Готові списки джерел за темами / Storage of spent nuclear fuel

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Добірка наукової літератури з теми "Storage of spent nuclear fuel"

Автор: Grafiati

Опубліковано: 30 травня 2022

Оновлено: 31 травня 2022

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Статті в журналах з теми "Storage of spent nuclear fuel"

Ewing, Rodney C. "Long-term storage of spent nuclear fuel." Nature Materials 14, no. 3 (February 20, 2015): 252–57. http://dx.doi.org/10.1038/nmat4226.

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Saegusa, Toshiari. "Concrete cask storage of spent nuclear fuel." Nuclear Engineering and Design 238, no. 5 (May 2008): 1167. http://dx.doi.org/10.1016/j.nucengdes.2007.03.029.

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Predd, P. P. "Perils of plutonium [spent nuclear fuel storage]." IEEE Spectrum 42, no. 7 (2005): 16–17. http://dx.doi.org/10.1109/mspec.2005.1460342.

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Santo Domingo, Jorge W., Christopher J. Berry, Michael Summer, and Carl B. Fliermans. "Microbiology of Spent Nuclear Fuel Storage Basins." Current Microbiology 37, no. 6 (December 1998): 387–94. http://dx.doi.org/10.1007/s002849900398.

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Papp, Reiner. "Guidebook on Spent Fuel Storage." Journal of Nuclear Materials 200, no. 2 (April 1993): 270. http://dx.doi.org/10.1016/0022-3115(93)90338-y.

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Esmail, Shadwan M. M., and Jae Hak Cheong. "Technical Options and Cost Estimates for Spent Nuclear Fuel Management at the Barakah Nuclear Power Plants." Science and Technology of Nuclear Installations 2021 (November 12, 2021): 1–25. http://dx.doi.org/10.1155/2021/3133433.

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In the planning and management of the interim storage of spent nuclear fuel, the technical and economic parameters that are involved have a significant role in increasing the efficiency of the storage system. Optimal parameters will reduce the total economic costs for countries embarking on nuclear energy, such as the UAE. This study evaluated the design performance and economic feasibility of various structures and schedules, to determine an optimal combination of parameters for the management of spent nuclear fuel. With the introduction of various storage technology arrangements and expected costs per unit for the storage system design, we evaluated eight major scenarios, each with a cost analysis based on technological and economic issues. We executed a number of calculations based on the use of these storage technologies, and considered their investment costs. These calculations, which were aligned with the net present value approach and conducted using MS Project and MATLAB software programs, considered the capacities of the spent fuel pools and the amount of spent nuclear fuel (SNF) that will be transferred to dry storage facilities. As soon as they sufficiently cool, the spent nuclear fuel is to be stored in a pool storage facility. The results show that applying a centralized dry storage (CDS) system strategy is not an economically feasible solution, compared with using a permanent disposal facility (PDF) (unless the variable investment cost is reduced or changed). The optimal strategy involves operating a spent fuel pool island (SFPI) storage after the first 20 years of the start of the permanent shutdown of the reactor. After 20 years, the spent fuel is then transferred to a PDF. This strategy also results in a 20.9% to 26.1% reduction in the total cost compared with those of the other strategies. The total cost of the proposed strategy is approximately 4,307 million USD. The duration of the fuel storage and the investment cost, particularly the variable investment cost, directly affect the choice of facility storage.

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ARITOMI, Masanori, Shigebumi AOKI, Toshiari SAEGUSA, Ryou KAWASAKI, and Masaaki OCHIAI. "Dry cask storage of spent fuel." Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan 31, no. 3 (1989): 331–46. http://dx.doi.org/10.3327/jaesj.31.331.

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Alyokhina, S., О. Dybach, A. Kostikov, and D. Dimitriieva. "Prediction of the maximum temperature inside container with spent nuclear fuel." Nuclear and Radiation Safety, no. 2(78) (June 7, 2018): 31–35. http://dx.doi.org/10.32918/nrs.2018.2(78).05.

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The definition of the thermal state of containers with spent nuclear fuel is important part of the ensuring of its safe storage during all period of storage facility operation. The this work all investigations are carried out for the storage containers of spent nuclear fuel of WWER-1000 reactors, which are operated in the Dry Spent Nuclear Fuel Storage Facility in Zaporizhska NPP. The analysis of existing investigations in the world nuclear engineering science concerning to the prediction of maximum temperatures in spent nuclear fuel storage container is carried out. The absence of studies in this field is detected and the necessity of the dependence for the maximum temperature in the storage container and temperature of cooling air on the exit of ventilation duct from variated temperatures of atmospheric air and decay heat formulation is pointed out. With usage of numerical simulation by solving of the conjugate heat transfer problems, the dependence of maximum temperatures in storage container with spent nuclear fuel from atmospheric temperature and decay heat is detected. The verification of used calculation method by comparison of measured air temperature on exit of ventilation channels and calculated temperature of cooling air was carried out. By regression analysis of numerical results of studies the dependence of ventilation air temperature from the temperature of atmospheric air and the decay heat of spent nuclear fuel was formulated. For the obtained dependence the statistical analysis was carried out and confidence interval with 95% of confidence is calculated. The obtained dependences are expediently to use under maximum temperature level estimation at specified operation conditions of spent nuclear fuel storage containers and for the control of correctness of thermal monitoring system work.

