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Academic literature on the topic 'Uranium cycle'

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Published: 25 May 2024

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Journal articles on the topic "Uranium cycle"

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Costa Peluzo, Bárbara Maria Teixeira, and Elfi Kraka. "Uranium: The Nuclear Fuel Cycle and Beyond." International Journal of Molecular Sciences 23, no. 9 (April 22, 2022): 4655. http://dx.doi.org/10.3390/ijms23094655.

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This review summarizes the recent developments regarding the use of uranium as nuclear fuel, including recycling and health aspects, elucidated from a chemical point of view, i.e., emphasizing the rich uranium coordination chemistry, which has also raised interest in using uranium compounds in synthesis and catalysis. A number of novel uranium coordination features are addressed, such the emerging number of U(II) complexes and uranium nitride complexes as a promising class of materials for more efficient and safer nuclear fuels. The current discussion about uranium triple bonds is addressed by quantum chemical investigations using local vibrational mode force constants as quantitative bond strength descriptors based on vibrational spectroscopy. The local mode analysis of selected uranium nitrides, N≡U≡N, U≡N, N≡U=NH and N≡U=O, could confirm and quantify, for the first time, that these molecules exhibit a UN triple bond as hypothesized in the literature. We hope that this review will inspire the community interested in uranium chemistry and will serve as an incubator for fruitful collaborations between theory and experimentation in exploring the wealth of uranium chemistry.
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Andersen, Morten B., Tim Elliott, Heye Freymuth, Kenneth W. W. Sims, Yaoling Niu, and Katherine A. Kelley. "The terrestrial uranium isotope cycle." Nature 517, no. 7534 (January 2015): 356–59. http://dx.doi.org/10.1038/nature14062.

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Korobeinikov, Valery V., Valery V. Kolesov, and Aleksandr V. Mikhalev. "Comparison of the minor actinide transmutation efficiency in models of a fast neutron uranium-thorium fueled reactor." Nuclear Energy and Technology 8, no. 1 (March 18, 2022): 49–53. http://dx.doi.org/10.3897/nucet.8.82757.

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In terms of nuclear raw materials, the issue of involving thorium in the fuel cycle is hardly very relevant. However, in view of the large-scale nuclear power development, the use of thorium seems to be quite natural and reasonable. The substitution of traditional uranium-plutonium fuel for uranium-thorium fuel in fast neutron reactors will significantly reduce the production of minor actinides, which will make it attractive for the transmutation of long-lived radioactive isotopes of americium, curium and neptunium that have already been and are still being accumulated. Due to the absence of uranium-233 in nature, the use of thorium in the nuclear power industry requires a closed fuel cycle. At the initial stage of developing the uranium-thorium cycle, it is proposed to use uranium-235 instead of uranium-233 as nuclear fuel. Studies have been carried out on the transmutation of minor actinides in a fast neutron reactor in which the uranium-thorium cycle is implemented. Several options for the structure of the core of such a reactor have been considered. It has been shown that heterogeneous placement of americium leads to higher rates of its transmutation than homogeneous placement does.
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Yang, Kun. "Study of Uranium and Thorium Fuels in Breed-and-Burn Mode." Frontiers in Science and Engineering 3, no. 10 (October 23, 2023): 14–22. http://dx.doi.org/10.54691/fse.v3i10.5663.

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The formation of fissile nuclei through breeding conversion is a hot topic in academic research, as it provides a continuous source of nuclear fuel for nuclear reactors. Fast neutron reactors, which have been extensively studied, use natural uranium or low-enriched uranium as the nuclear fuel, achieving burning after uranium-plutonium conversion. Thorium, as another potential fissile fuel, can theoretically be converted into nuclear reactor fuel through the thorium-uranium cycle. In this study, the physical evolution process of nuclear fuel in a specific core parameter is simulated using the Monte Carlo program, and the performance differences of the thorium-uranium cycle and uranium-plutonium cycle in achieving in situ breeding-burning (Breed-and-Burn, B&B) mode are analyzed using neutron balance analysis method. The optimal ratio conditions for achieving self-sustained B&B burning in a thorium-uranium fuel mixed core are investigated. The study shows that for traditional solid-state nuclear reactor cores with a lower fuel proportion, thorium-breeding fuel has poor neutron economy compared to uranium-based breeding fuel, making it more difficult to achieve the B&B mode.
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Kovalev, Nikita V., Boris Ya Zilberman, Nikolay D. Goletsky, and Andrey B. Sinyukhin. "A new approach to the recycling of spent nuclear fuel in thermal reactors within the REMIX concept." Nuclear Energy and Technology 6, no. 2 (June 19, 2020): 93–98. http://dx.doi.org/10.3897/nucet.6.54624.

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A review of simulated nuclear fuel cycles with mixed uranium-plutonium fuel (REMIX) was carried out. The concept of REMIX fuel is one of the options for closing the nuclear fuel cycle (NFC), which makes it possible to recycle uranium and plutonium in VVER-1000/1200 thermal reactors at a 100% core loading. The authors propose a new approach to the recycling of spent nuclear fuel (SNF) in thermal reactors. The approach implies a simplified fabrication of mixed fuel when plutonium is used in high concentration together with enriched natural uranium, while reprocessed uranium is supposed to be enriched and used separately. The share of standard enriched natural uranium fuel in this nuclear fuel cycle is more than 50%, the share of mixed natU+Pu fuel is 25%, the rest is fuel obtained from enriched reprocessed uranium. It is emphasized that the new approach has the maximum economic prospect and makes it possible to organize the fabrication of this fuel and nuclear material cross-cycling at the facilities available in the Russian Federation in the short term. This NFC option eliminates the accumulation of SNF in the form of spent fuel assemblies (SFA). SNF is always reprocessed with the aim of further using the primary reprocessed uranium and plutonium. Non-recyclable in thermal reactors, burnt, reprocessed uranium, the energy potential of which is comparable to natural uranium, as well as secondary plutonium intended for further use in fast reactors, are sent as reprocessing by-products to the storage area.
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Moiseenko, V., and S. Chernitskiy. "Nuclear Fuel Cycle with Minimized Waste." Nuclear and Radiation Safety, no. 1(81) (March 12, 2019): 30–35. http://dx.doi.org/10.32918/nrs.2019.1(81).05.

