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Relevant bibliographies by topics / Spent reactor fuels

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Academic literature on the topic 'Spent reactor fuels'

Author: Grafiati

Published: 4 June 2021

Last updated: 1 August 2024

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Journal articles on the topic "Spent reactor fuels"

1

Durmaz, Busra, Gizem Bakir, Bugra Arslan, and Huseyin Yapici. "Analysis of reusability of ThO2 and spent UO2 fuels enriched with ads in a CANDU reactor." Nuclear Technology and Radiation Protection 37, no. 4 (2022): 289–301. http://dx.doi.org/10.2298/ntrp2204289d.

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The study presents the analysis of the reusability of ThO2 and spent UO2 fuels enriched in two different ADS reactors fuelled with Minor Actinide. The spent UO2 fuels are taken out from pressurized water reactor and CANDU spent fuels. For this analysis, the CANDU-37 reactor having a total fission thermal power of 2156 MW is considered and 14 different cases of enriched fuels taken from the previous enrichment processes are analysed by burning in this reactor. The 3-D and time-dependent critical burn up calculations are carried out by using the MCNP 2.7 code. To determine the effective burn tim

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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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3

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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4

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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5

Nor Azman, Muhammad ‘Adli, Nur Syazwani Mohd Ali, Muhammad Syahir Sarkawi, Muhammad Arif Sazali, and Nor Afifah Basri. "Nuclear fuel materials and its sustainability for low carbon energy system: A review." IOP Conference Series: Materials Science and Engineering 1231, no. 1 (2022): 012016. http://dx.doi.org/10.1088/1757-899x/1231/1/012016.

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Abstract World energy generation for electricity is still dependent on fossil fuels since it is more reliable and secure than the current intermittent renewable energy systems. Although the integration of renewable energy as an energy mix is in progress, still it could not be able to replace fossil fuels. Dependency on fossil fuels will not only contribute to severe climate change but will also degrade future generation quality of life. Hence, the solution to quandary is by integrating nuclear power plants with those of renewable energy such as solar and wind to meet the energy demand and to e

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6

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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Billiet, Gabriel, Xavier Doligez, Guy Marleau, Marc Ernoult, Alain Hébert, and Nicolas Thiollière. "Multi-physics DONJON5 reactor models for improved fuel cycle simulation with CLASS." EPJ Nuclear Sciences & Technologies 10 (2024): 5. http://dx.doi.org/10.1051/epjn/2024008.

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This work investigates reactor model biases and their consequences in nuclear scenario simulations. Usually, the models for Pressurized Water Reactors are based on infinite 2D assembly depletion simulations, but recent work has shown the importance of 3D complete core simulation for uncertainty reduction. The consideration of a whole core leads to new reactor parameters in the simulations that may bring additional biases. The fuel temperature distribution is one of them, and previous work considered isothermal reactors, leading to probable uncertainties in spent fuel inventory at reactor disch

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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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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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Aisyah, Aisyah, Mirawaty Mirawaty, Dwi Luhur Ibnu Saputra, et al. "Effects of %FIMA on Storage-Safety Parameters of Spent Fuel from Experimental Pebble-Bed Reactor." Sains Malaysiana 50, no. 2 (2021): 525–36. http://dx.doi.org/10.17576/jsm-2021-5002-23.

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The back end of the utilization of nuclear technology is safety and management of spent fuel, which is a key element contributing to the success of the nuclear power plant program. Indonesia’s National Nuclear Energy Agency resolved to establish an experimental power reactor, called RDE, as a nuclear power plant demo. The fuel of this reactor is similar to that of German’s experimental pebble-bed reactor (PBR), Arbeitsgemeinschaft Versuchsreaktor(AVR). In this study, the spent fuel of AVR was studied to obtain the safety parameter data for storage of RDE spent fuel by varying the fission in th

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Dissertations / Theses on the topic "Spent reactor fuels"

1

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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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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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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6

Foster, Jack Warren. "Development and implementation of a response-function concept for spent nuclear fuel cask analysis." Thesis, Georgia Institute of Technology, 1993. http://hdl.handle.net/1853/17275.

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Bopp, Andrew T. "The calculation of fuel bowing reactivity coefficients in a subcritical advanced burner reactor." Thesis, Georgia Institute of Technology, 2013. http://hdl.handle.net/1853/50295.

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The United States' fleet of Light Water Reactors (LWRs) produces a large amount of spent fuel each year; all of which is presently intended to be stored in a fuel repository for disposal. As these LWRs continue to operate and more are built to match the increasing demand for electricity, the required capacity for these repositories grows. Georgia Tech's Subcritical Advanced Burner Reactor (SABR) has been designed to reduce the capacity requirements for these repositories and thereby help close the back end of the nuclear fuel cycle by burning the long-lived transuranics in spent nuclear fuel.