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Hwang, J. Y., and L. E. Efferding. "Development of a Thermal Analysis Model for a Nuclear Spent Fuel Storage Cask and Experimental Verification With Prototype Testing." Journal of Engineering for Gas Turbines and Power 111, no. 4 (October 1, 1989): 647–51. http://dx.doi.org/10.1115/1.3240306.

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A thermal analysis evaluation is presented of a nuclear spent fuel dry storage cask designed by the Westinghouse Nuclear Components Division. The cask is designed to provide passive cooling of 24 Pressurized Water Reactor (PWR) spent fuel assemblies for a storage period of at least 20 years at a nuclear utility site (Independent Spent Fuel Storage Installation). A comparison is presented between analytical predictions and experimental results for a demonstration cask built by Westinghouse and tested under a joint program with the Department of Energy and Virginia Power Company. Demonstration testing with nuclear spent fuel assemblies was performed on a cask configuration designed to store 24 intact spent fuel assemblies or canisters containing fuel consolidated from 48 assemblies.

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Trofymenko, О. R., І. M. Romanenko, М. І. Holiuk, C. V. Hrytsiuk, P. М. Kutsyn, А. V. Nosovskyi, Y. М. Pysmennyy, and V. І. Gulik. "The Three-Dimensional Neutron-Physical Model of Spent Nuclear Fuel Storage System." Nuclear Power and the Environment 20 (2021): 51–59. http://dx.doi.org/10.31717/2311-8253.21.1.4.

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The management of spent nuclear fuel is one of the most pressing problems of Ukraine’s nuclear energy. To solve this problem, as well as to increase Ukraine’s energy independence, the construction of a centralized spent nuclear fuel storage facility is being completed in the Chornobyl exclusion zone, where the spent fuel of Khmelnytsky, Rivne and South Ukrainian nuclear power plants will be stored for the next 100 years. The technology of centralized storage of spent nuclear fuel is based on the storage of fuel assemblies in ventilated HI-STORM concrete containers manufactured by Holtec International. Long-term operation of a spent nuclear fuel storage facility requires a clear understanding of all processes (thermohydraulic, neutron-physical, aging processes, etc.) occurring in HI-STORM containers. And this cannot be achieved without modeling these processes using modern specialized programs. Modeling of neutron and photon transfer makes it possible to analyze the level of protective properties of the container against radiation, optimize the loading of MPC assemblies of different manufacturers and different levels of combustion and evaluate biological protection against neutron and gamma radiation. In the future it will allow to estimate the change in the isotopic composition of the materials of the container, which will be used for the management of aging processes at the centralized storage of spent nuclear fuel. The article is devoted to the development of the three-dimensional model of the HI-STORM storage system. The model was developed using the modern Monte Carlo code Serpent. The presented model consists of models of 31 spent fuel assemblies 438MT manufactured by TVEL company, model MPC-31 and model HISTORM 190. The model allows to perform a wide range of scientific tasks required in the operation of centralized storage of spent nuclear fuel.

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Дисертації з теми "Storage of spent nuclear fuel"

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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Dissertacao (Mestrado)
IPEN/D
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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Tese (Doutoramento)
IPEN/T
Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP

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Hartnick, Megan Donna. "Evaluation of nuclear spent fuel dry storage casks and storage facility designs." Master's thesis, University of Cape Town, 2017. http://hdl.handle.net/11427/25279.

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Koeberg Nuclear Power Station (KNPS) is the only nuclear power station in Africa and it stores its spent nuclear fuel (SNF) onsite in the spent fuel pool (SFP). Additional aged SNF assemblies are stored in dry storage casks in a facility located on the KNPS site. This minor research dissertation aims at evaluating various dry storage cask found in open literature. The dissertation provides an overview of cask types, heat transfer, radiation shielding and storage facility types. Specific criteria are required in the selection of casks and the storage facility to house the casks on site. The selection criteria for casks and the storage facility were determined and technically evaluated in this dissertation. The selected casks were evaluated in terms of SNF criticality, radiation shielding, decay heat removal and heat transfer. Other aspects also determined by calculation were the seismic stability of casks and the cask footprint. The results obtained show the relationship of the spent fuel (SF) packing density between the different casks. Different shielding materials are used in the casks and it aided the heat transfer process to take place with some casks having additional features which included cooling fins and air vents for adequate cooling of the SNF. Through these some trends could be identified which could be used in the selection or design of new storage casks. Recommendations for further study are to evaluate a greater range of casks to verify and improve upon the relationship of evaluated parameters that were shown in the technical evaluation. These casks should all have similar means of maintaining sub-criticality, shielding and heat removal in order to generate comparable results.