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A uranium-based nuclear fuel and fuel cycle are proposed for energy production. The fuel composition is chosen so that during reactor operation the amount of each transuranic component remains unchanged since the production rate and nuclear reaction rate are balanced. In such a ‘balanced’ fuel only uranium-238 content has a tendency to decrease and, to be kept constant, must be sustained by continuous supply. The major fissionable component of the fuel is plutonium is chosen. This makes it possible to abandon the use of uranium-235, whose reserves are quickly exhausted. The spent nuclear fuel of such a reactor should be reprocessed and used again after separation of fission products and adding depleted uranium. This feature simplifies maintaining the closed nuclear fuel cycle and provides its periodicity. In the fuel balance calculations, nine isotopes of uranium, neptunium, plutonium and americium are used. This number of elements is not complete, but is quite sufficient for calculations which are used for conceptual analysis. For more detailed consideration, this set may be substantially expanded. The variation of the fuel composition depending on the reactor size is not too big. The model accounts for fission, neutron capture and decays. Using MCNPX numerical Monte-Carlo code, the neutron calculations are performed for the reactor of industrial nuclear power plant size with MOX fuel and for a small reactor with metallic fuel. The calculation results indicate that it is possible to achieve criticality of the reactor in both cases and that production and consuming rates are balanced for the transuranic fuel components. In this way, it can be assumed that transuranic elements will constantly return to such a reactor, and only fission products will be sent to storage. This will significantly reduce the radioactivity of spent nuclear fuel. It is important that the storage time for the fission products is much less than for the spent nuclear fuel, just about 300 years.
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Asiah A, Nur, Merry Yanti, Zaki Su’ud, Menik A., and H. Sekimoto. "Preliminary design study of Long-life Gas Cooled Fast Reactor With Modified CANDLE Burnup Scheme." Indonesian Journal of Physics 20, no. 4 (November 3, 2016): 85–88. http://dx.doi.org/10.5614/itb.ijp.2009.20.4.3.

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In this paper, preliminary design study of Gas Cooled Fas Reactors with Natural Uranium as Fuel Cycle Input has been performed. Gas Cooled Fast Reactor is slightly modified by employing modified CANDLE burnup scheme so that it can use Natural Uranium as fuel cycle input. The natural uranium is initially put in region 1, after one cycle of 10 years of burn-up it is shifted to region 2 and the region 1 is filled by fresh natural uranium fuel. This concept is basically applied to all regions. In this case the system has been applied to many power level which results relatively flexible discharge burn-up level up from about 20%HM to 30 %HM.
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Lapin, A., A. Bobryashov, V. Blandinsky, and E. Bobrov. "ASSESSMENT OF THE SYSTEM CHARACTERISTICS OF A REACTOR WITH SUPERCRITICAL COOLANT PARAMETERS FOR VARIOUS FUEL CYCLES." PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY. SERIES: NUCLEAR AND REACTOR CONSTANTS 2020, no. 3 (September 26, 2020): 51–62. http://dx.doi.org/10.55176/2414-1038-2020-3-51-62.

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Nowadays nuclear energy operates in an open fuel cycle. One of the most important directions in the development of nuclear energy is the closure of the nuclear fuel cycle. The solution to this problem is possible with the use of fast neutron reactors. To achieve this goal, the possibility of using a reactor with a fast-resonance neutron spectrum cooled by supercritical water (SCWR) was considered. The SCWR reactor can be effectively used in a closed nuclear fuel cycle, since it makes it possible to use spent fuel and dump uranium with a small amount of plutonium added. The layout options of the core with a change in the size of the core and reproduction zones are considered. The possibility of placing reproduction zones from various materials inside the active zone was evaluated. Based on the studies, an acceptable version of the core is selected in terms of system characteristics. For the considered arrangement of the reactor core, the possibility of shorting the uranium-plutonium and uranium-thorium fuel cycles has been investigated. The system characteristics of the reactor installation were studied for the following fuel load options: 1. Loading MOX fuel into the core, depleted uranium in the lateral zone of reproduction. 2. Loading of uranium-thorium fuel into the core and side screens. The results of the assessments of the system characteristics of the reactor are considered in the article.
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Chen, Aimei, Xiaobei Zheng, Chunxia Liu, Yuxia Liu, and Lan Zhang. "Uranium thermochemical cycle: hydrogen production demonstration." Energy Sources, Part A: Recovery, Utilization, and Environmental Effects 40, no. 21 (August 1, 2018): 2542–49. http://dx.doi.org/10.1080/15567036.2018.1504141.

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Wei, Chunlin, Xiuan Shi, Yongwei Yang, and Zhiwei Zhou. "ICONE19-43519 Preliminary Research on Thorium-Uranium Fuel Cycle Characteristic in PWR." Proceedings of the International Conference on Nuclear Engineering (ICONE) 2011.19 (2011): _ICONE1943. http://dx.doi.org/10.1299/jsmeicone.2011.19._icone1943_209.

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Dissertations / Theses on the topic "Uranium cycle"

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Lambert, Janine. "A Life Cycle Assessment of a Uranium Mine in Namibia." Scholar Commons, 2016. http://scholarcommons.usf.edu/etd/6291.

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Uranium mining and nuclear power is a controversial topic as of late, especially in light of the recent Fukushima event. Although the actual use of nuclear fuel has minimal environmental impact, its issues come at the very beginning and end of the fuel’s life cycle in both the mining and fuel disposal process. This paper focuses on a life cycle analysis (LCA) of uranium mine in the desert nation of Namibia in Southern Africa. The goal of this LCA is to evaluate the environmental effects of uranium mining. The LCA focuses on water and energy embodiment such that they can then be compared to other mines. The functional unit of the analysis is 1kg of yellowcake (uranium oxide). The processes considered include mining and milling at Langer Heinrich Uranium (LHU). The impact categories evaluated include the categories in ReCiPe assessment method with a focus of water depletion, and cumulative energy demand. It was found that the major environmental impacts are marine ecotoxicity, human toxicity, freshwater eutrophication, and freshwater ecotoxicity. These mainly came from electricity consumption in the mining and milling process, especially electricity generated from hard coal. Milling tailings was also a contributor, especially for marine ecotoxicity and human toxicity. The other electricity generation types, including nuclear, hydro, natural gas, and diesel contribute to marine exotoxicity and human toxicity as well. Hydro-electricity, tailings form milling, sodium carbonate, and nuclear electricity also cause freshwater eutrophication at the LHU mine. The major contributor of the water depletion was hard coal generated electricity consumption as well. Tailings also led to a level of water depletion that was significant but much smaller than that of the coal-based electricity. In terms of energy, weighting portrayed the main energy used to be nuclear power, in terms of MJ equivalents. Nuclear power was then followed by fossil fuels and finally hydropower. Most of the energy used was for the uranium mining process rather than the milling process. As expected, the direct water, and energy values, 0.5459 m3 and 97.34 kWh per kg of yellowcake, were much lower than the LCA embodiment values of 282.67 m3 and 76,479 kWh per kg of yellowcake. When compared to other mines, the water use at LHU was found to be much lower while the energy use was found to be much higher.
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KOMATSU, CINTIA N. "Diretrizes para avaliação do gasto ambiental no ciclo do combustivel nuclear." reponame:Repositório Institucional do IPEN, 2008. http://repositorio.ipen.br:8080/xmlui/handle/123456789/11712.

