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Journal articles on the topic 'Spent nuclear fuel storage'

Author: Grafiati

Published: 5 June 2025

Last updated: 1 August 2025

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1

Rahayu, D. S., L. Ambarsari, S. E. Shalsabilla, et al. "Sulphate-reducing bacteria (SRB) in interim storage of spent nuclear fuel." IOP Conference Series: Earth and Environmental Science 1271, no. 1 (2023): 012057. http://dx.doi.org/10.1088/1755-1315/1271/1/012057.

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Abstract Interim Storage of Spent Nuclear Fuel (ISSF) is an installation for temporarily storing spent nuclear fuels. Nuclear fuel storage pools must be free from contamination by corrosion-causing microorganisms such as Sulphate Reduction Bacteria (SRB). This research aims to detect SRB on the pool’s wall, floor, and spent nuclear fuel racks. The measured parameters consisted of physicochemical, total bacteria, total SRB, and detection of SRB on the wall, floor, and spent fuel rack in the pool using the SRB kit. The results showed that the quality of the water chemistry in the pool was within

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2

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

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3

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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4

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

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5

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 (1998): 387–94. http://dx.doi.org/10.1007/s002849900398.

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6

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 (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 t

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7

Bonano, Evaristo J., Elena A. Kalinina, and Peter N. Swift. "The Need for Integrating the Back End of the Nuclear Fuel Cycle in the United States of America." MRS Advances 3, no. 19 (2018): 991–1003. http://dx.doi.org/10.1557/adv.2018.231.

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ABSTRACTCurrent practice for commercial spent nuclear fuel management in the United States of America (US) includes storage of spent fuel in both pools and dry storage cask systems at nuclear power plants. Most storage pools are filled to their operational capacity, and management of the approximately 2,200 metric tons of spent fuel newly discharged each year requires transferring older and cooler fuel from pools into dry storage. In the absence of a repository that can accept spent fuel for permanent disposal, projections indicate that the US will have approximately 134,000 metric tons of spe

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8

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

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9

Vaschenko, Volodymyr, Iryna Corduba, and Sergey Tsibitovsky. "NUCLEAR-ENVIRONMENTAL SAFETY OF STORAGE AND MANAGEMENT OF SPENT NUCLEAR FUEL." Construction Engineering, no. 41 (February 4, 2025): 128–41. https://doi.org/10.32347/tb.2024-41.0415.

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Today, the situation with spent nuclear fuel (SNF) is still complicated due to the lack of safe technologies for its cost-effective and environmentally friendly reprocessing and safe final disposal. Spent nuclear fuel is not waste in the classical definition and understanding. In this paper, spent nuclear fuel is defined as a valuable secondary energy raw material. The paper concludes that further, socially acceptable and guaranteed safe development of the global nuclear power industry is possible only under the condition of absolute priority of nuclear and environmental safety of the entire n

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10

Trofymenko, О. R., І. M. Romanenko, М. І. Holiuk, et al. "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 Intern

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11

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

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12

Timonova, L. N., O. N. Lyakhova, A. O. Aidarkhanov, and B. A. Abdigamitov. "ASSESSMNET OF INTEGRITY OF PROTECTIVE BARRIERS OF LONG-TERM STORAGE FACILITY OF BN -350 REACTOR FACILITY." NNC RK Bulletin, no. 2 (June 30, 2020): 49–54. http://dx.doi.org/10.52676/1729-7885-2020-2-49-54.

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One of the ways of long-term handling spent nuclear fuel is storage of spent nuclear fuel in containers. For the purpose of complex radiological assessment and to make long-term prediction estimates of radiological situation possible at the territory of spent nuclear fuel storage facility the control over emanation of radioactive gases into atmosphere should be provided. Gaseous wastes are one a kind of radioactive wastes resulting from operation of nuclear energy and industry facilities. And increase in their concentration in the air indicate radioactive wastes from nuclear power plants or me

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13

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

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14

Hakobyan, M. T., A. I. Ksenofontov, and S. A. Sargsyan. "Scenario analysis loss of heat removal from the spent fuel pool on nuclear power plant." Global Nuclear Safety 48, no. 3 (2023): 5–16. http://dx.doi.org/10.26583/gns-2023-03-01.

