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Energies
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Storage and Disposal Options for Nuclear Waste II
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Storage and Disposal Options for Nuclear Waste II

A special issue of Energies (ISSN 1996-1073). This special issue belongs to the section "B4: Nuclear Energy".

Deadline for manuscript submissions: closed (30 June 2023) | Viewed by 2722

Special Issue Editor

Dr. Katarzyna Kiegiel

E-Mail Website
Guest Editor
Centre for Radiochemistry and Nuclear Chemistry, Institute of Nuclear Chemistry and Technology, 16 Dorodna, 03-161 Warszawa, Poland
Interests: synthesis; organic synthesis; uranium; leaching; extraction; leaching processes; separation
Special Issues, Collections and Topics in MDPI journals

Special Issue Information

Dear Colleagues,

Nuclear technology has multiple applications that are fundamental to our daily life. It is impossible to list all the uses of ionizing radiation. It is used in medical diagnostics and therapy, sterilization of medical equipment, generating low-carbon electricity, improving agriculture and food production, and hydrology. The sustainable application of nuclear technologies is fully linked with the responsible management of produced waste. Nuclear waste releases radiation and it must be managed suitably, safely, and effectively. The management and disposal of radioactive waste are some of the most problematic aspects of the nuclear fuel cycle today. Advanced fuel recycling technologies are focused on efficiently removing and transmuting the most radiotoxic long-lived portions of used nuclear fuel (UNF). Substantial progress is needed globally in the management of radioactive waste. Efficient solutions for radioactive waste management operations are already available or are in advanced phases of development. More progress could be expected in the near- and medium-term. However, issues of nuclear waste management are not only technical, but also social. This Special Issue will not only focus on methods and conceptions of storage and disposal of nuclear waste, but also improving the visibility of development, good practice, and potent solutions.

Dr. Katarzyna Kiegiel
Guest Editor

Manuscript Submission Information

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Please visit the Instructions for Authors page before submitting a manuscript. The Article Processing Charge (APC) for publication in this open access journal is 2600 CHF (Swiss Francs). Submitted papers should be well formatted and use good English. Authors may use MDPI's English editing service prior to publication or during author revisions.

Keywords

  • radioactive waste
  • management
  • storage
  • disposal of nuclear waste
  • nuclear reprocessing

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Published Papers (2 papers)

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Research

18 pages, 5805 KiB  
Article
Back-Analysis of Rock Mass Strength at a Radioactive Waste Disposal Site Using Acoustic Emission Monitoring Data and 3D Numerical Modelling
by Ferenc Deák, Matthew A. Perras, István Szűcs and Ákos Török
Energies 2023, 16(12), 4686; https://doi.org/10.3390/en16124686 - 13 Jun 2023
Cited by 1 | Viewed by 988
Abstract
In this study, a new method was examined that used acoustic emission (AE) monitoring data, in combination with a primary Boundary Element stress analysis, to back-calculate rock mass strength. The presented AE data came from the National Radioactive Waste Repository (NRWR) for low- [...] Read more.
In this study, a new method was examined that used acoustic emission (AE) monitoring data, in combination with a primary Boundary Element stress analysis, to back-calculate rock mass strength. The presented AE data came from the National Radioactive Waste Repository (NRWR) for low- and intermediate-level waste (LLW/ILW). AE monitoring is able to detect the pre-peak, peak, and post-peak stress changes in rock mass. The presented method used AE monitoring data to back-calculate parameters, such as uniaxial compressive strength and the rock mass deformation modulus. The AE initiation threshold was used to develop an objective function that considered the stress in the rock mass and the rock mass strength. The findings of this research propose that most AE events can be related to the crack initiation threshold, and in space, most of them are located at points away from the excavated walls. In the vicinity of the excavation damage zones around the cavities, the stress conditions beyond the crack damage boundary of the rock mass occur in many areas, leading to significant irreversible deformations. This novel method was demonstrated to aid in the prediction of rock mass strength and is a valuable, non-invasive method for improving the spatial prediction of rock mass parameters, which will lead to safer underground storage facilities. Full article
(This article belongs to the Special Issue Storage and Disposal Options for Nuclear Waste II)
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18 pages, 26113 KiB  
Article
Minor Actinides Transmutation and 233U Breeding in a Closed Th-U Cycle Based on Molten Chloride Salt Fast Reactor
by Liaoyuan He, Liang Chen, Shaopeng Xia and Yang Zou
Energies 2022, 15(24), 9472; https://doi.org/10.3390/en15249472 - 14 Dec 2022
Cited by 2 | Viewed by 1313
Abstract
Long-lived minor actinides (MAs) are one of the primary contributors to the long-term radiological hazards of nuclear waste, and the buildup of MAs is hampering the development of nuclear power. The transmutation of MAs in reactors is regarded as a potential way to [...] Read more.
Long-lived minor actinides (MAs) are one of the primary contributors to the long-term radiological hazards of nuclear waste, and the buildup of MAs is hampering the development of nuclear power. The transmutation of MAs in reactors is regarded as a potential way to replace direct disposal to reduce the impact of MA on the environment and improve the utilization of fuel. Due to its superior features, such as outstanding neutron economy, no fuel assembly fabrication, high neutron flux, and especially online refueling and reprocessing, the molten chloride salt fast reactor (MCFR) is regarded as one of the potential reactors for MA incineration. In this work, MA transmutation capability and 233U breeding performance for an optimized MCFR have been evaluated in different scenarios. The results show that the MA transmutation capability and 233U breeding performance with online transuranic elements (TRU) and 232Th feeding scenario are improved significantly compared with the case in online 233U and 232Th feeding, when the initial MA loading is 5 mol%, the total mass of MA transmutation and MA incineration is 7160 kg and 1759 kg during the whole 100 years operation under online TRU and 232Th feeding scenario, and the corresponding average annual net production of 233U is 450 kg, however, the MA transmutation amount, MA incineration amount and average annual net production of 233U for online 233U and 232Th feeding scenario is 5298 kg, 1315 kg, and 249 kg, respectively. In addition, the research also shows that the increase in initial loading of MA has no obvious effect on the improvement of the 233U breeding performance but can improve the transmutation efficiency of MA under online TRU and 232Th feeding scenarios. Furthermore, if 233U is continuously extracted online from the core during the operation, the 233U breeding performance will be significantly improved, but it will deteriorate the safety performance, such as the fuel temperature coefficient of reactivity (TCR) and the effective delayed neutron fraction (EDNF), more importantly, it will also put forward higher requirements for the immature online reprocessing technology. Full article
(This article belongs to the Special Issue Storage and Disposal Options for Nuclear Waste II)
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