ADS Fuel Developments in Europe: Results from the EUROTRANS Integrated Project.

Delage, F.; Belin, Renaud C.; Xn, Chen; Elio, D'agata; Klaassen, F.M.; Knol, S.; Maschek, W.; Ottaviani, Jean-Pierre; Rineiski, A.; Sobolev, V.; Somers, J.; Staicu, D.; Thetford, R.; Wallenius, Janne; Wernli, B.

doi:10.1016/j.egypro.2011.06.039

Cited by 21 publications

(4 citation statements)

References 2 publications

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“…MgO provides good thermal conductivity, it is considered as a good candidate as IM [12]. Some irradiation tests showed that MgO-MA pellets appearance was much closed to the fresh one, very small swelling rates were observed for the MgO fuel.…”

Section: Inert Matrix Fuel (Imf) For Transmutationmentioning

confidence: 99%

Ceramics for high level radioactive waste solidification

Wang¹,

Liang²

2012

J Adv Ceram

106

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Several countries reprocess their nuclear spent fuel using the Purex process to recover U and Pu as MOX fuel. The high level radioactive waste (HLW) produced during this reprocessing is a complex mixture containing both radioactive (fission products, minor actinides) and non-radioactive elements. Since HLW shows high rate heat release and contains some long half-life and biologically toxic radionuclide, its treatment and disposal technology is complex, difficult and high cost. HLW treatment and disposal become a worldwide challenge and research focus. In order to minimize the potential long-term impact of HLW, studies on enhanced chemical separation processes of long-lived radionuclides are in progress. Two options are then envisaged for these separated radionuclides: (a) transmutation into short-lived or non-radioactive elements, (b) immobilization in highly durable ceramic matrix instead of borosilicate glass. In this paper, we briefly review the composition, structure, processing and product properties of some ceramic candidates for inert matrix fuels (IMF) and the immobilization of high level radioactive waste.

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Section: Inert Matrix Fuel (Imf) For Transmutationmentioning

confidence: 99%

Ceramics for high level radioactive waste solidification

Wang¹,

Liang²

2012

J Adv Ceram

106

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“…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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“…A fast waste burner core designed as a 1.14x1.14x90 cm 3 hexahedral lattice filled with 0.5 cm radius rods surrounded by a 0.05 cm thick steel cladding and embedded in He gas. The fuel, a futurix6 [19] type of ceramic actinide mixture, could be varied again by changing the Pu isotopes mass percentage. In this case, we found that no material can be interposed between the fuel elements to obtain a relatively high value of k eff which is more of interest in this context.…”

Section: The Modelmentioning

confidence: 99%

An alternative observable to estimate keff in fast ADS

Chersola¹,

Ricco²,

Ripani³

et al. 2016

Preprint

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In this paper we examine an alternative method for determining the neutron multiplication factor k eff in fast subcritical reactors, based on the observable obtained by calculating the ratio between the "fast" component of the neutron flux (in this case by fast we mean neutrons with kinetic energy above 0.5 MeV) and the whole flux at all energies. The assumption behind the present study was that the above mentioned observable would be only sensitive to k eff , provided a peripheral fuel rod is considered (i.e. far from the neutron source in subcritical systems) and k eff is sufficiently high. Indeed, our results show that, for k eff > 0.7, the ratio calculated for LFR or GFR models turns out to show a quite similar trend well approximated by a straight line, while a different slope is observed for a sodium reactor. In our opinion, the results obtained show that such observable, after appropriate calibrations on the real systems under consideration, may be used for determining k eff in all operational conditions, in particular for subcritical systems with different types of neutron source and different values of the beam current.

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ADS Fuel Developments in Europe: Results from the EUROTRANS Integrated Project.

Cited by 21 publications

References 2 publications

Ceramics for high level radioactive waste solidification

Ceramics for high level radioactive waste solidification

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

An alternative observable to estimate keff in fast ADS

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