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Casella, Amanda J. Miller William Hughes Hanson Brady D. "The dissolution rate of unirratiated UO₂ under repository conditions the influence of fuel and water chemistry, dissolved oxygen, and temperature /." Diss., Columbia, Mo. : University of Missouri--Columbia, 2008. http://hdl.handle.net/10355/6625.

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Title from PDF of title page (University of Missouri--Columbia, viewed on Feb 24, 2010). The entire thesis text is included in the research.pdf file; the official abstract appears in the short.pdf file; a non-technical public abstract appears in the public.pdf file. Dissertation supervisors: Dr. William H. Miller, Dr. Brady D. Hanson. Vita. Includes bibliographical references.

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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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Ilas, Germina. "A Monte Carlo based nodal diffusion model for criticality analysis and application of high-order cross section homogenization method of two-group nodal diffusion." Diss., Georgia Institute of Technology, 2002. http://hdl.handle.net/1853/16092.

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Books on the topic "Spent reactor fuels"

1

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

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2

Agency, International Atomic Energy, ed. Options, experience, and trends in spent nuclear fuel management. International Atomic Energy Agency, 1995.

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3

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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United States. Department of Energy. Office of Civilian Radioactive Waste Management. Used nuclear fuel. [U.S. Department of Energy, Office of Civilian Radioactive Waste Management], 1992.

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R, Johnson E., Saverot P. M, and Institute of Nuclear Materials Management., eds. Monograph on spent nuclear fuel storage technologies. Institute of Nuclear Materials Management, 1997.

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C, Gauld I., Wagner J. C, U.S. Nuclear Regulatory Commission. Spent Fuel Project Office., and Oak Ridge National Laboratory, eds. Recommendations on fuel parameters for standard technical specifications for spent fuel storage casks. Spent Fuel Project Office, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, 2001.

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8

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

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9

U.S. Dept. of Energy. Urgent-relief foreign research reactor spent fuel transportation plan. Savannah River Operations Office, U.S. Dept. of Energy, 1994.

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Fuel, Southern States Energy Board Transportation Working Group on the Urgent-Relief Acceptance of Foreign Research Reactor Spent Nuclear. After-action tabletop discussion: Final meeting summary and attendance list. The Board, 1994.

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Book chapters on the topic "Spent reactor fuels"

1

Walters, William, Alireza Haghighat, Shivakumar Sitaraman, and Young Ham. "Development ofINSPCT-Sfor Inspection of Spent Fuel Pool." In Reactor Dosimetry: 14th International Symposium. ASTM International, 2012. http://dx.doi.org/10.1520/stp155020120052.

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Walters, William, Alireza Haghighat, Shivakumar Sitaraman, and Young Ham. "Development ofINSPCT-Sfor Inspection of Spent Fuel Pool." In Reactor Dosimetry: 14th International Symposium. ASTM International, 2012. http://dx.doi.org/10.1520/stp49649t.

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3

Verma, Vinod Kumar, and Karel Katovsky. "Special Hybrid Systems and Molten-Salt Reactors." In Spent Nuclear Fuel and Accelerator-Driven Subcritical Systems. Springer Singapore, 2018. http://dx.doi.org/10.1007/978-981-10-7503-2_2.

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Adelfang, P., A. J. Soares, and I. N. Goldman. "Spent Nuclear Fuel from Research Reactors: International Status and Perspectives." In NATO Science for Peace and Security Series C: Environmental Security. Springer Netherlands, 2007. http://dx.doi.org/10.1007/978-1-4020-5903-2_1.

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Kopečni, M., M. V. Mataušek, Z. Vukadin, and T. Maksin. "Corrosion Problems in the Research Reactor “RA” Spent Fuel Storage Pool." In Microbial Degradation Processes in Radioactive Waste Repository and in Nuclear Fuel Storage Areas. Springer Netherlands, 1997. http://dx.doi.org/10.1007/978-94-011-5792-6_13.

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Chechetkina, Z. I., Yu V. Chechetkin, A. E. Novoselov, V. G. Bordachev, V. V. Maklakov, and I. Yu Zhemkov. "Trial of Storage Container Technology for Research Reactor Spent Nuclear Fuel." In NATO Science for Peace and Security Series C: Environmental Security. Springer Netherlands, 2007. http://dx.doi.org/10.1007/978-1-4020-5903-2_15.