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The spent nuclear fuel storage system is designed to store and cool spent fuel for several years taking into account scheduled reloads and unloading of the entire core accumulated after use in a nuclear reactor. It consists of special pools or containers where spent fuel is placed for temporary storage before final treatment or disposal. These systems provide safe and efficient storage of spent fuel to prevent radioactive material from leaking into the environment and minimize risks to human health and the natural environment. The events that occurred during the Fukushima nuclear disaster on M

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15

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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16

Sapon, M., O. Gorbachenko, S. Kondratyev, et al. "Prevention of Damage to Spent Nuclear Fuel during Handling Operations." Nuclear and Radiation Safety, no. 2(86) (June 12, 2020): 62–71. http://dx.doi.org/10.32918/nrs.2020.2(86).08.

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According to regulatory requirements, when carrying out handling operations with spent nuclear fuel (SNF), prevention of damage to the spent fuel assemblies (SFA) and especially fuel elements shall be ensured. For this purpose, it is necessary to exclude the risk of SFA falling, SFA uncontrolled displacements, prevent mechanical influences on SFA, at which their damage is possible. Special requirements for handling equipment (in particular, cranes) to exclude these dangerous events, the requirements for equipment strength, resistance to external impacts, reliability, equipment desi

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17

Mitev, M., and K. Filipov. "Feasibility Study for Minor Actinides Transmutation in Conventional Power Reactors." IOP Conference Series: Earth and Environmental Science 1234, no. 1 (2023): 012016. http://dx.doi.org/10.1088/1755-1315/1234/1/012016.

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Abstract The handling and storage of the spent fuel from the current nuclear power reactors is one of the major ecological challenges in front of the nuclear energy industry, due to its long period of high radiotoxicity. It is mainly caused by the long-lived minor actinides generated in the nuclear fuel. Therefore profound study of the possibilities for shortening the terms of storage of spent nuclear fuels and some of high radioactive waste through the currently available technologies is necessary. The possibility for transmutation of Neptunium, Americium and Curium isotopes, as most abundant

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18

Schnellbach, Yan-Jie, Thomas Radermacher, Irmgard Niemeyer, Stefan Roth, and Malte Göttsche. "Antineutrino detection concepts for safeguarding spent nuclear fuel." Safety of Nuclear Waste Disposal 2 (September 6, 2023): 203. http://dx.doi.org/10.5194/sand-2-203-2023.

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Abstract. Spent nuclear fuel (SNF) from nuclear power generation requires long-term safeguards in interim storage and final disposal. Current safeguarding approaches for spent fuel storage facilities (SFSFs) propose a combination of material accountancy, containment and surveillance, and design information verification. Antineutrino emissions from the ongoing beta decay of fission fragments could provide complementary information on the potential diversion of nuclear material and misuse of the facility or assist in reverification scenarios as antineutrinos pass through any shielding, structure

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19

Chen, C. H., Y. J. Lin, C. H. Chen, and C. W. Yang. "The interface design of storage and examination system for BWR spent nuclear fuel dry storage demonstration project in Taiwan." Journal of Physics: Conference Series 2345, no. 1 (2022): 012013. http://dx.doi.org/10.1088/1742-6596/2345/1/012013.

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Abstract Due to the lack of Boiling Water Reactor (BWR) fuel examination data after dry storage, Taiwan Power Company and Institute of Nuclear Energy Research jointly launched the “Taiwan Nuclear Fuel Storage Demonstration Project” to collect fuel characteristics data under simulated dry storage. To meet the project requirements, BWR fuel rods in different fuel designs will be selected and then store in simulated storage containers in different environments for 10 years. The interface considerations and design results of the auxiliary equipment for spent nuclear fuel storage, transfer, and non

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20

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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21

Rejková, Jana, Jan Macák, and Lumír Nachmilner. "The Waste Disposal Package for Spent Nuclear Fuel." Chemické listy 116, no. 2 (2022): 110–14. http://dx.doi.org/10.54779/chl20220110.