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Chen, Xinhui 1966. "Thermal analysis of dry spent fuel transportation and storage casks." Thesis, Massachusetts Institute of Technology, 1996. http://hdl.handle.net/1721.1/38395.

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Khoza, Best. "Physics and engineering aspects of South Africa's proposed dry storage facility for spent nuclear fuel." Master's thesis, Faculty of Engineering and the Built Environment, 2019. https://hdl.handle.net/11427/31697.

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The continual increase in electricity dependence for the advancement of society has led to increased demand in electricity globally. This increased demand, among other things such as global warming interventions and energy security have encouraged the need to diversify electricity generation sources. Civilian use of nuclear power dates back to the 1950s. The United States of America and France are currently leading with the highest nuclear power generation in the world, generating 101 GWe and 63 GWe, respectively. Several countries such as China and the United Arab Emirates have committed to new nuclear build in order to increase their nuclear power generation capacities. Standing against the prospects of growth of the nuclear power industry are technical and nontechnical challenges. These include proliferation risk, safety, high capital costs and high-level waste management. Most spent nuclear fuel from power reactors is currently stored in the spent fuel pools on reactor sites, and some have been reprocessed. It is estimated that about 32% (370 000 tons of Heavy Metal) of the total spent fuel generated from power reactors have been reprocessed up to date. With most of the spent fuel pools filling up, alternative interim and long term disposal of spent nuclear fuel solutions have been under investigation from as early as the 1970s. South Africa has planned an interim dry storage facility for the spent nuclear fuel to be established at the existing Koeberg power station. The interim dry storage facility will make use of HI-STAR 100 multi-purpose casks to store spent nuclear fuel until the country decides on final disposal solution. There are many aspects that are critical to safe, efficient and cost-effective long term storage of spent nuclear fuel. Some of the physics and engineering aspects concerning dry storage facilities are briefly discussed. The aspects presented here are: radiation containment, spent fuel, sub-criticality, decay heat removal, site location aspects, response to seismic events, cask corrosion, transportation infrastructure, operability and monitoring. The study of the three existing dry cask storages from the USA, Hungary and Belgium gives an overview of the dry cask technology in use today. These presentations are based on publicly available reliable information. The proposed dry storage facility at Koeberg will be in the existing power station footprint using the HI-STAR 100 casks. The decision to have the proposed dry storage facility at Koeberg will minimise related licence applications and part of security installations as the site already has some security. The location of the facility in the power station’s footprint also allows for cost-effective and safe transportation of casks from the reactor building to the proposed facility. The modularity aspect of the dry cask storage facility at MV Paks in Hungary should also be employed at Koeberg to allow for more storage. This will cater for additional casks that may need to be stored if more nuclear power plants are procured in the future. South Africa’s air traffic around the Western Cape is not as congested as Belgium’s. There is, therefore, no need for the casks to be housed in concrete buildings like Doel’s. Most of Koeberg’s high-level waste would have had a longer cooling time in the pools compared to the minimum cooling time required for the chosen cask technology. This will provide a conservative, safe approach for Koeberg’s facility. Dry cask storage technology has provided a reliable interim dry storage solution for several countries. Despite uncertainties for long term disposal options, the proposed dry cask storage facility at Koeberg is a suitable interim storage alternative for South Africa to allow continuous operation of the plant. This conclusion is based on the physics and engineering aspects that have been presented in this minor dissertation.

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Hugo, Bruce Robert. "Modeling evaporation from spent nuclear fuel storage pools| A diffusion approach." Thesis, Washington State University, 2016. http://pqdtopen.proquest.com/#viewpdf?dispub=10043059.

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Accurate prediction of evaporative losses from light water reactor nuclear power plant (NPP) spent fuel storage pools (SFPs) is important for activities ranging from sizing of water makeup systems during NPP design to predicting the time available to supply emergency makeup water following severe accidents. Existing correlations for predicting evaporation from water surfaces are only optimized for conditions typical of swimming pools. This new approach modeling evaporation as a diffusion process has yielded an evaporation rate model that provided a better fit of published high temperature evaporation data and measurements from two SFPs than other published evaporation correlations. Insights from treating evaporation as a diffusion process include correcting for the effects of air flow and solutes on evaporation rate. An accurate modeling of the effects of air flow on evaporation rate is required to explain the observed temperature data from the Fukushima Daiichi Unit 4 SFP during the 2011 loss of cooling event; the diffusion model of evaporation provides a significantly better fit to this data than existing evaporation models.

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Fairlie, Ian. "Radioactive waste : international examination of storage and reprocessing of spent fuel." Thesis, Imperial College London, 1997. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.268029.

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Burns, Joe 1966. "On selection and operation of an international interim storage facility for spent nuclear fuel." Thesis, Massachusetts Institute of Technology, 2004. http://hdl.handle.net/1721.1/16642.