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Ramanathan, L. V., S. M. C. Fernandes, and O. V. Correa. "Corrosion of Research Reactor Aluminum Clad Spent Fuel in Wet Storage." In NATO Science for Peace and Security Series C: Environmental Security. Springer Netherlands, 2007. http://dx.doi.org/10.1007/978-1-4020-5903-2_20.

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Zheng, Jia-Kang. "Rational Argument of the Closed Loop of the Reactor Spent Fuel." In Lecture Notes in Electrical Engineering. Springer Nature Singapore, 2023. http://dx.doi.org/10.1007/978-981-99-3455-3_18.

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Matsumoto, Tetsuo, Hungyuan B. Liu, and Robert M. Brugger. "Design of Epithermal Neutron Beams Using Spent Fuel Elements at the Musashi Reactor." In Cancer Neutron Capture Therapy. Springer US, 1996. http://dx.doi.org/10.1007/978-1-4757-9567-7_59.

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Lambert, J. D. B., and R. Lambert. "An Overview of Spent Fuel Storage at Commercial Reactors in the United States." In NATO Science for Peace and Security Series C: Environmental Security. Springer Netherlands, 2007. http://dx.doi.org/10.1007/978-1-4020-5903-2_4.

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Conference papers on the topic "Spent reactor fuels"

1

Sassani, David, Laura Price, Heeho Park, Edward Matteo, and Paul Mariner. "Evaluating Geologic Disposal Pathways for Advanced Reactor Spent Fuels." In Proposed for presentation at the INTERNATIONAL HIGH-LEVEL RADIOACTIVE WASTE MANAGEMENT CONFERENCE held November 13-17, 2022 in phoenix, AZ US. US DOE, 2022. http://dx.doi.org/10.2172/2005981.

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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 & 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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Li, Muyue, Zhenyu Fei, Kunzhe Bao, Boren Ke, Xiaodong Sun, and Lumin Wang. "Zero-Emission Mobile Carbon Capture Facility Powered By Decay Heat of Nuclear Spent Fuels." In 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20). American Nuclear Society, 2023. http://dx.doi.org/10.13182/nureth20-41353.

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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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Braeckeveldt, Marnix, Luc Ooms, and Gustaaf Geenen. "Dry Storage of Spent Research Reactor Fuel in Castor BR3® Casks at Belgoprocess in Belgium." 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/icem2001-1211.

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Abstract The BR3 reactor (10.5 MWe) at the Nuclear Research Center SCK•CEN was the first PWR plant installed in Europe and has been shut down in 1987. The BR3 reactor is from 1989 in a decommissioning stage and most of the spent fuel is presently still stored in the deactivation pool of the BR3 plant and has to be evacuated. The BR3 was used as a test-reactor for new fuel types and assemblies (Mixed Oxide (MOX) fuel, fuel rods containing burnable poison (Gd2O3) and other types of fuels). Some fuel rods, having undergone a destructive analysis, are stored in different laboratories at the SCK•CE

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Taniguchi, Daisuke, Naoki Hirokawa, and Yuki Ishiwatari. "Development of Fuel Route/Dropped Load PSA for UK ABWR." In 2018 26th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2018. http://dx.doi.org/10.1115/icone26-82022.

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Generic Design Assessment (GDA) of Hitachi-GE’s United Kingdom (UK) Advanced Boiling Water Reactor (ABWR) was completed in December 2017. Various Probabilistic Safety Assessment/Analyses (PSAs) are utilized to provide the risk insights for design of UK ABWR. This paper provides the characteristics of “Fuel Route/Dropped Load” PSA which is included in the scope of UK ABWR PSA and focuses on the effects of dropped load. “Fuel Route” means the all areas where the new or spent fuels are moved or stored. Shutdown PSA and Spent Fuel Storage Pool (SFP) PSA cover large parts of risk assessment for the

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Boubcher, Mustapha, Zhiliang Meng, Catherine M. Cottrell, and Sermet Kuran. "Advanced Fuel CANDU Reactor (AFCR) Core Physics With High-Burnup Recycled Uranium and Uranium-Thorium Fuel." In 2013 21st International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2013. http://dx.doi.org/10.1115/icone21-16662.

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The CANDU reactor has flexibility for using alternative fuels, such as Recycled Uranium (RU), low-enriched uranium and thorium (LEU/Th) and plutonium-thorium (Pu/Th) based fuels. This capability results from a versatile pressure tube design, simple fuel bundle, on-power refuelling, and high neutron economy. The Advanced Fuel CANDU Reactor (AFCR), which retains the excellent neutron economy and fuel cycle flexibility that are inherent in the CANDU reactor design, is a design jointly undertaken by Candu Energy and its Chinese partners led by CNNC. The objective is to use RU that is planned to be

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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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Morris, Jenny, Stephen Wickham, Phil Richardson, Colin Rhodes, and Mike Newland. "Contingency Options for the Dry Storage of Magnox Spent Fuel in the UK." In ASME 2009 12th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2009. http://dx.doi.org/10.1115/icem2009-16330.

