Статті в журналах: "Storage of spent nuclear fuel"

1

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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2

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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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

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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5

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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6

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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7

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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8

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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9

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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10

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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11

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 spent fuel in dry storage by mid-century when the last plants in the current reactor fleet are decommissioned. Current designs for storage systems rely on large dual-purpose (storage and transportation) canisters that are not optimized for disposal. Various options exist in the US for improving integration of management practices across the entire back end of the nuclear fuel cycle.

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12

Rejková, Jana, Jan Macák, and Lumír Nachmilner. "The Waste Disposal Package for Spent Nuclear Fuel." Chemické listy 116, no. 2 (February 15, 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 during storage.

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13

Sapon, M., O. Gorbachenko, S. Kondratyev, V. Krytskyy, V. Mayatsky, V. Medvedev, and S. Smyshlyaeva. "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 design solutions, manufacturing quality are analyzed in this work. The requirements of Ukrainian and U.S. regulatory documents also are considered. The implementation of these requirements is considered on the example of handling equipment, in particular, spent nuclear fuel storage facilities. This issue is important in view of creation of new SNF storage facilities in Ukraine. These facilities include the storage facility (SFSF) for SNF from water moderated power reactors (WWER): a Сentralized SFSF for storing SNF of Rivne, Khmelnitsky and South-Ukraine Nuclear Power Plants (СSFSF), and SFSF for SNF from high-power channel reactors (RBMK): a dry type SFSF at Chornobyl nuclear power plant (ISF-2). After commissioning of these storage facilities, all spent nuclear fuel from Ukrainian nuclear power plants will be placed for long-term “dry” storage. The safety of handling operations with SNF during its preparation for long-term storage is an important factor.

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14

Saegusa, T., K. Shirai, T. Arai, J. Tani, H. Takeda, M. Wataru, A. Sasahara, and P. L. Winston. "REVIEW AND FUTURE ISSUES ON SPENT NUCLEAR FUEL STORAGE." Nuclear Engineering and Technology 42, no. 3 (June 30, 2010): 237–48. http://dx.doi.org/10.5516/net.2010.42.3.237.

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15

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

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16

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 (May 13, 2007): 549–54. http://dx.doi.org/10.1093/rpd/ncm111.

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17

Aisyah, Aisyah, Mirawaty Mirawaty, Dwi Luhur Ibnu Saputra, Risdiyana Setiawan, Pungky Ayu Artian, Ratiko Ratiko, and Nasruddin Nasruddin. "Effects of %FIMA on Storage-Safety Parameters of Spent Fuel from Experimental Pebble-Bed Reactor." Sains Malaysiana 50, no. 2 (February 28, 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 the initial metallic atoms (%FIMA). These parameters that must be studied include the radioactivity, decay heat, proliferation threats of both 239Pu and 235U, and the presence of 137Cs, a dangerous fission product that can escape from damaged spent fuels. The calculation was conducted by ORIGEN 2.1. The result of the study demonstrates a higher %FIMA indicates a higher safety level that is required since the activity and decay heat of the spent fuel will increase and, as will be the total amounts of 239Pu and 137Cs. However, the 235U amount will decrease. For a 100 years storage of spent fuel, the optimum %FIMA is 8.2 with a canister capacity of 1,900 pebbles. Further, the activity and decay heat of the spent nuclear fuel are 2.013 × 1013 Bq and 6.065 W, respectively. The activities of 239Pu, 137Cs, and 235U are 5.187 ×1011, 7.100 × 1012, and 7.339 × 107 Bq, respectively.

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18

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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19

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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20

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 mode. The paper presents calculation results and analysis on the selection of the most conservative conditions of neutron multiplication leading to the maximum value of Keff.

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21

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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22

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 Next Generation Safeguards Initiative Spent Fuel Libraries, representative for Westinghouse 17ˣ17 PWR assemblies. The ORIGEN-S code then calculates the spontaneous fission and (α,n) emissions for individual fuel rods, followed by detailed MCNP simulations of neutrons transported through the fuel assemblies. A comprehensive database of neutron energy spectral profiles is to be constructed, with different enrichment, burn-up, and cooling time conditions. The end goal is to utilize the computational spent fuel library, predictive algorithm, and a pressurized 4He scintillator to verify the spent fuel assemblies inside a cask. This work identifies neutron spectral signatures that correlate with the cooling time of spent fuel. Both the total and relative contributions from spontaneous fission and (α,n) change noticeably with respect to cooling time, due to the relatively short half-life (18 years) of the major neutron source 244Cm. Identification of this and other neutron spectral signatures allows the characterization of spent nuclear fuels in dry cask storage.