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Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 2004.
Includes bibliographical references.
This electronic version was submitted by the student author. The certified thesis is available in the Institute Archives and Special Collections.
Disposal of post-irradiation fuel from nuclear reactors has been an issue for the nuclear industry for many years. Most countries currently have no long-term disposal strategy in place. Therefore, the concept of an intermediate nuclear spent fuel storage facility has been introduced as a method of temporarily storing the spent fuel in a central location until long-term disposal of the spent nuclear fuel is made available. General criteria that can be used to compare potential international sites for an intermediate nuclear spent fuel storage facility have been identified and elucidated. Those criteria were then utilized to compare four potential international intermediate nuclear spent fuel storage facility (IINSFSF) sites. Two of the sites are in Russia (one in the area of the old nuclear city of Krasnoyarsk-26 currently known as Zheleznogorsk and one on Sakhalin Island in the area of the town of Kholmsk), one is in China (in the area of the town of Xilinhot in the Nei Mongol province) and one in Australia (in the area of the city of Meekatharra in Western Australia). Safety and safeguard regulations for nuclear facilities were reviewed and appropriate portions that could be applied to a potential IINSFSF are recommended. An analysis was conducted to determine legal issues pertinent to an IINSFSF and a brief, limited overview of the most important legal issues is presented. The effects that nuclear fuels subjected to higher burnups (than practiced now) will have on dry cask storage was examined and recommendations for storage strategies are proposed.
(cont.) The selected criteria involve the areas of Geological Suitability, Seismic Stability, Land Area Suitability, Site Infrastructure Suitability, Transportation Infrastructure Suitability, Meteorological Suitability, Willingness of the Host Nation and Population Density. Application of the criteria to the suggested sites revealed that Krasnoyarsk - 26 is the best alternative. This is mainly due to the willingness of the host nation of Russia to accept this type of facility. Krasnoyarsk - 26 also rates as the best site with respect to the criteria of geological suitability and seismic suitability. Without consideration for the willingness of the host nation, Meekatharra would be the ideal site. Xilinhot was evaluated as the third best alternative followed by the Sakhalin Island site of Kholmsk. The legal issue that would be of most concern to an IINSFSF would be potential liability. It would be best if the host nation were a signatory of an international treaty limiting the liability of the IINSFSF operator. Of the two major international nuclear liability treaties in existence the one preferable is the Paris Convention. Economics are driving nuclear power plants in the United States to look to implement more highly enriched fuels to achieve higher burnupsHow these higher burnup spent fuels will affect dry cask storage of spent fuels at reactor sites should be examined. To determine this, the decay heat output of higher burnup spent fuels was compared to the storage capacity of a typical dry cask storage system ...
by Joe Burns.
S.M.

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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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Fortkamp, Jonathan C. "Characterization of the radiation environment for a large area interim spent nuclear fuel storage facility /." The Ohio State University, 1999. http://rave.ohiolink.edu/etdc/view?acc_num=osu1488188894437725.

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Книги з теми "Storage of spent nuclear fuel"

Holt, Mark. Civilian nuclear spent fuel temporary storage options. [Washington, D.C.]: Congressional Research Service, Library of Congress, 1998.

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Lambert, J. D. B., and K. K. Kadyrzhanov, eds. Safety Related Issues of Spent Nuclear Fuel Storage. Dordrecht: Springer Netherlands, 2007. http://dx.doi.org/10.1007/978-1-4020-5903-2.

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

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International Symposium on Safety and Engineering Aspects of Spent Fuel Storage (1994 Vienna). Safety and engineering aspects of spent fuel storage: Proceedings of an International Symposium on Safety and Engineering Aspects of Spent Fuel Storage. Vienna: International Atomic Energy Agency, 1995.

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National Research Council (U.S.). Committee on the Safety and Security of Commercial Spent Nuclear Fuel Storage. Safety and security of commercial spent nuclear fuel storage: Public report. Washington, D.C: National Academies Press, 2006.

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1930-, Schweitzer Glenn E., Robbins Kelly, National Research Council (U.S.). Office for Central Europe and Eurasia., National Academies Press (U.S.), and Rossiĭskai︠a︡ akademii︠a︡ nauk, eds. Setting the stage for international spent nuclear fuel storage facilities: International workshop proceedings. Washington, D.C: National Academies Press, 2008.

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Wagner, J. C. Assessment of reactivity margins and loading curves of for PWR burnup-credit cask designs. Washington, DC: Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2003.

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Wagner, J. C. Recommendations for addressing axial burnup in PWR burnup credit analyses. Washington, DC: Division of Systems Analysis and Regulatory Effectiveness, U.S. Nuclear Regulatory Commission, 2003.

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Wagner, J. C. Recommendations on the credit for cooling time in PWR burnup credit analyses. Washington, DC: Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2003.

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Частини книг з теми "Storage of spent nuclear fuel"

Lambert, R. W., and R. L. Yang. "US Commercial LWR Spent Fuel Storage." In Nuclear Materials Safety Management, 139–42. Dordrecht: Springer Netherlands, 1998. http://dx.doi.org/10.1007/978-94-011-5070-5_20.