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The UK Nuclear Decommissioning Authority (NDA) is responsible for safe and secure management of spent nuclear fuel. Magnox fuel is held at some Magnox reactor sites and at Sellafield where it is reprocessed using a number of facilities. It is intended that all Magnox fuel will be reprocessed as described in the published Magnox Operating Programme (MOP) [1]. In the event, however, that a failure occurs within the reprocessing plant, the NDA has initiated a programme of activities to explore alternative contingency options for the management of wetted Magnox spent fuel. Magnox fuel comprises me

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Hyland, 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.

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With world stockpiles of used nuclear fuel increasing, the need to address the long-term utilization of this resource is being studied. Many of the transuranic (TRU) actinides in nuclear spent fuel produce decay heat for long durations, resulting in significant nuclear waste management challenges. These actinides can be transmuted to shorter-lived isotopes to reduce the decay heat period or consumed as fuel in a CANDU® reactor. Many of the design features of the CANDU reactor make it uniquely adaptable to actinide transmutation. The small, simple fuel bundle simplifies the fabrication and hand

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Reports on the topic "Spent reactor fuels"

1

Valentine, T. E., J. T. Mihalczo, R. C. Kryter, and V. C. Miller. Subcritical Noise Analysis Measurements with Fresh and Spent Research Reactor Fuels Elements. Office of Scientific and Technical Information (OSTI), 1999. http://dx.doi.org/10.2172/12457.

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2

Cooper, T. D. Spent nuclear fuel project recommended reaction rate constants for corrosion of N-Reactor fuel. Office of Scientific and Technical Information (OSTI), 1998. http://dx.doi.org/10.2172/362570.

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3

Trahan, Alexis Chanel. Safeguarding Reactors and Spent Nuclear Fuel. Office of Scientific and Technical Information (OSTI), 2020. http://dx.doi.org/10.2172/1623417.

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4

Trahan, Alexis. Safeguards for Reactors and Spent Fuel. Office of Scientific and Technical Information (OSTI), 2021. http://dx.doi.org/10.2172/1804306.

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5

Walling, R. C., C. M. Heeb, and W. L. Purcell. Reactor-specific spent fuel discharge projections, 1987-2020. Office of Scientific and Technical Information (OSTI), 1988. http://dx.doi.org/10.2172/5325630.

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6

Westerdale, S. S., A. Junghans, R. J. deBoer, M. Pigni, and P. Dimitriou. Summary Report of the Technical Meeting on (alpha,n) Nuclear Data Evaluations and Data Needs. IAEA Nuclear Data Section, 2022. http://dx.doi.org/10.61092/iaea.vdj4-pakp.

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Abstract:

A Technical Meeting addressing (α,n) data needs for applications spanning reactor operation and safeguards, nonproliferation and spent fuel management, low-background experiments, and nuclear astrophysics was organised by the IAEA from 8 to 12 November 2021. Over 60 participants from fifteen Member States attended the virtual event. Participants reviewed the status of (α,n) measurements, models, codes and evaluated libraries with a view to identifying the gaps in the above areas and proposing the necessary actions to address them and produce reliable (α,n) data for the applications. A summary

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7

Heeb, C. M., R. A. Libby, and G. M. Holter. Reactor-specific spent fuel discharge projections, 1984 to 2020. Office of Scientific and Technical Information (OSTI), 1985. http://dx.doi.org/10.2172/5678444.

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8

Heeb, C. M., R. C. Walling, and W. L. Purcell. Reactor-specific spent fuel discharge projections: 1986 to 2020. Office of Scientific and Technical Information (OSTI), 1987. http://dx.doi.org/10.2172/6530788.

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9

Heeb, C. M., R. A. Libby, R. C. Walling, and W. L. Purcell. Reactor-specific spent fuel discharge projections: 1985 to 2020. Office of Scientific and Technical Information (OSTI), 1986. http://dx.doi.org/10.2172/5369258.

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10

Murphy, B. D. Characteristics of Spent Fuel from Plutonium Disposition Reactors. Vol. 3: A Westinghouse Pressurized-Water Reactor Design. Office of Scientific and Technical Information (OSTI), 1997. http://dx.doi.org/10.2172/652690.

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