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23

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 multi-stage methodology proposed by the authors. Thus, mutual thermal influence of the containers and boundary conditions at the inlets to the ventilation duct of each storage container should be identified. Thermal processes in the container group where spent nuclear fuel is stored that are described in this paper are analyzed by solving the conjugate heat transfer problems. A row of containers under wind influence is simulated and the structure of ventilation airflow inside the containers is identified. The mutual thermal influence of the containers is absent under calm conditions, and heated air does not come from one container to another. Resulting from the simulation, boundary conditions at the inlet of the ventilation duct are specified and can be used in the iterative modelling methodology for spent fuel thermal condition. The dependence of the velocity of the inlet ventilation air in the ventilation duct of each container in the row was defined. The container placement methodology with the purpose of decreasing the wind influence on the thermal condition of spent fuel storage was proposed. Thermal studies are carried out for the containers and storage conditions of the dry spent nuclear storage facility at Zaporizhzhya NPP.

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24

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, the validation of the created computational models could not be accomplished. However, according to the verification scheme of the COBRA-SFS authors, the verification of the new models was implemented.

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25

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 open WWER-440 fuel assemblies and examine fuel elements. Optimal ways of spent fuel disposal and monitoring of nuclear fuel condition were designed. With appropriate approach of conservativeness, new factor for specifying spent fuel leak tightness is introduced in the paper. By using computer simulations (based on SCALE 4.4a code) for fission products creation and measurements by system “Sipping in pool,” the limit values of leak tightness were established.

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26

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 bundles at the interim storage together with a core of 92 LEU fuel bundles meets the requirements of radiation safety. The results indicate that in the most severe case, i.e., the complete loss of water in the reactor tank, the operators still can access the reactor hall to mitigate the accident within a limited time. Particularly, in the control room, the dose rate of about 1.4 μ Sv / h is small enough for people to work normally.

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27

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

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28

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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29

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

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30

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

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31

Munro, Kirstin, and George Tolley. "Property values and tax rates near spent nuclear fuel storage." Energy Policy 123 (December 2018): 433–42. http://dx.doi.org/10.1016/j.enpol.2018.08.035.

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32

Al Saadi, Sara, and Yongsun Yi. "Dry storage of spent nuclear fuel in UAE – Economic aspect." Annals of Nuclear Energy 75 (January 2015): 527–35. http://dx.doi.org/10.1016/j.anucene.2014.09.003.

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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. The results are presented for burnups of 30 to 49 GWd/MTHM and different cooling times up to 100 years. According to these results, total activity of a spent fuel assembly with initial enrichment of 3.92%, burnup of 49 GWd/MTHM, and cooling time of 3 years is 1.92 × 1016 Bq. The results can be utilized specifically in transportation/storage cask design for spent fuel management of Bushehr nuclear power plant.

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34

SAEGUSA, Toshiari, Chihiro ITO, Kohji NAGANO, Satoshi FUKUDA, and Kenji YAMAJI. "Trend of Dry Storage Technology of Spent Fuel." Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan 37, no. 8 (1995): 675–80. http://dx.doi.org/10.3327/jaesj.37.675.

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35

Lin, Y. J., C. H. Chen, C. W. Yang, and C. H. Chen. "The storage container for demonstrate BWR spent nuclear fuel dry storage in Taiwan." Journal of Physics: Conference Series 2020, no. 1 (September 1, 2021): 012010. http://dx.doi.org/10.1088/1742-6596/2020/1/012010.

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36

Konarski, Piotr, Cédric Cozzo, Grigori Khvostov, and Hakim Ferroukhi. "Spent nuclear fuel in dry storage conditions – current trends in fuel performance modeling." Journal of Nuclear Materials 555 (November 2021): 153138. http://dx.doi.org/10.1016/j.jnucmat.2021.153138.