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Kurnosov, V. A., Yu V. Kozlov, V. V. Spichev, and N. S. Tikhonov. "Safety Problems in Storage and Transportation of Spent Fuel." In Nuclear Materials Safety Management, 169–81. Dordrecht: Springer Netherlands, 1998. http://dx.doi.org/10.1007/978-94-011-5070-5_23.

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Nyikos, Lajos, Tamás Pajkossy, and Robert Schiller. "Corrosion in a Spent Fuel Storage Basin." In Microbial Degradation Processes in Radioactive Waste Repository and in Nuclear Fuel Storage Areas, 121–24. Dordrecht: Springer Netherlands, 1997. http://dx.doi.org/10.1007/978-94-011-5792-6_14.

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Liu, Y. Y. "Ageing Management for Extended Storage of Spent Nuclear Fuel." In The Ageing of Materials and Structures, 119–37. Cham: Springer International Publishing, 2017. http://dx.doi.org/10.1007/978-3-319-70194-3_10.

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Kritskij, V. "Wet Storage of Spent Nuclear Fuel: Corrosion Process Investigations." In Microbial Degradation Processes in Radioactive Waste Repository and in Nuclear Fuel Storage Areas, 125–30. Dordrecht: Springer Netherlands, 1997. http://dx.doi.org/10.1007/978-94-011-5792-6_15.

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Vorobyov, A. I., S. V. Demyanovsky, R. G. Mudarisov, and V. D. Ptashny. "Container for Transportation and Long-Term Storage of Spent Nuclear Fuel." In Nuclear Materials Safety Management, 269–70. Dordrecht: Springer Netherlands, 1998. http://dx.doi.org/10.1007/978-94-011-5070-5_33.

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Zhang, Yu, Weidong Rong, Shiwei Wang, Zheng Zheng, and Wenbin Wei. "The Study of Extending AP1000 Spent Fuel Racks’ Storage Capacity." In Proceedings of The 20th Pacific Basin Nuclear Conference, 295–305. Singapore: Springer Singapore, 2017. http://dx.doi.org/10.1007/978-981-10-2317-0_29.

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Artak, Barseghyan, and Martoyan Gagik. "Transportation and Storage of Spent Nuclear Fuel: Security and Theory." In Transport of Dangerous Goods, 227–49. Dordrecht: Springer Netherlands, 2011. http://dx.doi.org/10.1007/978-94-007-2684-0_9.

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Earle, O. Keener. "Options for the Handling and Storage of Nuclear Vessel Spent Fuel." In Remaining Issues in the Decommissioning of Nuclear Powered Vessels, 285–95. Dordrecht: Springer Netherlands, 2003. http://dx.doi.org/10.1007/978-94-010-0209-7_31.

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Rothwell, Geoffrey. "An Economic Review of Monitored Retrievable Storage for Spent Nuclear Fuel." In Transportation of Hazardous Materials, 63–76. Boston, MA: Springer US, 1993. http://dx.doi.org/10.1007/978-1-4615-3222-4_5.

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Тези доповідей конференцій з теми "Storage of spent nuclear fuel"

Wang, Xinyu, Richard Cable Kurwitz, and Zhijian Zhang. "Optimization of Fuel Storage in Spent Fuel Pool." In 2018 26th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2018. http://dx.doi.org/10.1115/icone26-81084.

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This paper is the optimization of fuel assembly placement in the spent fuel pool according to the categorized rules. Only some specifically reactivity class assemblies could put together as the pattern. The allowable patterns, the number of the fuel assembly for each reactivity class and the number of RCCAs are from the nuclear power plant technique specification. Each assembly in the pool should obey the pattern rules and the user needs the optimal spent fuel pool configuration that could maximize the free space. In this study, the genetic algorithm and greedy algorithm are discussed, and both of two algorithms have the difficulties to the real engineering problem. A new approach that improves the greedy strategy at each step is proposed, make the greedy algorithm is more adapted to the engineering problem. Use the new approach to test Seabrook Unit 1 and Arkansas Unit 2 spent fuel pool at different cases, and show results by the visible figures. The output arrangements by the program shown that the results are satisfied the user requirements.

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Botsch, Wolfgang, Silva Smalian, Peter Hinterding, Holger Völzke, Dietmar Wolff, and Eva-Maria Kasparek. "Safety Aspects of Dry Spent Fuel Storage and Spent Fuel Management." In ASME 2013 15th International Conference on Environmental Remediation and Radioactive Waste Management. American Society of Mechanical Engineers, 2013. http://dx.doi.org/10.1115/icem2013-96039.