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Made available in DSpace on 2014-10-09T12:55:00Z (GMT). No. of bitstreams: 0
Made available in DSpace on 2014-10-09T14:07:16Z (GMT). No. of bitstreams: 0
Dissertacao (Mestrado)
IPEN/D
Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP
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LIMA, CINTIA MONTEIRO DE. "STUDY OF URANIUM COMPOUNDS SOLUBILITY IN THE NUCLEAR FUEL CYCLE IN LPS." PONTIFÍCIA UNIVERSIDADE CATÓLICA DO RIO DE JANEIRO, 2008. http://www.maxwell.vrac.puc-rio.br/Busca_etds.php?strSecao=resultado&nrSeq=12141@1.

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COORDENAÇÃO DE APERFEIÇOAMENTO DO PESSOAL DE ENSINO SUPERIOR
CONSELHO NACIONAL DE DESENVOLVIMENTO CIENTÍFICO E TECNOLÓGICO
O ciclo do combustível nuclear é o conjunto de etapas do processo industrial que transforma o mineral urânio até sua utilização como combustível nuclear. Em todas as etapas do ciclo os trabalhadores estão expostos a partículas contendo urânio. Para avaliar os riscos é necessário conhecer a taxa de deposição, a concentração e a cinética da partícula no trato respiratório. Os testes de solubilidade in vitro, permitem um estudo sistemático da solubilidade de qualquer composto. Nesse estudo foram utilizadas amostras de DUA, TCAU e UO2 em contato com o liquido pulmonar simulado e estas foram analisadas pela técnica de PIXE (Particle Induced X rays Emission) para determinação da fração de urânio solubilizada e pela técnica de 252 Cf-PDMS (Plasma Desorption Mass Spectrometry) para a determinação da especiação química. Os objetivos específicos foram: (i) Identificar os compostos de urânio na fração respirável do aerossol nas etapas selecionadas do ciclo de combustível nuclear; (ii) identificar e determinar a solubilidade dos compostos de urânio em líquido pulmonar simulado; (iii) Determinar os parâmetros de solubilidade dos compostos de urânio. Os valores dos parâmetros de solubilidade determinados neste estudo para o DUA, TCAU e UO2 são: fr, = 0,83; sr = 0,51 d -1 e ss = 0,0075 d -1 ; fr = 0,60; sr = 0,70 d -1 e ss = 0,00089 d -1 e fr = 0,19; sr = 0,47 d -1 e ss = 0,0019 d -1 , respectivamente.
The nuclear fuel cycle is the industrial process that converts the uranium ore, to its use as fuel, inside of a nuclear power station. In all steps from the nuclear cycle workers are exposure to uranium dust particles. To evaluate the risk due particles incorporation data like deposition, concentration and kinetics of the particles in the respiratory tract must be know The in vitro solubility test allows a systemic understanding about the compound solubility. Samples of DUA, TCAU e UO2 and SLF was collected in different time interval and the uranium concentration was determined by PIXE (Particle Induced X rays Emissions) technique and the uranium compounds were identified by 252 Cf-PDMS (Plasma Desorption Mass Spectrometry). The specific objectives were: (i) identifying uranium compounds in the respirable fractions of aerosol (ii) identified and determinated the uranium coumpounds solubility in simulated lung fluid (iii) determinated the solubility parameters to this uranium compounds. The solubility parameters to DUA, TCAU and UO2 are: fr, = 0,83; sr = 0,51 d -1 and ss = 0,0075 d -1; fr = 0,60; sr = 0,70 d -1 and ss = 0,00089 d -1 e fr = 0,19; sr = 0,47 d -1 e ss = 0,0019 d -1, respectively.
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Wade, Roy Jr. "A genetic system for studying uranium reduction by Shewanella putrefaciens." Diss., Georgia Institute of Technology, 2002. http://hdl.handle.net/1853/25304.

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Wang, Dean 1971. "Optimization of a seed and blanket thorium-uranium fuel cycle for pressurized water reactors." Thesis, Massachusetts Institute of Technology, 2003. http://hdl.handle.net/1721.1/29956.

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Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 2003.
Includes bibliographical references (p. 189-194).
A heterogeneous LWR core design, which employs a thorium/uranium once through fuel cycle, is optimized for good economics, wide safety margins, minimal waste burden and high proliferation resistance. The focus is on the Whole Assembly Seed and Blanket (WASB) concept, in which the individual seed and blanket regions each occupy one full-size PWR assembly in a checkerboard core configuration. A Westinghouse 4-loop 1150 MWe PWR was selected as the reference plant design. The optimized heterogeneous core, after several iterations, employs 84 seed assemblies and 109 blanket assemblies. Each assembly has the characteristic 17x17 rod array. The seed fuel is composed of 20 w/o enriched annular UO2 pellets. Erbium is used in the fresh seed to help regulate local power peaking and reduce soluble boron concentrations. Erbium was evenly distributed into all pin central holes except for the peripheral pins and four corner pins of each assembly where more erbium was used due to their higher power level. The blanket fuel is a mixture of 87% ThO2 - 13% UO2 by volume, where the uranium is enriched to 10 w/o. The blanket fuel pin diameter is larger than the seed fuel pin diameter. There are two separate fuel management flows: a standard three-batch scheme is adopted for the seed (18 month cycle length) and a single-batch for the blanket, which is to stay in the core for up to 9 seed cycles. The WASB core design was analyzed by well known tools in the nuclear industry. The neutronic analysis was performed using the Studsvik Core Management System (CMS), which consists of three codes: CASMO-4, TABLES-3 and SIMULATE-3. Thermal-hydraulic analysis was performed using EPRI's VIPRE-01.
(cont.) Fuel performance was analyzed using FRAPCON. The radioactivity and decay heat from the spent seed and blanket fuel were studied using MIT's MCODE (which couples MCNP and ORIGEN) to do depletion calculations, and ORIGEN to analyze the spent fuel characteristics after discharge. The analyses show that the WASB core can satisfy the requirements of fuel cycle length and safety margins of conventional PWRs. The coefficients of reactivity are comparable to currently operating PWRs. However, the reduction in effective delayed neutron fraction (eff) requires careful review of the control systems because of its importance to short term power transients. Whole core analyses show that the total control rod worth of the WASB core is about 1/3 less than those of a typical PWR for a standard arrangement of Ag-In-Cd control rods in the core. The use of enriched boron in the control rods can effectively improve the control rod worth. The control rods have higher worth in the seed than in the blanket. Therefore, a new loading pattern has been designed so that almost all the control rods will be located in seed assemblies. However, the new pattern requires a redesign of the vessel head of the reactor, which is an added cost in case of retrofitting in existing PWRs. Though the WASB core has high power peaking factors, acceptable MDNBR in the core can be achieved under conservative assumptions by using grids with large local pressure loss coefficient in the blanket. However, the core pressure drop will increase by 70% ...
by Dean Wang.
Ph.D.
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Richard, Joshua (Joshua Glenn). "A strategy for transition from a uranium fueled, open cycle SFR to a transuranic fueled, closed cycle sodium cooled fast reactor." Thesis, Massachusetts Institute of Technology, 2012. http://hdl.handle.net/1721.1/76972.

