality calculations for both UOX and MOX disrupted fuel assemblies canisters systems in the reference Belgian disposal concept and one of its variant. We examine the influence of different parameters (water moderation and geometry alteration) on the neutron multiplication factor, keff. In all the studied cases, the reference concept does not present criticality risks. The variant concept sometimes presents criticality risks. The present results only concern fresh UOX and MOX fuel assemblies. Further developments of this work will include irradiated (UOX and MOX) f
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Permana, Sidik, Mitsutoshi Suzuki, and Zaki Su’ud. "Comparative analysis of LWR and FBR spent fuels for nuclear forensics evaluation." In THE 3RD INTERNATIONAL CONFERENCE ON ADVANCES IN NUCLEAR SCIENCE AND ENGINEERING 2011: ICANSE 2011. AIP, 2012. http://dx.doi.org/10.1063/1.4725449.

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Dehaudt, Philippe. "Physicochemical State of the Spent Fuel Leaving the Reactors." 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/icem2001-1195.

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Abstract This review focuses on the current knowledge, updated at the end of 1999, about the physicochemical state of the fuels leaving light water reactors, and particularly pressurized water reactors in France. Accessible data in the scientific literature, or those acquired at the CEA, are particularly numerous. Their analysis and their synthesis are joined together to constitute a collection of references intended to the specialists in nuclear fuel and for all those which contribute to the studies on the storage or final disposal of the irradiated fuel.
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Wu, Xiaoli, Yapei Zhang, Wenxi Tian, Guanghui Su, and Suizheng Qiu. "Analysis of a Loss of Heat Removal Accident in a PWR Spent Fuel Pool." In 2014 22nd International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2014. http://dx.doi.org/10.1115/icone22-30515.

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The Fukushima Daiichi nuclear accident shows that it is necessary to study potential severe accidents and corresponding mitigation measures for the spent fuel pool (SFP) of a nuclear power plant (NPP). This paper presents a study on the consequences of loss of heat removal accident in the spent fuel pool of a typical pressurized water reactor using the Modular Accident Analysis Program (MAAP5) code. Analysis of uncompensated loss of water due to the loss of heat removal with initial pool water level of 12.2 m (designated as a reference case) has been performed. The analyses cover a broad spect
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Kotoh, Kenji, Yuzo Yamashita, and Takeshi Nakamura. "Effective Use of Uranium Resources and Dissolution of Recovered Uranium Storage Accumulation by a Uranium Multi-Recycle System." In ASME 2010 13th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2010. http://dx.doi.org/10.1115/icem2010-40051.

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The uranium recovered from LWR spent fuels, containing an amount of 235U comparable to that in the natural uranium, can be recycled as uranium fuels for LWRs by re-enrichment using a conventional centrifuge cascade. However, the remade fuel is inferior to the original fuel produced from the natural uranium on the burn-up performance, because the former includes 236U as a neutron absorber which is yielded in the spent fuel and then enhanced in the re-enrichment process. Therefore, a few times recycle of recovered uranium may be available but its successive recycle is not recommendable because o
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You, G. S., W. M. Choung, J. H. Ku, S. I. Moon, and H. D. Kim. "Pyroprocess Facility Design for a Nuclear Fuel Cycle." In 2013 21st International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2013. http://dx.doi.org/10.1115/icone21-15190.

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The Korea Atomic Energy Research Institute (KAERI) has been developing pyroprocess for the dry conditioning of PWR spent nuclear fuels since 1997. The ACPF (Advanced spent fuel Conditioning Process Facility) was developed for volume reduction research on spent PWR fuel. Several years later, the PRIDE (PyRoprocess Integrated inactive Demonstration) facility was also developed for SFR fuel utilization research by pyroprocessing. An integrated full pyroprocess was used in the PRIDE facility. Presently another pyroprocess facility, ESPF (Engineering Scale Pyroprocess Demonstration Facility), is be
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Reports on the topic "SPENT FUELS"

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Ahn, T. M. Dry oxidation and fracture of LWR spent fuels. Office of Scientific and Technical Information (OSTI), 1996. http://dx.doi.org/10.2172/414309.

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Huang, F. F., and F. W. Moore. Refinishing contamination floors in Spent Nuclear Fuels storage basins. Office of Scientific and Technical Information (OSTI), 1997. http://dx.doi.org/10.2172/325388.

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L.F. Pincock, W.D. Hintze, and J. Duguid. Analysis of DOE Spent Nuclear Fuels for Repository Disposal. Office of Scientific and Technical Information (OSTI), 2006. http://dx.doi.org/10.2172/893932.

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HUNACEK, G. S. Spent nuclear fuels project 100-K operations spill assessment. Office of Scientific and Technical Information (OSTI), 1999. http://dx.doi.org/10.2172/798027.

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Wuertz, R., and M. Ellinger. Characterization of spent nuclear fuels for direct final disposal. Office of Scientific and Technical Information (OSTI), 1988. http://dx.doi.org/10.2172/7777105.

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Lawrence, L. A., T. A. Thornton, and K. S. Redus. Spent nuclear fuels project characterization data quality objectives strategy. Office of Scientific and Technical Information (OSTI), 1994. http://dx.doi.org/10.2172/10114576.

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Cresap, D. A., P. J. Sentieri, and J. R. Wilson. Criticality evaluation and protocol for DOE-owned spent nuclear fuels. Office of Scientific and Technical Information (OSTI), 1995. http://dx.doi.org/10.2172/130638.

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Simpson, Michael, and II-Soon Hwang. Investigation of Electrochemical Recovery of Zirconium from Spent Nuclear Fuels. Office of Scientific and Technical Information (OSTI), 2014. http://dx.doi.org/10.2172/1169253.

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Bendixsen, C. L., D. L. Fillmore, R. J. Kirkham, et al. Development and engineering plan for graphite spent fuels conditioning program. Office of Scientific and Technical Information (OSTI), 1993. http://dx.doi.org/10.2172/142482.

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CHODAK, P. USING PROLIFERATION-RESISTANT FUELS TO MANAGE GLOBAL PLUTONIUM INVENTORIES: GOING BEYOND THE SPENT-FUEL STANDARD. Office of Scientific and Technical Information (OSTI), 1999. http://dx.doi.org/10.2172/785170.

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