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As with the storage of all radioactive materials, the storage of spent nuclear fuel (SF) and high-level radioactive waste (HLW) must conform to safety requirements. Safety aspects like safe enclosure of radioactive materials, safe removal of decay heat, nuclear criticality safety and avoidance of unnecessary radiation exposure must be achieved throughout the storage period. The implementation of these safety requirements can be achieved by dry storage of SF and HLW in casks as well as in other systems such as dry vault storage systems or spent fuel pools, where the latter is neither a dry nor a passive system. After the events of Fukushima, the advantages of passively and inherently safe dry storage systems have become more obvious. TÜV and BAM, who work as independent experts for the competent authorities, present the licensing process for sites and casks and inform about spent nuclear fuel management and issues concerning dry storage of spent nuclear fuel, based on their long experience in these fields. All safety relevant issues like safe enclosure, shielding, removal of the decay heat or behavior of cask and building under accident conditions are checked and validated with state-of-the-art methods and computer codes before the license approval. It is shown how dry storage systems can ensure the compliance with the mentioned safety criteria over a long storage period. Exemplarily, the process of licensing, erection and operation of selected German dry storage facilities is presented.

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Wang, Mengqi, Nan Pan, Hui Li, and Baojun Jia. "Radiation Shielding Analysis of a Spent Fuel Dry Storage Cask for FA300 Spent Fuel Assemblies." In 2017 25th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2017. http://dx.doi.org/10.1115/icone25-66462.

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Spent fuel dry storage technology is one of the most important intermediate storage technologies for spent fuel, because of its high security, good economic and easy to expand the scale. This article aims at designing a spent fuel dry storage cask which can contain 21 FA300 spent fuel assemblies. The spent fuel dry storage cask is designed as concrete cask structure, which has the advantages of low manufacturing cost and simple manufacturing technology. Ventilation channels are designed for heating transfer, because the concrete is not a good thermal conductivity material. And labyrinth structure is designed for the ventilation channel to reduce the cavity streaming. Radiation sources in spent fuel assemblies are mainly produced from fission products, actinides and their daughters located inside the effective fuel region, and other activation products in structure materials, which are calculated by ORIGEN. The source and geometry of this problem are complex, and this is a real world deep penetration and streaming problem. Discrete ordinate method has great advantage in solving the deep penetration problem. Based on three-dimensional discrete ordinate code TORT, radiation shielding design method for spent fuel dry storage cask is studied, including main shield cask, cover lid, and ventilation channel. The results show that this spent fuel dry storage cask containing 21 FA300 spent fuel (cooling time: 10 years) assemblies can satisfy the requirement of dose rate limits in GB18871.

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Carter, Joe T., and Robert H. Jones. "Containers for Commercial Spent Nuclear Fuel." In ASME 2017 Pressure Vessels and Piping Conference. American Society of Mechanical Engineers, 2017. http://dx.doi.org/10.1115/pvp2017-66247.

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Kosiak, Pavlo, and Martin Lovecky. "Long-term storage of nuclear fuel in spent fuel casks." In 18TH CONFERENCE OF POWER SYSTEM ENGINEERING, THERMODYNAMICS AND FLUID MECHANICS. AIP Publishing, 2019. http://dx.doi.org/10.1063/1.5138625.

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Lloyd, Timothy M. "Solving the Challenges of Early Storage of Spent Fuel: the SENTRY™ Spent Fuel Management System." In 2021 28th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2021. http://dx.doi.org/10.1115/icone28-66590.

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Abstract Placing spent fuel into dry cask storage as soon as possible allows decommissioning plants to lower site risk, reduce costs associated with management and maintenance of the spent fuel pool, and accelerate decommissioning. The SENTRY™ Spent Fuel Management System1 is a dual-purpose system satisfying requirements for both storage and eventual transportation of the spent fuel. This paper describes the features and characteristics of the SENTRY system and explains the key areas where the product family represents a step change from existing industry offerings. Fuel being loaded into casks within times as low as 1.5 to 2 years presents substantial new challenges to electric utilities and cask vendors. Decay heat falls off as a sum of exponentials and is much higher at early times. By the 1.5 to 2 year timeframe, heat loads are decreasing on the order of 10% per month. Radiological source terms are not only falling in strength, but are also changing in energy intensity and type. Harder neutron and photon spectra at these earlier times must also be addressed. Thermal and radiological source term data for the SENTRY system have been established through the use of an NRC-approved Westinghouse data set characterizing fuel over a wide range of burnup, enrichment, and decay time values. This data is used to construct cooling tables which provide loading rules in the form of the minimum cooling time required to load the assembly in a particular zone of a SENTRY canister. No further plant-specific calculations or demonstrations are required by the utility. Unique to Westinghouse is the use of adjoint methods to develop shielding results, which are de-coupled from the source term associated with specific assemblies. As the industry’s leading performer of Reactor Vessel Surveillance Programs, Westinghouse makes routine use of a combined forward/adjoint approach to radiation transport. The adjoint shielding methodology allows for the explicit calculation of dose rates over a very large range of source term values with essentially no additional computation. As a result, Westinghouse can make use of its ADSORB computer code to develop shielding results for the full set of enrichment, burnup, and decay times described above. ADSORB also uses an equivalent process to determine the earliest time that ensures the fuel’s decay heat will fall below the analyzed values used to demonstrate acceptable thermal performance. The use of this methodology allows Westinghouse to establish the shortest overall time for which fuel can safely be placed into defined regions of a spent fuel canister.