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Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2012.
Cataloged from PDF version of thesis.
Includes bibliographical references (p. 110-111).
Reactors utilizing a highly energetic neutron spectrum, often termed fast reactors, offer large fuel utilization improvements over the thermal reactors currently used for nuclear energy generation. Conventional fast reactor deployment has been hindered by the perceived need to use plutonium as fuel, coupling the commercial introduction of fast reactors to the deployment of large-scale thermal reactor used fuel reprocessing. However, the future of used fuel treatment in the United States is highly uncertain, creating a bottleneck for the introduction of fast reactor technology. A strategy centered around using uranium-fueled fast reactor cores in a once-through mode-a uranium startup fast reactor (USFR)-decouples fast reactor commercialization from fuel reprocessing and enables transition to a recycle mode once the technology becomes available and economic. The present work investigates the optimal strategy for recycling spent fuel from once-through sodium cooled fast reactors (SFRs), by analyzing the performance of various designs. A range of acceptable transitions are described and their economic, breeding, nonproliferation, and safety performance are characterized. A key finding is that the burnups of all cores were limited by the allowable fluence to the cladding rather than by the core reactivity. The carbide cores achieve fluence-limited burnups 15-25% greater than the comparable metal cores, though the metal cores can be optimized via decrementing the fuel volume fraction to reach fluence-limited burnups within 10% of the carbide cores. The removal of minor actinides from the recycled fuel has a minimal impact on the achievable burnups of both types of fuels, decreasing the fluence-limited burnup by less than half a percent in all cases. Similarly, long-term storage of the USFR fuel had minimal impact on the achievable burnups of all cores, decreasing the fluencelimited burnup by no more than 2% in all cases. Levelized fuel costs were in the range of 5.98 mills/kWh to 7.27 mills/kWh for the carbide cores, and 6.81 mills/kWh to 7.57 mills/kWh for the optimized metal cores, which is competitive with fuel costs of current LWRs and once-through SFRs. The metal and carbide multicore cores, made using slightly more than one once-through SFR core, functioned as slight fissile burners with fissile inventory ratios (FIRs) near 0.9. The uranium+ cores, made using one oncethrough SFR core plus natural uranium makeup, functioned in a fissile self-sustaining mode with FIRs near unity. All cores discharged fuel that was less attractive for weapon use than that of an LWR. The carbide cores had maximum sodium void worths in the range of $2.81-$2.86, approximately half the worth of the metal cores, which were in the range of $4.97-$5.14. Carbide and metal multicore cores possessed initial reactivities in the range of 15,000 pcm, requiring either multi-batch staggered reloading or control system modifications to achieve acceptable shutdown margins. The uranium+ carbide and metal cores achieved acceptable shutdown margin with the nominal control configuration and the single-batch reloading scheme. The overall conclusion is that USFR spent fuel is readily usable for recycle.
by Joshua Richard.
S.M.
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Lefebvre, Pierre. "Évolution à long terme de la spéciation et de la mobilité de l’uranium dans les sédiments et les sols : processus naturels d'enrichissement en uranium dans le bassin versant du Lac Nègre." Electronic Thesis or Diss., Sorbonne université, 2021. http://www.theses.fr/2021SORUS292.

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La connaissance du comportement géochimique de l’uranium (U) dans l’environnement est essentielle pour en limiter la propagation dans les milieux contaminés. Ce travail de thèse visait avant tout à déterminer l’évolution sur plusieurs milliers d’années des phases non-cristallines de U dans les sédiments naturellement riches en U (jusqu’à plus de 1000 µg/g) du lac Nègre, dans le massif du Mercantour (Alpes-Maritimes, France). Grâce aux rapports isotopiques de U (δ238U et (234U/238U)) et à la spectroscopie d’absorption X (XAS) au seuil L3 de U, il est montré que U est déposé initialement sous forme d’espèces mononucléaires liées à la matière organique, et est rapidement réduit en U(IV). En moins de 700 ans, ces phases sont transformées en polymères de U(IV)-silice avec une structure locale proche de la coffinite (USiO4·nH2O). Cette transformation souligne l’impact de l’abondance de ligands qui limitent la précipitation de phases cristallines de U, mais ne réduit que faiblement la labilité de U, dont la mobilité potentielle reste importante après plus de 3000 ans. A l’échelle du bassin versant, U provient initialement de fractures dans la roche-mère granitique, puis est piégé en grandes quantités dans les sols, en particulier dans la zone humide en amont du lac (jusqu’à > 5000 µg/g U), avant d’être transporté vers le lac par érosion. Cette fixation dans les sols a lieu par complexation sur la matière organique dont certaines structures biologiques, avant réduction partielle en U(IV). On trouve ainsi surtout des formes mononucléaires de U, mais aussi des phases polymériques de U(VI) potentiellement issues d’un vieillissement de U après des milliers d’années d’accumulation
Understanding the geochemical behavior of uranium (U) in the environment is crucial for the limitation of U dissemination in contaminated systems. The primary objective of this thesis was to determine the potential evolution of noncrystalline U phases over thousand years in naturally U-rich lacustrine sediments (up to more than 1000 µg/g) from Lake Nègre, in the Mercantour-Argentera Massif (South-East France). Using U isotopic ratios (δ238U and (234U/238U)) and U L3-edge X-ray absorption spectroscopy (XAS), we show that U is first deposited as organic-bound mononuclear species and is readily reduced to U(IV). In less than 700 years, these species transform into U(IV)-silica polymers with a local structure close to that of coffinite (USiO4·nH2O). This transformation highlights the role of ligand abundance in limiting the precipitation of crystalline U phases, but only slightly reduces the lability of uranium which potential mobility remains significant even after several thousand years. At the watershed scale, U originates from fractures in the granitic bedrock and is subsequently scavenged in the soils, especially in the wetland upstream of the lake (up to > 5000 µg/g), before being transported through erosion. Uranium scavenging in the soils occurs through complexation by organic matter including particular biological structures, followed by partial reduction to U(IV). U is thus mainly present in mononuclear species but also in polymeric U(VI) phases which may potentially result from U aging after thousand years of accumulation
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Eglinger, Aurélien. "Cycle de l'uranium et évolution tectono-métamorphique de la ceinture orogénique Pan-Africaine du Lufilien (Zambie)." Thesis, Université de Lorraine, 2013. http://www.theses.fr/2013LORR0306/document.