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A key issue in the safety of spent nuclear fuel storage is the lifetime and effectiveness of barriers isolating the radioactive waste from the environment. In the event of a failure of the waste disposal package, the condition of the fuel pellets and the impact on their immediate surroundings will be an important factor. The goal of this review article is to summarize the state and changes of nuclear fuel at the end of the fuel cycle and the influence of the parameters of the deep repository environment on the corrosion processes of the engineered barriers and on the release of radionuclides d

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22

Makarenko, М., Yu Vorobyov, O. Zhabin, and М. Vyshemirskyi. "Thermal Analysis of Vertical Dry Storage Cask for Nuclear Spent Fuel in Off-Normal Conditions." Nuclear and Radiation Safety, no. 4(96) (December 21, 2022): 5–12. http://dx.doi.org/10.32918/nrs.2022.4(96).01.

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One of the key aspects for safety assessment of spent fuel dry storage systems is evaluation of the temperature profile for spent fuel in various storage conditions. In this effort, a three-dimensional model of a vertical dry storage HI‑STORM 190 UA system for VVER-1000 fuel is developed for ANSYS CFX code. This model is then used for the analysis of spent fuel thermal state in normal conditions and in a hypothetical case of a loss of the fuel canister integrity. Canister depressurization with helium leakage and its substitution with air lead to degradation of heat removal and increase of spen

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23

Moratilla Soria, B. Yolanda, Maria Uris Mas, Mathilde Estadieu, Ainhoa Villar Lejarreta, and David Echevarria-López. "Recycling versus Long-Term Storage of Nuclear Fuel: Economic Factors." Science and Technology of Nuclear Installations 2013 (2013): 1–7. http://dx.doi.org/10.1155/2013/417048.

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The objective of the present study is to compare the associated costs of long-term storage of spent nuclear fuel—open cycle strategy—with the associated cost of reprocessing and recycling strategy of spent fuel—closed cycle strategy—based on the current international studies. The analysis presents cost trends for both strategies. Also, to point out the fact that the total cost of spent nuclear fuel management (open cycle) is impossible to establish at present, while the related costs of the closed cycle are stable and known, averting uncertainties.

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24

Borysenko, V., V. Goranchuk, Yu Pionkovskyi, and M. Sapon. "Selection of Conservative Assumptions in Nuclear Safety Justification of SNF Storage Systems." Nuclear and Radiation Safety, no. 2(74) (May 22, 2017): 24–28. http://dx.doi.org/10.32918/nrs.2017.2(74).05.

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The paper addresses the description of computer model for the spent fuel assemblies storage system in SCALE and MCNP codes, as well as the results in selection of conservative assumptions made to justify the nuclear safety of moving, transport and storage operations with the VVER-1000 spent nuclear fuel (SNF) in designed Centralized Spent Fuel Storage Facility (CSFCF). When justifying the nuclear safety, it is necessary to confirm that the maximum value of the effective multiplication coefficient K eff in SNF storage systems is kept below specified limit of 0.95 in any design-basis operation m

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25

Alyokhina, S., A. Kostikov, D. Lunov, O. Dybach, and D. Dimitriieva. "Definition of mutual thermal influence of containers with spent nuclear fuel at the open storage site." Nuclear and Radiation Safety, no. 4(80) (December 3, 2018): 36–40. http://dx.doi.org/10.32918/nrs.2018.4(80).06.

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The problem of spent nuclear fuel handling in Ukraine is a key issue. A half of spent nuclear fuel is currently stored in Ukraine at the open-site dry storage facility at Zaporizhzhya NPP. Thermal safety analysis should be performed as a part of the storage facility safety assessment. Thermal analysis of a container group is a poorly investigated area. As literature review shows, current results do not clearly identify mutual influence of the containers and influence of weather conditions on the thermal condition of stored spent nuclear fuel. This type of analysis could be performed using the

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Hakobyan, David A., and Victor I. Slobodchuk. "Temperature conditions in the RBMK spent fuel pool in the event of disturbances in its cooling mode." Nuclear Energy and Technology 7, no. (1) (2021): 9–13. https://doi.org/10.3897/nucet.7.64363.