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37

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 (September 25, 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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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 (February 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 ensure sustainability of energy source. The current operating nuclear power plants in the world use the concept of water-cooled reactors. It was designed so that the fast neutrons born from fission reactions were slowed down in the moderator to allow other fission reactions events in sustainable chain reactions. Besides, the slow neutrons with low energy is a favourable reactor feature for safe and efficient operation. The common types of nuclear fuel materials in water-cooled reactors are enriched uranium dioxide and natural uranium contained in nuclear fuel elements. After it has been used, the fuel elements will be stored as spent fuel. Prolonged storage of used nuclear fuels will make the volume of nuclear waste high and become hard to manage after a long period of storage. An effort to reprocess the spent fuel as to extract fissile and fertile material to be used in nuclear fuels usually was undertaken to reduce the waste volume. However, this process may lead to an undesirable proliferation of nuclear material. In this review article, research on the advancement of nuclear fuel materials will be discussed based on the reduction method of the nuclear spent fuel volume and radiotoxicity, as well as to study its sustainability for the future low carbon energy system.

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39

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 (September 17, 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 programming (MILP-1) model is used to minimize the cost of the casks required. (2) A deterministic algorithm (A1) assigns the spent fuel assemblies to a specific region of a specific cask based on an MILP-1 solution. (3) Starting from the A1 solutions, a local search algorithm (A2) minimizes the standard deviation of the thermal load among casks. Instances with 1200 fuel assemblies (and six intervals for the decay heat) are optimally solved by MILP-1 plus A1 in less than one second. Additionally, A2 gets a Pearson’s coefficient of variation lower than 0.75% in less than 260s CPU (1000 iterations).

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40

Wiss, Thierry, Oliver Dieste, Emanuele De Bona, Alessandro Benedetti, Vincenzo Rondinella, and Rudy Konings. "SUPERFACT: A Model Fuel for Studying the Evolution of the Microstructure of Spent Nuclear Fuel during Storage/Disposal." Materials 14, no. 21 (October 30, 2021): 6538. http://dx.doi.org/10.3390/ma14216538.

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The transmutation of minor actinides (in particular, Np and Am), which are among the main contributors to spent fuel α-radiotoxicity, was studied in the SUPERFACT irradiation. Several types of transmutation UO2-based fuels were produced, differing by their minor actinide content (241Am, 237Np, Pu), and irradiated in the Phénix fast reactor. Due to the high content in rather short-lived alpha-decaying actinides, both the archive, but also the irradiated fuels, cumulated an alpha dose during a laboratory time scale, which is comparable to that of standard LWR fuels during centuries/millenaries of storage. Transmission Electron Microscopy was performed to assess the evolution of the microstructure of the SUPERFACT archive and irradiated fuel. This was compared to conventional irradiated spent fuel (i.e., after years of storage) and to other 238Pu-doped UO2 for which the equivalent storage time would span over centuries. It could be shown that the microstructure of these fluorites does not degrade significantly from low to very high alpha-damage doses, and that helium bubbles precipitate.

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41

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 (March 24, 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 emergency FA discharging should be provided in SFPs. The paper presents the results of a numerical simulation of the temperature conditions in SFPs both for compacted SNF storage and for emergency FA discharging. Several types of disturbances in normal SFP cooling mode are considered, including partial loss of cooling water and exposure of SFAs. The simulation was performed using the ANSYS CFX software tool. Estimates were made of the time for heating water to the boiling point, as well as the time for heating the cladding of the fuel elements to a temperature of 650 °С. The most critical conditions are observed in the emergency FA discharging compartment. The results obtained make it possible to estimate the time that the personnel have to restore normal cooling mode of the spent fuel pool until the maximum temperature for water and spent fuel assemblies is reached.

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42

Ratiko, Ratiko, Raden Sumarbagiono, Aisyah Aisyah, Wati Wati, Kuat Heriyanto, Mirawaty Mirawaty, Pungky Ayu Artiani, et al. "Theoretical and Experimental Analysis on Influence of Natural Airflow on Spent Fuel Heat Removal in Dry Cask Storage." Sustainability 14, no. 3 (February 6, 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 produces an air density difference. The air density difference causes a pressure difference, which then generates natural airflow. The result of the theoretical analysis was validated with simulation software and experimental investigation using a reduced-scale dry storage prototype. The dry storage prototype consisted of a dry cask body and two canisters stacked to store materials testing reactor (MTR) spent fuel, which generates decay heat. The cask body had four air inlet vents on the bottom and four air outlet vents at the top. To simulate the decay heat from the spent fuel in the two canisters, the canisters were wrapped with an electric wire heater that was connected to a voltage regulator to adjust the heat power. The theoretical analysis results of this study are relatively consistent with the experimental results, with the mean relative deviation (MRD) values for the prediction of air velocity, the heat rate using natural airflow, and the heat rate using the thermal resistance network equation are +0.76, −23.69, and −29.54%, respectively.