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L'uranium, élément lithophile et incompatible, peut être utilisé en traceur géochimique pour discuter des différents modèles de formation et d'évolution de la croûte continentale. Ce travail de thèse, ciblé sur la ceinture Pan-Africaine du Lufilien en Zambie, caractérise le cycle de l'U et les minéralisations d'U pour ce segment de croûte continentale. Les séries silicoclastiques/évaporitiques de la ceinture du Lufilien, encaissant les minéralisations d'U, se sont déposées en contexte de rift (bassin du Roan) lors de la dislocation du supercontinent Rodinia au Néoprotérozoïque inférieur. Les âges U-Pb des grains de zircon détritique de ces séries métasédimentaires soulignent une source principalement Paléoprotérozoïque. Ces mêmes grains de zircon présentent des signatures isotopiques epsilonHf inférieures au CHUR (entre 0 et -15) et des âges modèles TDM Hf, compris entre ~2.9 et 2.5 Ga. Ces données suggèrent donc la formation d'une croûte continentale précoce, et donc une extraction mantellique de l'U dès la fin de l'Archéen puis une remobilisation par déformation et métamorphisme au cours du Protérozoïque. L'U aurait donc été remobilisé et re-concentré au cours d'orogenèses successives jusqu'au cycle Pan-Africain. Durant ce cycle Pan-Africain, la datation U-Pb et la signature REY (REE et Yttrium) des cristaux d'uraninite caractérisent un premier évènement minéralisateur, daté vers 650 Ma, associé à la circulation de fluides de bassin expulsés des évaporites du Roan, circulant à l'interface socle/couverture, dans ce contexte de rift continental. Un second événement minéralisateur, daté vers 530 Ma et contemporain du pic métamorphique, est assuré par des fluides métamorphiques issus de la dissolution des évaporites, en contexte de subduction/accrétion continentale. Quelques remobilisations tardives de l'U sont observées lors de l'exhumation des roches métamorphiques
Uranium is an incompatible and lithophile element and can be used as a geochemical tracer to discuss the generation and the evolution of continental crust. This thesis, focused on the Pan-African Lufilian belt in Zambia, characterizes the U cycle for this crustal segment. Silici-clastic and evaporitic sediments have been deposited within an intracontinental rift during the dislocation of the Rodinia supercontinent during the early Neoproterozoic. U-Pb ages on detrital zircon grains in these units indicate a dominant Paleoproterozoic provenance. The same zircon grains show subchondritic epsilonHf (between 0 and -15) and yield Hf model ages between ~2.9 and 2.5 Ga. These data suggest that the continental crust was generated before the end of the Archean associated with U extraction from the mantle. This old crust has been reworked by deformation and metamorphism during the Proterozoic. U has been remobilized and re-concentrated during several orogenic cycles until the Pan-African orogeny. During this Pan-African cycle, U-Pb and REY (REE and Yttrium) signatures of uranium oxides indicate a first mineralizing event at ca. 650 Ma during the continental rifting. This event is related to late diagenesis hydrothermal processes at the basement/cover interface with the circulation of basinal brines linked to evaporites of the Roan. The second stage, dated at 530 Ma, is connected to metamorphic highly saline fluid circulations, synchronous to the metamorphic peak of the Lufilian orogeny. These fluids are derived from the Roan evaporite dissolution. Some late uranium remobilizations are described during exhumation of metamorphic rocks and their tectonic accretion in the internal zone of the Lufilian orogenic belt
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Louw, Alet. "The environmental regulation of uranium mines in Namibia : a project life cycle analysis / Louw A." Thesis, North-West University, 2012. http://hdl.handle.net/10394/7600.

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Uranium exploration and mining activities in Namibia have increased rapidly since 2003, which increase not only poses a significant impact on the country’s economy, but also on its unique and pristine natural environment. The nature and extent of the environmental impacts associated with uranium mining requires a sound environmental law and policy framework that regulates uranium activities, impacts and aspects during each phase of the project life cycle of a uranium mine. It also requires of authorities to establish and enhance environmental protection and sustainability during uranium mining operations and to ensure that all environmental impacts that inevitably occur as a result of uranium mining activities are addressed in a holistic and integrated manner during each phase of the project life cycle of a uranium mine. In order to do this the country must develop and maintain an efficient and effective environmental governance regime. Namibia’s environmental law and policy framework that regulates uranium mining does not cover the entire PLC of uranium mining. It is vital that the current loops in the country’s existing environmental regulatory framework be closed and that an efficient and effective environmental governance regime, as envisaged in this study, be established. This will enable the administering agents to actively promote and maintain the welfare of the people, ecosystems, essential ecological processes and the biodiversity of Namibia, as well as the utilisation of living natural resources on a sustainable basis to the benefit of all Namibians, both present and future, as pledged in the Namibian Constitution.
Thesis (LL.M. (Environmental law))--North-West University, Potchefstroom Campus, 2012.
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MATTIOLO, SANDRA R. "Diretrizes para implantação de um sistema de gestão ambiental no ciclo do combustível nuclear: estudo de caso da USEXA-CEA." reponame:Repositório Institucional do IPEN, 2012. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10169.

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IPEN/T
Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP
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Books on the topic "Uranium cycle"

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1964-, Bourdon Bernard, Mineralogical Society of America, and Geochemical Society, eds. Uranium-series geochemistry. Washington, DC: Mineralogical Society of America, 2003.