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The problems of reprocessing and long-term storage of spent nuclear fuel (SNF) at nuclear power plants with RBMK reactors have not been fully resolved so far. For this reason, nuclear power plants are forced to search for new options for the disposal of spent fuel, which can provide at least temporary SNF storage. One of the possible solutions to this problem is to switch to compacted SNF storage in reactor spent fuel pools (SFPs). As the number of spent fuel assemblies (SFAs) in SFPs increases, a greater amount of heat is released. In addition, no less important is the fact that a place for e

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27

Shugailo, O., and S. Smyshliaieva. "Monitoring of Spent Fuel Condition over Long-Term Storage." Nuclear and Radiation Safety, no. 1(105) (March 26, 2025): 4–16. https://doi.org/10.32918/nrs.2025.1(105).01.

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The Coordinated Research Projects (CRPs) of the International Atomic Energy Agency (IAEA) are a powerful tool for engaging multiple countries that operate spent fuel storage facilities to address important safety issues at a deep level of competence and expertise. One of the topics that needs thorough research is the behavior and condition assessment of spent fuel assemblies and fuel rods during long/very long-term storage in spent fuel storage facilities. Naturally, over an extended period, special attention is drawn to degradation mechanisms, aging effects and aging management programs that

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28

Бушуев, Н. И., and Э. И. Даниелов. "Economic justification of various methods of spent nuclear fuel storage." Экономика и предпринимательство, no. 11(136) (February 27, 2022): 1156–62. http://dx.doi.org/10.34925/eip.2021.11.136.231.

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Наличие долгоживущих изотопов высокой активности в отработавшем ядерном топливе требует его длительного хранения. Короткоживущие изотопы теряют активность во влажном бассейне реактора. Часть отработавшего топлива хранится в мокрых хранилищах, сухих хранилищах и других хранилищах. Основные методы хранения -краткосрочное мокрое и долговременные сухое и подземное. Мокрое хранение топлива осуществляется в железобетонных резервуарах, футерованных сталью под слоем воды. Вода действует как радиационная защита и обеспечивает необходимую температуру отработавшему топливу. В связи с повышенным тепловыде

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29

Mikloš, M., and V. Kršjak. "New Methods for Evaluation of Spent Fuel Condition during Long-Term Storage in Slovakia." Science and Technology of Nuclear Installations 2009 (2009): 1–5. http://dx.doi.org/10.1155/2009/459139.

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Experiences with an advanced spent nuclear fuel management in Slovakia are presented in this paper. The evaluation and monitoring procedures are based on practices at the Slovak wet interim spent fuel storage facility in NPP Jaslovské Bohunice. Since 1999, leak testing of WWER-440 fuel assemblies are provided by special leak tightness detection system “Sipping in pool” delivered by Framatomeanp with external heating for the precise defects determination. In 2006, a new inspection stand “SVYP-440” for monitoring of spent nuclear fuel condition was inserted. This stand has the possibility to ope

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30

Saegusa, T., K. Shirai, T. Arai, et al. "REVIEW AND FUTURE ISSUES ON SPENT NUCLEAR FUEL STORAGE." Nuclear Engineering and Technology 42, no. 3 (2010): 237–48. http://dx.doi.org/10.5516/net.2010.42.3.237.

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31

Kralik, M., V. Kulich, J. Studeny, and P. Pokorny. "Dosimetry at an interim storage for spent nuclear fuel." Radiation Protection Dosimetry 126, no. 1-4 (2007): 549–54. http://dx.doi.org/10.1093/rpd/ncm111.

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32

ANDERSON, EARL. "Utilities Face Squeeze in Spent Nuclear Fuel Storage Space." Chemical & Engineering News 63, no. 13 (1985): 11. http://dx.doi.org/10.1021/cen-v063n013.p011.

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33

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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34

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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35

Nguyen, Kien-Cuong, Vinh-Vinh Le, Ton-Nghiem Huynh, Ba-Vien Luong, Nhi-Dien Nguyen, and Hoai-Nam Tran. "Interim Storage of the Dalat Nuclear Research Reactor: Radiation Safety Analysis." Science and Technology of Nuclear Installations 2020 (December 7, 2020): 1–10. http://dx.doi.org/10.1155/2020/7327045.