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Yubin, Zhang, Ouyang Yong, Zhou Yuwei, and Liu Jinlin. "Accident Safety Evaluation Method for Spent Fuel Dry Storage Facilities." In 2017 25th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2017. http://dx.doi.org/10.1115/icone25-66508.

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Dry storage is one of the ways to store spent fuel in the middle of the reactor, which can effectively alleviate the pressure of the storage on the spent fuel pool of nuclear power plant. This paper tries to combine the site of dry storage facilities and the design characteristics to explain and discuss the safety evaluation method under the accident condition, from the mechanical analysis, critical safety, the decay heat removal, the shielding design and so on. Then according to the operating procedures and the accident condition that may be occurred, put forward some possible ways of monitoring and measures of safety protection should be added.

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Wang, Jinhua, Bing Wang, Bin Wu, and Yue Li. "Design of the Spent Fuel Storage Well of HTR-PM." In 2016 24th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2016. http://dx.doi.org/10.1115/icone24-60051.

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There are more than 400 reactors in operation to generate electricity in the world, most of them are pressurized water reactors and boiling water reactors, which generate great amount of spent fuel every year. The residual heat power of the spent fuel just discharged from the reactor core is high, it is required to store the spent fuel in the spent fuel storage pool at the first 5 years after discharged from the reactor, and then the spent fuel could be moved to the interim storage facility for long term storage, or be moved to the factory for final treatment. In the accident of the Fukushima in 2011, the spent fuel pool ruptured, which led to the loss of coolant accident, it was very danger to the spent fuel assemblies stored in the pool. On the other hand, the spent fuel stored in the dry storage facility was safe in the whole process of earthquake and tsunami, which proved inherent safety of the spent fuel dry storage facility. In china, the High Temperature gas cooled Reactor (HTR) is developing for a long time in support of the government. At the first stage, HTR-10 with 10MW thermal power was designed and constructed in the Institute of Nuclear Energy Technology (INET) of Tsinghua University, and then the High Temperature Reactor-Pebble bed Modules (HTR-PM) is designed to meet the commercial application, which is in constructing process in Shandong Province. HTR has some features of the generation four nuclear power plant, including inherent safety, avoiding nuclear proliferation, could generate high temperature industrial heat, and so on. Spherical fuel elements would be used as fuel in HTR-PM, there are many coating fuel particles separated in the fuel element. As the fuel is different for the HTR and the PWR, the fuel element would be discharged into the appropriate spent fuel canister, and the canister would be stored in the appropriate interim storage facility. As the residual power density is very low for the spent fuel of HTR, the spent fuel canister could be cooled with air ventilation without water cooling process. The advantage of air cooling mode is that it is no need to consider the residual heat removal depravation due to loss of coolant accident, so as to increase the inherent safety of the spent fuel storage system. This paper introduced the design, arrangement and safety characteristics of the spent fuel storage well of HTR-PM. The spent fuel storage wells have enough capacity to hold the total spent fuel canisters for the HTR-PM. The spent fuel storage facility includes several storage wells, cold intake cabin, hot air discharge cabin, heat shield cylinders, well lids and so on. The cold intake cabin links the inlets of all the wells, which would be used to import cold air to every well. The hot air discharge cabin links the outlets of all the wells, which would be used to gather heated air discharged from every well, the heated air would be discharged to the atmosphere through the ventilating pipe at the top of the hot air cabin. The design of the spent fuel storage well and the ventilating pipe could discharge the residual heat of the spent fuel canisters in the storage wells, which could ensure the operating safety of the spent fuel storage system.

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Shaukat, Syed K., and Vincent K. Luk. "Seismic Behavior of Spent Fuel Dry Cask Storage Systems." In 10th International Conference on Nuclear Engineering. ASMEDC, 2002. http://dx.doi.org/10.1115/icone10-22395.

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The U. S. Nuclear Regulatory Commission (NRC) is conducting a research program to investigate technical issues concerning the dry cask storage systems of spent nuclear fuel by conducting confirmatory research for establishing criteria and review guidelines for the seismic behavior of these systems. The program focuses on developing 3-D finite element analysis models that address the dynamic coupling of a module/cask, a flexible concrete pad, and an underlying soil/rock foundation, in particular, the soil-structure-interaction. Parametric analyses of the coupled models are performed to include variations in module/cask geometry, site seismicity, underlying soil properties, and cask/pad interface friction. The analyses performed include: 1) a rectangular dry cask module typical of Transnuclear West design at a site in Western USA where high seismicity is expected; 2) a cylindrical dry cask typical of Holtec design at a site in Eastern USA where low seismicity is expected; and 3) a cylindrical dry cask typical of Holtec design at a site in Western USA with medium high seismicity. The paper includes assumptions made in seismic analyses performed, results, and conclusions.

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Al Saadi, Sara, and Yongsun Yi. "Interim Storage of Spent Nuclear Fuel in the UAE Nuclear Power Plants." In 2014 22nd International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2014. http://dx.doi.org/10.1115/icone22-30081.

