Recycling of nuclear spent fuel with AIROX processing

Majumdar, D.; Jahshan, S.N.; Allison, C.M.; Kuan, P.; Thomas, T.R.

doi:10.2172/10146308

Cited by 12 publications

(6 citation statements)

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“…− can be used to differentiate the Nd(TTA) 3 and Nd(TTA) 4 − species formed in the TTA-RTIL system. 32a The UV−vis spectra of extracted Nd 3+ species into 0.1 M TTA in C 4 mim•NTf 2 at pH 5 appeared very similar (Figure S7) to the species obtained after dissolution of Nd 2 O 3 in wet TTA-RTIL, suggesting the formation of anionic Nd(TTA) 4…”

Section: Speciation Of Dissolved Eu(iii)mentioning

confidence: 99%

“…(v) Most of the transuranium elements formed at the atomistic scale can substitute for U in the UO 2 matrix and exist in the form of AnO 2 (An = Pu, Np, and Am) . The majority of the volatiles or semivolatiles can be removed by AIROX, OREX, or voloxidation treatment of the spent fuel. The PGM and other FPs, such as Rb, Cs, Ba, and Zr, form separate metallic or oxide phases.…”

Section: Introductionmentioning

confidence: 99%

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Simple, Fast, and Selective Dissolution of Eu₂O₃ in an Ionic Liquid as a Sustainable Paradigm for Lanthanide–Actinide Separations in Radioactive Waste Remediation

et al. 2022

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The liquid–liquid extraction (LLE) process for lanthanide–actinide separation from the nuclear fuel cycle has several drawbacks such as, the requirement of cooling for decay heat control, the handling of large volumes of toxic volatile organic compounds (VOCs), and secondary waste generation. Alternatively reprocessing without spent fuel cooling is done by pyroprocessing, which uses high-temperature corrosive molten salts and requires elevated temperature, and is an energy-intensive process. In recent years, some of the shortcomings of both LLE and pyroprocessing are overcome by the use of room temperature ionic liquids (RTILs) as the solvents. In the present work, an attempt was made to exploit the potential of the neoteric, less-corrosive, low-VOC RTILs toward direct dissolution-based separations at ambient conditions. The present paper involves the selective dissolution of Eu2O3 in an RTIL, i.e., C4mim·NTf2 containing 2-thenoyltrifluoroacetone (HTTA) within ca. 30 min at ambient conditions; while the dissolution of AmO2 and UO2 were found to be very poor, making this an attractive method for lanthanide–actinide separation, a key step in radioactive waste management, i.e., an actinide partitioning and transmutation strategy. The quantitative dissolution of Eu2O3 from simulated spent nuclear fuel with different Eu2O3 loading was also shown. Water plays a crucial role in deciding the kinetics of dissolution and amount of the dissolved oxide. The combination of X-ray absorption, fluorescence, and UV–vis spectroscopic studies suggested the formation of the dehydrated anionic complex Ln(TTA)4 – to play pivotal role in the oxide dissolution process. The structure of the complex was analyzed by density functional theory and extended X-ray absorption fine structure. The mechanism of oxide dissolution was proposed and electrochemical studies were performed to understand the possible recovery option using electrodeposition of the dissolved Eu3+.

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Section: Speciation Of Dissolved Eu(iii)mentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Simple, Fast, and Selective Dissolution of Eu₂O₃ in an Ionic Liquid as a Sustainable Paradigm for Lanthanide–Actinide Separations in Radioactive Waste Remediation

et al. 2022

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“…If ADCFR is combined with simple high‐dry reprocessing, a fully closed nuclear‐energy system becomes feasible. It belongs to ADANES, which is an ideal clean nuclear‐fission energy system.…”

Section: Discussionmentioning

confidence: 99%

Conceptual study of an accelerator-driven ceramic fast reactor with long-term operation

Yan

Zhang

et al. 2018

Int J Energy Res

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Summary To improve both safe operation and high resource utilization in nuclear power, we propose and investigate the concept of an accelerator‐driven ceramic fast reactor (ADCFR). This reactor type has the potential to operate continuously throughout a 40‐year core life, without fuel shuffling or supplementation. The ADCFR consists of a high‐power superconducting linear accelerator, a gravity‐driven dense granular spallation‐target, and a ceramic fast reactor. The performance of the ADCFR was assessed by using a neutron‐physics simulation, thermal calculations, and a characteristic analysis. The results show that the peak position for the neutron spectrum in the ADCFR is at about 0.1 MeV. This means that it falls with the fast neutron spectrum, and it can convert loaded nuclear fertile material into fissile fuel. Using a burnup simulation, the ideal effective multiplication‐factor (Keff) was calculated by using a combination of subcritical (accelerator‐driven) and critical modes. In 40 year of operation, Keff is obtained from the initial 0.98 to the peak ~1.02 and then to ~0.99. Different granular coolant materials were selected to compare neutron performance. In breeding, the differences are relatively small. The thermal calculation indicates that heat transfer performance of granular makes it possible to meet the required specifications in theory. Finally, the corresponding characteristics, with regard to the 2‐phase coolant, ceramic materials, nuclear safety performance, operation modes, economics, and range of applications were analyzed. Accelerator‐driven ceramic fast reactors can achieve very high levels of inherent safety, good breeding performance, high power‐generation efficiency, and high flexibility in wide range of applications.