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Radiation safety analysis of a new interim storage of the Dalat Nuclear Research Reactor (DNRR) for keeping spent high enriched uranium (HEU) fuel bundles during the core conversion to low enriched uranium (LEU) fuel had been performed and presented. The photon source and decay heat of the spent HEU fuel bundles were calculated using the ORIGEN2.1 code. Gamma dose rates of the spent fuel interim storage were evaluated using the MCNP5 code with various scenarios of water levels in the reactor tank and cooling time. The radiation safety analysis shows that the retention of 106 spent HEU fuel bun

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36

Vlček, Daniel. "RESIDUAL HEAT POWER REMOVAL FROM SPENT NUCLEAR FUEL DURING DRY AND WET STORAGE." Acta Polytechnica CTU Proceedings 19 (December 14, 2018): 36. http://dx.doi.org/10.14311/app.2018.19.0036.

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This project deals with the thermal analyses of the wet and dry storages of the spent nuclear fuel. The dry spent fuel storage sub-channel code COBRA-SFS has been used in order to calculate the temperature field. In this code, the new model of residual heat removal was created for the SKODA 1000/19 cask where the spent nuclear fuel TVSA-T type from NPP Temelin will be stored. The object of calculations was to obtain the inside temperatures under maximum loads. After that, the results were compared to the requirements of the local regulatory body. Because of the absence of experimental data, th

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SAEGUSA, Toshiari, and Masumi WATARU. "Current Status of Spent Fuel Storage Technology." Journal of the Atomic Energy Society of Japan 57, no. 4 (2015): 259–64. http://dx.doi.org/10.3327/jaesjb.57.4_259.

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38

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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Xu, Chende, Zhengguang Wang, Shuai Tang, et al. "Research Progress on Thermal Hydraulic Characteristics of Spent Fuel Pools: A Review." Energies 16, no. 10 (2023): 3990. http://dx.doi.org/10.3390/en16103990.

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Nuclear power plants (NPPs) produce large amounts of spent fuel while generating electricity. After the spent fuel is taken out of the reactor core, it still has a high decay heat and needs to be cooled for years or even decades before it can be reprocessed or buried deeply. Due to the long storage period of spent fuel, storage safety evaluation is a concern. In this regard, cooling systems are critical for the safe storage of spent fuel. Here, the research progress of cooling methods for spent fuel pools (SFPs) is reviewed, and the structural characteristics, application limitations and heat

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40

Kostiushko, Ya, O. Dudka, Yu Kovbasenko, and A. Shepitchak. "Approaches to Safety Justification for Loading of VSC-VVER Containers in ZNPP DSFSF." Nuclear and Radiation Safety, no. 4(84) (December 19, 2019): 82–87. http://dx.doi.org/10.32918/nrs.2019.4(84).10.

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The introduction of new fuel for nuclear power plants in Ukraine is related to obtaining a relevant license from the regulatory authority for nuclear and radiation safety of Ukraine. The same approach is used for spent nuclear fuel (SNF) management system. The dry spent fuel storage facility (DSFSF) is the first nuclear facility created for intermediate dry storage of SNF in Ukraine. According to the design based on dry ventilated container storage technology by Sierra Nuclear Corporation and Duke Engineering and Services, ventilated storage containers (VSC-VVER) filled with SNF of VVER-1000 a

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Brinton, Samuel, and Mujid Kazimi. "A nuclear fuel cycle system dynamic model for spent fuel storage options." Energy Conversion and Management 74 (October 2013): 558–61. http://dx.doi.org/10.1016/j.enconman.2013.03.041.

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Hakobyan, David A., and Victor I. Slobodchuk. "Temperature conditions in the RBMK spent fuel pool in the event of disturbances in its cooling mode." Nuclear Energy and Technology 7, no. 1 (2021): 9–13. http://dx.doi.org/10.3897/nucet.7.64363.

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The problems of reprocessing and long-term storage of spent nuclear fuel (SNF) at nuclear power plants with RBMK reactors have not been fully resolved so far. For this reason, nuclear power plants are forced to search for new options for the disposal of spent fuel, which can provide at least temporary SNF storage. One of the possible solutions to this problem is to switch to compacted SNF storage in reactor spent fuel pools (SFPs). As the number of spent fuel assemblies (SFAs) in SFPs increases, a greater amount of heat is released. In addition, no less important is the fact that a place for e

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Ratiko, Ratiko, Raden Sumarbagiono, Aisyah Aisyah, et al. "Theoretical and Experimental Analysis on Influence of Natural Airflow on Spent Fuel Heat Removal in Dry Cask Storage." Sustainability 14, no. 3 (2022): 1859. http://dx.doi.org/10.3390/su14031859.