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Bernard, Bourdon, Geochemical Society, and Mineralogical Society of America, eds. Uranium-series geochemistry. Washington, D.C: Mineralogical Society of America, 2003.

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Austria) International Symposium on the Uranium Production Cycle and the Environment (2000 Vienna. The Uranium production cycle and the environment: Proceedings International Symposium held in Vienna, 2-6 October 2000. Vienna: IAEA, 2002.

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Finch, Warren Irvin. Uranium, its impact on the national and global energy mix: And its history, distribution, production, nuclear fuel-cycle, future, and relation to the environment. Washington: U.S. G.P.O., 1997.

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International, Symposium on Uranium Production and Raw Materials for the Nuclear Fuel Cycle (2005 Vienna Austria). Uranium production and raw materials for the nuclear fuel cycle: Supply and demand, economics, the environment and energy security : proceedings of an international symposium on ... Vienna: International Atomic Energy Agency, 2006.

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A, Fenter Paul, ed. Applications of synchrotron radiation in low-temperature geochemistry and environmental sciences. Washington, DC: Mineralogical Society of America, 2002.

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1930-, Logsdail D. H., and Mills A. L. 1931-, eds. Solvent extraction and ion exchange in the nuclear fuel cycle. Chichester: Published for the Society of Chemical Industry, London, by Ellis Horwood, 1985.

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International Symposium on Uranium and Electricity. Conference. Proc eedings: International symposium on uranium and electricity, the complete nuclear fuel cycle, September 18-21, 1988, Saskatoon, Canada. Edited by Talbot K. H, Lakshmanan V. I, Canadian Nuclear Society, and Canadian Nuclear Association. Peterborough, Ont: Heritage Publications, 1990.

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Symposium on Nuclear Fuel Cycle and Reactor Strategies: Adjusting to New Realities (1997 Vienna, Austria). Nuclear fuel cycle and reactor strategies: Adjusting to new realities : key issue papers from a symposium held in co-operation with the European Commission, the OECD Nuclear Energy Agency and the Uranium Institute 3-6 June 1997, Vienna. Vienna: International Atomic Energy Agency, 1997.

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Gotchy, R. L. Potential health and environmental impacts attributable to coal and nuclear fuel cycles: Final report. Washington, DC: Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1987.

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Book chapters on the topic "Uranium cycle"

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Usman, Shoaib. "Uranium-Plutonium Nuclear Fuel Cycle." In Nuclear Energy Encyclopedia, 77–87. Hoboken, NJ, USA: John Wiley & Sons, Inc., 2011. http://dx.doi.org/10.1002/9781118043493.ch11.

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Sreenivas, T., A. K. Kalburgi, M. L. Sahu, and S. B. Roy. "Exploration, Mining, Milling and Processing of Uranium." In Nuclear Fuel Cycle, 17–79. Singapore: Springer Nature Singapore, 2023. http://dx.doi.org/10.1007/978-981-99-0949-0_2.

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Falck, W. Eberhard. "Uranium Mining Life-Cycle Energy Cost vs. Uranium Resources." In The New Uranium Mining Boom, 201–9. Berlin, Heidelberg: Springer Berlin Heidelberg, 2011. http://dx.doi.org/10.1007/978-3-642-22122-4_24.

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Li, Zhiyong, Jiang Hu, Mei Rong, Xin Shang, and Yifan Zhang. "Economic Analysis of the One Through Fuel Cycle Based on Equilibrium Mass Flow." In Springer Proceedings in Physics, 156–64. Singapore: Springer Nature Singapore, 2023. http://dx.doi.org/10.1007/978-981-99-1023-6_15.

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AbstractIn order to evaluate the cost of each stage of the one through fuel cycle (OTC), the uranium required for each stage of the OTC is calculated in detail based on the equilibrium mass flow. According to the material flow analysis, front-end cost and back-end cost of the nuclear fuel cycle under different discount rates are analyzed according to the material flow. The results show that the front-end cost increases with the discount rate, while the back-end cost decreases with the discount rate, and the front-end cost is higher than the back-end cost. The three stages of natural uranium, uranium enrichment and fuel manufacturing not only account for a large proportion of the total cost, but also have a strong sensitivity. Among them, the cost of uranium enrichment has the greatest impact on LCOE, followed by the cost of natural uranium.
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Sharma, S. K. "Preliminary study of interaction between tailing and the hydrologic cycle at a uranium mine near Tatanagar, India." In Uranium, Mining and Hydrogeology, 631–38. Berlin, Heidelberg: Springer Berlin Heidelberg, 2008. http://dx.doi.org/10.1007/978-3-540-87746-2_79.

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Balygin, A. A., G. B. Davydova, A. M. Fedosov, A. V. Krayushkin, Y. A. Tishkin, A. I. Kupalov-Yaropolk, and V. A. Nikolaev. "Use of Uranium-Erbium and Plutonium-Erbium Fuel in Rbmk Reactors." In Safety Issues Associated with Plutonium Involvement in the Nuclear Fuel Cycle, 121–30. Dordrecht: Springer Netherlands, 1999. http://dx.doi.org/10.1007/978-94-011-4591-6_14.

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Marshalkin, V. E., V. M. Povyshev, and Yu A. Trurnev. "On Solving the Fissionable Materials Non-Proliferation Problem in the Closed Uranium-Thorium Cycle." In Advanced Nuclear Systems Consuming Excess Plutonium, 237–57. Dordrecht: Springer Netherlands, 1997. http://dx.doi.org/10.1007/978-94-007-0860-0_19.

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"Uranium and uranium-plutonium nuclear fuel." In Closed Nuclear Fuel Cycle with Fast Reactors, 161–67. Elsevier, 2022. http://dx.doi.org/10.1016/b978-0-323-99308-1.00034-9.

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Hooton, Brian. "The Nuclear Fuel Cycle." In Understanding Nuclear Reactors, 97–106. Oxford University PressOxford, 2024. http://dx.doi.org/10.1093/oso/9780198902652.003.0009.