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“…In this work, the composition of the spent fuel was obtained by previous studies [20], considering a typical PWR fuel with initial enrichment of 4.5% and a 50 GWd/MTU of burnup. A calculation was made to obtain the recovering fuel composition taking into consideration the percentage of fission product removal by AIROX [21] and OREOX [22]. The results comprise two reprocessed fuel that was used in the simulations namely: FRA (Fuel Reprocessed by AIROX technique) and FRO (Fuel Reprocessed by OREOX technique).…”

Section: Evaluated Fuelsmentioning

confidence: 99%

Neutronic evaluation of CANDU-6 core using reprocessed fuels

et al. 2020

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The spent fuel from a PWR still contains some amount of fissile materials depending on their initial enrichment and the burnup. Thus, spent fuel from PWRs containing about 1.5% of fissile material could be used as fuel for CANDU reactors after some fission products are removed from it. Thus, an important proposal is the DUPIC cycle, where spent fuels from a PWR are packaged into a CANDU fuel bundle using mechanical reprocessing but without the need of chemical reprocessing. When it is refueled with reprocessed fuel, the reactivity of the system increases, and this behavior may affect the safety parameters of the reactor. Therefore, this work studies the neutronic parameters of two reprocessing fuel techniques: AIROX and OREOX, which are evaluated for two different cores configuration. The first one considers heavy water as a moderator and coolant. The second one considers heavy water and light water as moderator and coolant respectively. These studies evaluate the core behavior based on the different number of reprocessed fuels channels and compare them with the reference core. To perform the simulation the MCNPX was used to calculate the effective multiplication factor, fuel temperature coefficient of reactivity, void reactivity coefficient, and neutron flux, which were evaluated at steady state condition for the different cases. The results show that the presence of parasitic absorbers in the reprocessed fuels hardens the neutron spectrum. This behavior provokes an increase in the core reactivity, in the fuel temperature coefficient and in the void reactivity coefficient. Among these parameters, the use of light water reduces the core reactivity but do not improve the fuel temperature coefficient and the void reactivity coefficient.

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Recycling of nuclear spent fuel with AIROX processing

Abstract: Portions of this document may be illegible electronic image products. Images are produced from the best available original document.

Cited by 12 publications

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Simple, Fast, and Selective Dissolution of Eu₂O₃ in an Ionic Liquid as a Sustainable Paradigm for Lanthanide–Actinide Separations in Radioactive Waste Remediation

Simple, Fast, and Selective Dissolution of Eu₂O₃ in an Ionic Liquid as a Sustainable Paradigm for Lanthanide–Actinide Separations in Radioactive Waste Remediation

Conceptual study of an accelerator-driven ceramic fast reactor with long-term operation

Neutronic evaluation of CANDU-6 core using reprocessed fuels

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Recycling of nuclear spent fuel with AIROX processing

Abstract: Portions of this document may be illegible electronic image products. Images are produced from the best available original document.

Cited by 12 publications

References 0 publications

Simple, Fast, and Selective Dissolution of Eu2O3 in an Ionic Liquid as a Sustainable Paradigm for Lanthanide–Actinide Separations in Radioactive Waste Remediation

Simple, Fast, and Selective Dissolution of Eu2O3 in an Ionic Liquid as a Sustainable Paradigm for Lanthanide–Actinide Separations in Radioactive Waste Remediation

Conceptual study of an accelerator-driven ceramic fast reactor with long-term operation

Neutronic evaluation of CANDU-6 core using reprocessed fuels

Contact Info

Product

Resources

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Simple, Fast, and Selective Dissolution of Eu₂O₃ in an Ionic Liquid as a Sustainable Paradigm for Lanthanide–Actinide Separations in Radioactive Waste Remediation

Simple, Fast, and Selective Dissolution of Eu₂O₃ in an Ionic Liquid as a Sustainable Paradigm for Lanthanide–Actinide Separations in Radioactive Waste Remediation