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A key issue contributing to the success of NPP technology is the safe handling of radioactive waste, particularly spent nuclear fuel. According to the IAEA safety standard, the spent fuel must be stored in interim wet storage for several years so the radiation and the decay heat of the spent fuel will decrease to the safe limit values, after which the spent fuel can be moved to dry storage. In this study, we performed a theoretical analysis of heat removal by natural convection airflow in spent nuclear fuel dry storage. The temperature difference between the air inside and outside dry storage

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Paunov, Petar, and Ivaylo Naydenov. "Long-Term Radiotoxicity Evaluation of PWR Spent Uranium and MOX Fuel and Highly Active Waste." E3S Web of Conferences 207 (2020): 01024. http://dx.doi.org/10.1051/e3sconf/202020701024.

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One of the main concerns related to nuclear power production is the generation and accumulation of spent nuclear fuel. Currently most of the spent fuel is stored in interim storage facilities awaiting final disposal or reprocessing. The spent fuel is stored in isolation from the environment in protected facilities or specially designed containers. Nevertheless, spent fuel and highly active waste might get in the environment in case the protective barriers are compromised. In such a case, spent fuel may pose risk to the environment and human health. Those risks depend on the concentration of th

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Bautista-Valhondo, Joaquín, Lluís Batet, and Manuel Mateo. "Minimizing the Standard Deviation of the Thermal Load in the Spent Nuclear Fuel Cask Loading Problem." Energies 13, no. 18 (2020): 4869. http://dx.doi.org/10.3390/en13184869.

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The paper assumes that, at the end of the operational period of a Spanish nuclear power plant, an Independent Spent Fuel Storage Installation will be used for long-term storage. Spent fuel assemblies are selected and transferred to casks for dry storage, with a series of imposed restrictions (e.g., limiting the thermal load). In this context, we present a variant of the problem of spent nuclear fuel cask loading in one stage (i.e., the fuel is completely transferred from the spent fuel pool to the casks at once), offering a multi-start metaheuristic of three phases. (1) A mixed integer linear

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Balan, O. V., S. A. Paskevych, S. S. Pidberezniyy, and D. V. Fedorchenko. "Simulation of the radiation environment during spent nuclear fuel management." Nuclear Physics and Atomic Energy 22, no. 3 (2021): 249–58. http://dx.doi.org/10.15407/jnpae2021.03.249.

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We have developed a model of the technological process for handling spent nuclear fuel in the reception building of the Centralized Storage Facility for Spent Nuclear Fuel using the ChNPP VRdose Planner Pro v. 2.2DEV-0. The results of the technological process simulation proved the reliability of the virtual models for scenarios of radiation-hazardous work for the optimization of the dose loads of personnel.

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Alyokhina, Svitlana, and Andrii Kostikov. "Unsteady heat exchange at the dry spent nuclear fuel storage." Nuclear Engineering and Technology 49, no. 7 (2017): 1457–62. http://dx.doi.org/10.1016/j.net.2017.07.029.

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Nagano, Koji. "An assessment of spent nuclear fuel storage demands under uncertainty." Nuclear Engineering and Design 238, no. 5 (2008): 1175–80. http://dx.doi.org/10.1016/j.nucengdes.2007.03.030.

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Huang, Frank H., and Francis W. Moore. "Dose-Reduction Improvements in Storage Basins of Spent Nuclear Fuel." Nuclear Technology 124, no. 2 (1998): 138–46. http://dx.doi.org/10.13182/nt98-a2914.

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Björkbacka, Åsa, Saman Hosseinpour, Magnus Johnson, Christofer Leygraf, and Mats Jonsson. "Radiation induced corrosion of copper for spent nuclear fuel storage." Radiation Physics and Chemistry 92 (November 2013): 80–86. http://dx.doi.org/10.1016/j.radphyschem.2013.06.033.

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