Spent Nuclear Fuel as Waste Material

Carbol, Paul; Detlef, Wegen; Thierry, Wiss; Fors, Patrik

doi:10.1016/b978-0-12-803581-8.10374-1

Cited by 8 publications

(8 citation statements)

References 138 publications

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“…Furthermore, fuels to be used in ADS systems dedicated to MAs transmutation can be described as highly innovative in comparison with those used in critical cores (Maschek et al, 2008). Irrespective of the recycling method considered, MAs are transmuted preferably in their dioxide form of cubic fluorite structure (Delage et al, 2020;Carbol et al, 2012), which, based on the lengthy experience available on MOX fuel, is known to provide good stability under irradiation (Pelletier and Guérin 2020). Because of the historical experience and knowledge gained on oxide fuels for LWR and FR, MA oxide fuel forms have been preferentially investigated in Europe and emerged as the primary option (Delage et al, 2011), which was also considered as a primary option for the Chinese ADS fuels research and development (R&D).…”

Section: Introductionmentioning

confidence: 99%

Preliminary Multi-Physics Performance Analysis and Design Evaluation of UO2 Fuel for LBE-Cooled Subcritical Reactor of China Initiative Accelerator Driven System

Wang

Yun

2021

Front. Energy Res.

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The China initiative Accelerator Driven System (CiADS) and the corresponding lead-bismuth eutectic (LBE) cooled subcritical reactor, as the research subject of one of the major national science and technology infrastructure projects, are undertaken by the Institute of Modern Physics-Chinese Academy of Sciences (IMP-CAS). And in the first phase, UO2 fuels will be loaded in the subcritical core to test the coupling technology and achieve a long-term steady operation. A brief description of CiADS subcritical reactor, fuel assembly and fuel element are presented here, and a multi-physics performance analysis and design evaluation of CiADS UO2 fuel are carried out by means of the FUTURE code. FUTURE is a fuel performance analysis code to evaluate the synergy of phenomena occurring in the fuel element and their impact on the fuel design improvement for the liquid metal fast reactor, which was developed jointly by IMP-CAS and Xi’an Jiaotong University (XJTU). In this paper, the FUTURE code was modified and updated focusing on characteristics of CiADS fuels. Relocation and densification models were added. Results of the hottest fuel element, mainly concerning the thermo-mechanical behaviors, are discussed concerning both fuel and cladding performance on the basis of indicative design limits. According to the preliminary design, the CiADS UO2 fuel exhibits good performance, and the main safety parameters are far below the indicative limits. The Fuel Cladding Mechanical Interaction (FCMI) is not very serious, and the permanent cladding strains and Cumulative Damage Fraction (CDF) are small and even negligible thanks to the low level of fuel temperature and corresponding stress. However, some critical issues may still exist, especially on LBE corrosion near the coolant inlet, where protective oxide layers are very thin from BoL to EoL. The modeling is useful for providing feedback to the conceptual design of the CiADS LBE-cooled subcritical reactor and the update of FUTURE code.

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Section: Introductionmentioning

confidence: 99%

Preliminary Multi-Physics Performance Analysis and Design Evaluation of UO2 Fuel for LBE-Cooled Subcritical Reactor of China Initiative Accelerator Driven System

Wang

Yun

2021

Front. Energy Res.

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“…The objective of this chapter is to present the key points to consider in studying the alteration of these complex systems as well as the bases of a relevant methodology. This approach is mainly based on the feedback acquired during the last 40 years on the alteration mechanisms of UOX and MOX spent fuels under interim wet storage or geological disposal conditions [49,[68][69][70][71][72]. Recent papers on the alteration of materials simulating fuel debris or on samples coming from accident sites are also considered.…”

Section: Interaction Of Simulated Debris With Water and Lessons Learned From Spent Fuel Leaching Studiesmentioning

confidence: 99%

Ten years after the NPP accident at Fukushima : review on fuel debris behavior in contact with water

Grambow

Nitta

Shibata

et al. 2021

Journal of Nuclear Science and Technology

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Following the NPP accident, several hundred tons of heat-generating corium and fuel debris have been cooled permanently by millions of m 3 of flowing. Knowledge on the interaction with water is crucial for any decommissioning planning.Starting from knowledge on the evolutions of the accident in the three reactor cores and associated fuel debris formations and some additional isotopic and physio-chemical information on debris fragments collected in Fukushima soils, we review the temporal evolution of the chemistry and leached radionuclide contents of the cooling water, comparing measured concentration ratios of the actinides and fission products in the water to reported results of laboratory leaching studies with either spent nuclear fuel or simulated fuel debris.As for spent fuel leaching, the fractions of inventories of 134,137 Cs in the cooling water are orders of magnitude larger than that of the actinides. After more than 10 years of fuel debris/ water contact, 137 Cs release rates have decreased by about a factor of 100. The total release of actinides from the fuel debris is orders of magnitude lower than that of 134,137 Cs or of 90 Sr. This high stability makes direct disposal of fuel debris in suitable containers after decommissioning a viable option.

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“…To this day, proliferation concerns have superseded reprocessing efforts in places like the U.S., forcing countries to instead increase their SNF storage capacity, thus deferring action on the nuclear waste issue. 4,6,7 New strategies for the selective separation and recovery of UO 2 2+ from SNF, without the parallel extraction of a Pu stream, could therefore significantly aid in reducing net SNF generated from reactors, minimizing demands on long-term geological repositories, and in turn closing the fuel cycle.…”

Section: Introductionmentioning

confidence: 99%

Selective electrochemical capture and release of uranyl from aqueous alkali, lanthanide, and actinide mixtures using redox-switchable carboranes

et al. 2022

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Spent Nuclear Fuel as Waste Material

Cited by 8 publications

References 138 publications

Preliminary Multi-Physics Performance Analysis and Design Evaluation of UO2 Fuel for LBE-Cooled Subcritical Reactor of China Initiative Accelerator Driven System

Preliminary Multi-Physics Performance Analysis and Design Evaluation of UO2 Fuel for LBE-Cooled Subcritical Reactor of China Initiative Accelerator Driven System

Ten years after the NPP accident at Fukushima : review on fuel debris behavior in contact with water

Selective electrochemical capture and release of uranyl from aqueous alkali, lanthanide, and actinide mixtures using redox-switchable carboranes

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