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43

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 are used, which are located on a special open concrete site. Containers VSC-VVER are modernized VSC-24 containers customized for hexagonal VVER-1000 spent fuel assemblies. The storage safety assessment methodology was created and improved directly during the licensing process. In addition, in accordance with the Energy Strategy of Ukraine up to 2035, one of the key task is the further diversification of nuclear fuel suppliers. Within the framework of the Executive Agreement between the Government of Ukraine and the U.S. Government, activities have been underway since 2000 on the introduction of Westinghouse fuel. The purpose of this project is to develop, supply and qualify alternative nuclear fuel compatible with fuel produced in Russia for Ukrainian NPPs. In addition, a supplementary approach to safety analysis report is being developed to justify feasibility of loading new fuel into the DSFSF containers. The stated results should demonstrate the fulfillment of design criteria under normal operating conditions, abnormal conditions and design-basis accidents of DSFSF components. Thus, the paper highlights both the main problems of DSFSF licensing and obtaining permission for placing new fuel types in DSFSF.

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44

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 the given radionuclide and are measured by the value of potential danger. The potential danger is called also ’radiotoxicity’. The paper examines spent uranium and MOX fuels from a reference PWR, as well as the highly radioactive wastes of their reprocessing. The radiotoxicity of the four materials is examined and evaluated for a cooling time of 1000 years. The contribution of different radionuclides is assessed and the cases of reprocessing and no reprocessing of spent fuel have been compared.

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45

Patrick, Wesley. "Operational and Technical Results from the Spent Fuel Test-Climax." Journal of the IEST 29, no. 1 (January 1, 1986): 51–54. http://dx.doi.org/10.17764/jiet.1.29.1.ym7936wh48m6m800.

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The technical feasibility of short-term storage and retrieval of spent nuclear fuel assemblies has recently been demonstrated in a test of deep geologic storage at the U.S. Department of Energy Nevada Test Site (NTS). Handling systems and procedures developed and deployed on this test functioned safely and reliably to emplace eleven intact spent-fuel assemblies and retrieve them three years later. Three exchanges of spent fuel were conducted at regular intervals during the storage period to maintain the proficiency of personnel and the readiness of the handling system. Technical data was collected using nearly 1,000 instruments. These data show that the mechanical and thermal properties of granites are compatible with nuclear waste isolation objectives. Measured and calculated temperatures are in excellent agreement, confirming the adequacy of available heat transfer codes. Radiation transport calculations were of high quality, exceeding the accuracy of available long-term dosimetry techniques which were used on the test. We also found good agreement between measured and calculated displacements within the rock mass.

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46

Lee, Sanghoon, and Daesik Yook. "Review of Spent Nuclear Fuel Dry Storage Demonstration Programs in US." Journal of the Nuclear Fuel Cycle and Waste Technology(JNFCWT) 15, no. 2 (June 30, 2017): 135–49. http://dx.doi.org/10.7733/jnfcwt.2017.15.2.135.

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47

Hackel, Lloyd, Jon Rankin, Matt Walter, C. Brent Dane, William Neuman, Pierre Oneid, Gareth Thomas, and Fred Bidrawn. "Preventing Stress Corrosion Cracking of Spent Nuclear Fuel Dry Storage Canisters." Procedia Structural Integrity 19 (2019): 346–61. http://dx.doi.org/10.1016/j.prostr.2019.12.038.

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48

Huajian, Chang, Dong Duo, and Xu Yong. "Spent fuel storage in pressure vessel for a nuclear heating reactor." Nuclear Engineering and Design 172, no. 1-2 (July 1997): 13–16. http://dx.doi.org/10.1016/s0029-5493(97)00029-0.

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49

Králı́k, Miloslav, Vladimı́r Kulich, and Jiřı́ Studený. "Neutron spectrometry at the interim storage facility for spent nuclear fuel." Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment 476, no. 1-2 (January 2002): 423–28. http://dx.doi.org/10.1016/s0168-9002(01)01482-6.

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50

Raynaud, Patrick A. C., and Robert E. Einziger. "Cladding stress during extended storage of high burnup spent nuclear fuel." Journal of Nuclear Materials 464 (September 2015): 304–12. http://dx.doi.org/10.1016/j.jnucmat.2015.05.008.

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