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The interim storage options of spent nuclear fuel (SNF) in Barakah nuclear power plants in the UAE were studied in terms of costs and technical issues. Considering the capacity of the spent fuel pools in Barakah nuclear power plants, two scenarios for the interim SNF storage were established. Scenario 1 is ‘minimum use of spent fuel pool’ that SNF will be transferred to dry storage facilities as soon as SNF has been sufficiently cooled down in a pool for the dry storage. Scenario 2 is defined as ‘maximum use of spent fuel pool’ that SNF will be stored in a pool as long as possible till the amount of stored SNF in the pool reaches the capacity of the pools and, then, to be moved for dry storage. For these two scenarios, cost analysis was performed in terms of net present values (NPVs) and levelized unit costs (LUCs). The life cycle of the dry storage was divided into three phases: i) preconstruction phase, ii) construction phase and iii) operation phase. By using data available in literature for the three phases, the total costs were calculated and compared between the two scenarios. For a basic analysis, using the discount rate of 5 % and the required cooling period (Tcool) of 7 years before the SNF transfer to dry storage, LUCs were 184 and 192 $/kg HM for Scenarios 1 and 2, respectively, which were comparable to other analysis results in literature. Then, additional calculations were performed using two different values of the discount rate and the cooling period, respectively. The NPV 1 for Scenario 1 ranges between 175.7 and 413.5 million 2014 $, depending on the discount rate and the cooling period, Tcool. For Scenario 2, NPVs of 85.2 and 237.3 million 2014 $ were obtained for discount rates of 7% and 3%, respectively. The comparisons of the NPVs between the two scenarios showed that Scenario 1 would cost 1.5 to 2.7 times Scenario 2. Technical issues of a dry storage system associated with the site specific conditions in the UAE were also studied. The higher ambient air temperature in the UAE than other countries could affect the cooling capacity of the dry storage by natural convection, which will affect the required cooling period (Tcool) in the spent fuel pool. Also, the harsh environments could have detrimental effects on the integrity of metallic components by degradation phenomena such as pitting, stress corrosion cracking (SCC). This discussion implies that the two aspects related to the harsh environment in the UAE should be studied as early as possible. The environmental and safety impacts associated with the dry storage of SNF were discussed. According to published reports in the USA it seems that there will be no significant environmental impacts of the dry storage for 60 years. However, it is judged that future studies should address the impacts for longer time period than 60 years.

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Звіти організацій з теми "Storage of spent nuclear fuel"

Karpius, Peter Joseph. Storage and Reprocessing of Spent Nuclear Fuel. Office of Scientific and Technical Information (OSTI), February 2017. http://dx.doi.org/10.2172/1342848.

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McKinnon, M. A., and V. A. DeLoach. Spent nuclear fuel storage -- Performance tests and demonstrations. Office of Scientific and Technical Information (OSTI), April 1993. http://dx.doi.org/10.2172/10150992.

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Lister, Tedd E., and Michael V. Glazoff. Transition of Spent Nuclear Fuel to Dry Storage: Modeling activities concerning aluminum spent nuclear fuel cladding integrity. Office of Scientific and Technical Information (OSTI), December 2018. http://dx.doi.org/10.2172/1492831.

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Swenson, C. E. Spent nuclear fuel canister storage building conceptual design report. Office of Scientific and Technical Information (OSTI), January 1996. http://dx.doi.org/10.2172/464058.

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Johnson, E. R., and K. J. Notz. Shipping and storage cask data for spent nuclear fuel. Office of Scientific and Technical Information (OSTI), November 1988. http://dx.doi.org/10.2172/6432956.

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Yu, Lingyu. Structural Health Monitoring of Nuclear Spent Fuel Storage Facilities. Office of Scientific and Technical Information (OSTI), April 2018. http://dx.doi.org/10.2172/1433370.

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Wang, Jy-An, Bruce Bevard, John Scaglione, and Rose Montgomery. Fracture toughness evaluations for spent nuclear fuel dry storage canister welds and spent nuclear fuel clad-pellet structures. Office of Scientific and Technical Information (OSTI), April 2021. http://dx.doi.org/10.2172/1782033.

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Bevard, Bruce Balkcom, Ugur Mertyurek, Randy Belles, and John M. Scaglione. BWR Spent Nuclear Fuel Integrity Research and Development Survey for UKABWR Spent Fuel Interim Storage. Office of Scientific and Technical Information (OSTI), October 2015. http://dx.doi.org/10.2172/1234354.

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KLEM, M. J. Spent Nuclear Fuel Project Canister Storage Building Functions and Requirements. Office of Scientific and Technical Information (OSTI), October 2000. http://dx.doi.org/10.2172/805645.

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Dana, W. P. Spent nuclear fuel Canister Storage Building CDR Review Committee report. Office of Scientific and Technical Information (OSTI), December 1995. http://dx.doi.org/10.2172/436521.

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