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Abstract The nuclear fuel cycle is described, including the distinction between the open cycle and the closed cycle. Mining to create yellow cake, and enrichment by gas centrifuge using uranium hexafluoride (HEX), are explained. Fuel fabrication of uranium oxide pellets completes the front-end of the fuel cycle. The benefits and disadvantages of MAGNOX as a fuel pin cladding are explained. The back-end of the fuel cycle covers spent fuel management, fuel pond storage with the visibility of Cherenkov radiation. A flow sheet covering the plutonium-uranium extraction (PUREX) reprocessing method with mixer settlers is explained. The methods for dealing with high-level waste (HLW), by vitrification, are described. It treats the management of intermediate-level waste (ILW) and low-level waste (LLW).
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Jeff, Wilks. "Uranium conversion and enrichment." In Nuclear Fuel Cycle Science and Engineering, 151–76. Elsevier, 2012. http://dx.doi.org/10.1533/9780857096388.2.151.

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Conference papers on the topic "Uranium cycle"

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Bobrov, Evgeniy, Pavel Teplov, Pavel Alekseev, Alexander Chibinyaev, and Anatoliy Dudnikox. "Variants of the Perspective Closed Fuel Cycle, Based on REMIX-Technology." In 2014 22nd International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2014. http://dx.doi.org/10.1115/icone22-31244.

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In the traditional closed fuel cycle, based on REMIX-technology (REgenerated MIXture of U and Pu oxides) the fuel composition is produced on the basis of a uranium and plutonium mixture from spent Light Water Reactor (LWR) fuel and additional natural uranium. In this case, there is some saving in the amount of natural uranium used. The basic features of the WWER-1000 fuel loadings with a new variant REMIX-fuel during multiple recycle in the closed nuclear fuel cycle are described in this paper. Such fuel compositions are produced on a basis of a uranium and plutonium mixture allocated at processing the spent fuel after irradiation in the WWER-1000 core, depleted uranium and fission material such as: 235U as a part of high-enriched uranium from the warheads superfluous for defense. Also here variants are considered of the perspective closed fuel cycle in which fissile feed materials for fuel manufacture is produced in the blankets of fast breeder reactors. The fissile material is 233U or Pu. The raw material is depleted uranium from the stocks of enrichment factories, or thorium. Natural uranium is not used in this case. The minimum feed material required for the REMIX technology in a closed fuel cycle was determined through calculations of different types of fissile and raw materials, with different cycle lengths and fuel-water ratios.
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Kaufman, Alan, Geoffrey J. Gilleaudeau, Lucas B. Cherry, Joseph T. Kulenguski, and Maya Elrick. "URANIUM ISOTOPE EVIDENCE FOR REDOX COUPLING OF THE CARBON CYCLE." In GSA Connects 2021 in Portland, Oregon. Geological Society of America, 2021. http://dx.doi.org/10.1130/abs/2021am-367633.

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Grambow, B., A. Abdelouas, F. Guittonneau, J. Vandenborre, J. Fachinger, W. von Lensa, P. Bros, et al. "The Backend of the Fuel Cycle of HTR/VHTR Reactors." In Fourth International Topical Meeting on High Temperature Reactor Technology. ASMEDC, 2008. http://dx.doi.org/10.1115/htr2008-58177.

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For various countries, the direct disposal of high level nuclear fuel wastes is a key option for the backend of the fuel cycle. For HTR/VHTR reactors this is assumed for the introductory phase of this reactor system. However, closed fuel cycles or a separation of spent coated-particles from the graphite moderator and specific treatment, conditioning and disposal of these waste streams are also possible. In the European Community project “RAPHAEL”, fuel waste performance is going to be studied in depth, including post-irradiation fuel characterization, analysis of the stability and failure mechanism of coatings and of fuel kernels and overall performance of waste packages with compact fuel and/or only with fuel particles in geological disposal environments. Different confinement matrices for separated fuel particles (vitrification, SiC, ZrO2) have been adapted to limit release of radionuclides into groundwater at low temperatures over geological time spans. The investigations are limited to Low-Enriched Uranium (LEU) fuel with uranium oxide and uranium oxycarbide kernels that will allow higher burn-up, but may be more susceptible to leaching.
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Boczar, Peter G., Bronwyn Hyland, Keith Bradley, and Sermet Kuran. "Achieving Resource Sustainability in China Through the Thorium Fuel Cycle in the Candu Reactor." In 18th International Conference on Nuclear Engineering. ASMEDC, 2010. http://dx.doi.org/10.1115/icone18-29664.

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The CANDU® reactor is the most resource-efficient reactor commercially available. The features that enable the CANDU reactor to utilize natural uranium facilitate the use of a wide variety of thorium fuel cycles. In the short term, the initial fissile material would be provided in a “mixed bundle”, in which low-enriched uranium (LEU) would comprise the outer two rings of a CANFLEX® bundle, with ThO2 in the central 8 elements. This cycle is economical, both in terms of fuel utilization and fuel cycle costs. The medium term strategy would be defined by the availability of plutonium and recovered uranium from reprocessed used LWR fuel. The plutonium could be used in Pu/Th bundles in the CANDU reactor, further increasing the energy derived from the thorium. Recovered uranium could also be effectively utilized in CANDU reactors. In the long term, the full energy potential from thorium could be realized through the recycle of the U-233 (and thorium) in the used CANDU fuel. Plutonium would only be required to top up the fissile content to achieve the desired burnup. Further improvements to the CANDU neutron economy could make possible a very close approach to the Self-Sufficient Equilibrium Thorium (SSET) cycle with a conversion ratio of unity, which would be completely self-sufficient in fissile material (recycled U-233).
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Yurievna Artamonova, Svetlana. "URANIUM IN AEROSOL OF NUCLEAR FUEL CYCLE ENTERPRISES REGION (NOVOSIBIRSK, RUSSIA)." In 15th International Multidisciplinary Scientific GeoConference SGEM2015. Stef92 Technology, 2011. http://dx.doi.org/10.5593/sgem2015/b51/s20.131.

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Romaniello, Stephen J. "Uranium Isotope Constraints on the Dynamics of Global Carbon Cycle Perturbations." In Goldschmidt2020. Geochemical Society, 2020. http://dx.doi.org/10.46427/gold2020.2220.

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Liberge, Renaud, and Marc Arslan. "Nuclear Fuel Cycle: Which Strategy to Sustain Nuclear Renaissance?" In 18th International Conference on Nuclear Engineering. ASMEDC, 2010. http://dx.doi.org/10.1115/icone18-29574.

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By proposing a credible response to the growing demand for energy while emitting no greenhouse gas, nuclear power will more than likely expand in the future, leading to increased quantities of used nuclear fuel to manage. Recycling the energy from this used fuel and an efficient waste management are key components for a sustainable development of nuclear energy. Current closed fuel cycle enables 25% in uranium savings, reduces the volume of waste by a factor 5 while its radiotoxicity is divided by a factor 10. Excellent track records of existing recycling plants participate to the competitiveness of MOX (Mixed Oxide) and ERU (Enriched Reprocessed Uranium) fuels compared to ENU (Enriched Natural Uranium) fuel. By offering a sound solution for nuclear waste management, recycling also contribute to favour nuclear acceptance. The advantages of closed fuel cycle have been demonstrated by the successful policy of recycling implemented in Europe for more than 30 years, with 35 reactors using MOX fuel with an excellent return of experience. The AREVA industrial recycling platform (La Hague and Melox plants) has treated more than 24,500 tons of used fuel and fabricated more than 1,600 tons of MOX fuel. With the new AREVA EPR™ reactor, recycling will take another step forward, enabling MOX fuel loading of up to 100%, thus offering optimized management options of recycled fuel, and giving more flexibility to its customers.
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Zhang, Zhenhua, Mingjun Chen, Peide Zhou, Qing Li, Zhiliang Meng, and Guowei Zhang. "CANDU Position and Prospect in Chinese Nuclear Fuel Cycle." In 2013 21st International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2013. http://dx.doi.org/10.1115/icone21-16727.

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To manage climate challenge and optimize energy supply structure, China has decided to develop more nuclear power in a safe and high-efficiency manner. On a nuclear sustainable development perspective, it is necessary to develop a closed fuel cycle (CFC) system and also take great efforts to improve natural uranium (NU) utilization ratio of thermal reactor. CANDU is great certainty to play an important role in this strategy. This paper presents CNNC Third Qinshan Nuclear Power Company Limited (TQNPC) efforts of being develop the engineering technologies of recycling reprocessed uranium (RU) and nuclear use of thorium (Th) resource in CANDU type reactor and finding the CANDU’s position in Chinese CFC system. Also this paper provides a proposal of implementation plan for Chinese CFC system development and also for application of the related CANDU engineering technologies.
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Gerasimov, Aleksander S., Boris R. Bergelson, and Tamara S. Zaritskaya. "Two Periods of Long-Term Storage of Thorium Spent Fuel." In ASME 2001 8th International Conference on Radioactive Waste Management and Environmental Remediation. American Society of Mechanical Engineers, 2001. http://dx.doi.org/10.1115/icem2001-1219.

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Abstract Radiotoxicity and decay heat power of actinides from spent thorium-uranium nuclear fuel of VVER-1000 type reactor during 100 000 year storage are discussed. Actinide accumulation in thorium fuel cycle is much less than in uranium fuel cycle. The radiotoxicity of actinides of thorium-uranium fuel by air is 5.5 times less and radiotoxicity by water is 3.5 times less than radiotoxicity of actinides of uranium fuel. Extraction of most important nuclides for transmutation permits to reduce radiologic danger of wastes remaining in storage.
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Mazanik, K. V., A. N. Skibinskaya, and A. I. Kiyavitskaya. "TRITIUM IN NUCLEAR FUEL CYCLE." In SAKHAROV READINGS 2021: ENVIRONMENTAL PROBLEMS OF THE XXI CENTURY. International Sakharov Environmental Institute of Belarusian State University, 2021. http://dx.doi.org/10.46646/sakh-2021-2-276-279.

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The nuclear fuel cycle (further NFC) includes the following main stages: mining of uranium ore, enrichment, production, operation of a nuclear power plant (further NPP) (power generation), management of spent nuclear fuel (further SNF) and radioactive waste (furtherr RW). In the NFC, tritium is formed at the stages of NPP operation and during SNF and RW handling, storage and disposal. In connection with the construction and commissioning in Belarus, monitoring of the tritium content in environmental objects is a important task at all stages of the station’s life.
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Reports on the topic "Uranium cycle"

1

Nolen, Blake, Joe Wermer, and Pallas Papin. The uranium fuel cycle. Office of Scientific and Technical Information (OSTI), February 2012. http://dx.doi.org/10.2172/1159068.

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Crowder, M. L. Studies with Ferrous Sulfamate and Alternate Reductants for 2nd Uranium Cycle. Office of Scientific and Technical Information (OSTI), January 2003. http://dx.doi.org/10.2172/807667.

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Douthat, D. M., A. Q. Armstrong, and R. N. Stewart. Operating and life-cycle costs for uranium-contaminated soil treatment technologies. Office of Scientific and Technical Information (OSTI), September 1995. http://dx.doi.org/10.2172/206528.

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Kiplinger, Jaqueline Loetsch, Blake Penfield Nolen, and Justin Kane Pagano. Transforming the Uranium Fuel Cycle: Safe & Economical Conversion of DUF6 to DUF4. Office of Scientific and Technical Information (OSTI), September 2019. http://dx.doi.org/10.2172/1569592.

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Kiplinger, Jaqueline Loetsch. Transforming the Uranium Fuel Cycle: Safe & Economical Conversion of DUF6 to DUF4. Office of Scientific and Technical Information (OSTI), October 2019. http://dx.doi.org/10.2172/1569727.

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Parks, C. V. Plutonium Production Using Natural Uranium From the Front-End of the Nuclear Fuel Cycle. Office of Scientific and Technical Information (OSTI), August 2002. http://dx.doi.org/10.2172/814165.

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Williams, Kent, Jason Hansen, and Ed Hoffman. Advanced Fuel Cycle – Cost Basis Report: Module D1-3 Uranium-based Ceramic Particle Fuel Fabrication. Office of Scientific and Technical Information (OSTI), September 2021. http://dx.doi.org/10.2172/2308750.

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Williams, Kent, Jason Hansen, and Ed Hoffman. Advanced Fuel Cycle Cost Basis Report: Module D1-1 Uranium-based Ceramic LWR Fuel Fabrication. Office of Scientific and Technical Information (OSTI), September 2023. http://dx.doi.org/10.2172/2316041.

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Zipperer, Travis, David Colameco, and Kenneth Geelhood. Criticality Safety and Fuel Performance Considerations for Enrichment Above 5 Weight Percent in the Uranium Dioxide Fuel Cycle. Office of Scientific and Technical Information (OSTI), July 2020. http://dx.doi.org/10.2172/1984525.

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Hansen, Jason, Ed Hoffman, and Kent Williams. Advanced Fuel Cycle – Cost Basis Report: Module C3 High-Assay Low-Enriched Uranium (HALEU) Enrichment and Deconversion/ Metallization. Office of Scientific and Technical Information (OSTI), September 2023. http://dx.doi.org/10.2172/2278788.

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