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Potential application of graphene oxide and Aspergillus niger spores with high adsorption capacity for recovery of europium from red phosphor,compact fluorescent lamp and simulated radioactive waste

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Journal of Rare Earths 2023年第1期41卷 157-166页

作者： B.Arunraj Vidya Rajesh N.Rajesh Department of Chemistry Birla Institute of Technology and Science-PilaniHyderabad CampusShameerpetHyderabad 500078India Department of Biological Sciences Birla Insttute of Technology and Science-PilaniHyderabad CampusShameerpetHyderabad 500078India

The recovery of rare earth elements(REEs) is a global challenge and the mining of rare earths has serious environmental implications due to the toxic waste released post ***,the rising demand for rare earths and their far reaching electronic applications necessitates an effective strategy to recover the REEs from more viable *** this work,the graphene oxide-Aspergillus niger spores(*** spores) blend was utilized for adsorptive recovery of a precious rare earth Eu(Ⅲ) and the adsorption variables like pH of the medium,adsorbent dosage,sorption kinetics,thermodynamics,and isotherm were optimized for the developed bioso *** adsorption process suits the Langmuir isotherm model with a maximum adsorption capacity of 147.3 mg/*** pseudo-second-order kinetics is a perfect fit to describe the adsorption *** results obtained through the Van’t Hoff plot show negative free energy change(ΔG^(0)) which implies the spontaneity of the adsorption *** negative standard enthalpy change(ΔH^(0)) values show that the nature of the adsorption process is *** analytical characterizations including Fourier transform infrared spectroscopy(FTIR),Raman,X-ray diffraction(XRD),X-ray photoelectron spectroscopy(XPS),Brunauer-Emmett-Teller(BET),thermal gravimetric analysis(TGA),and scanning electron microscopy-energy dispersive X-ray spectroscopy(SEM-EDX) were employed to study the *** features of *** spores biosorbent were applied to recover Eu(Ⅲ) from real samples such as fluorescent lamp phosphor,red phosphor powder,and a simulated radioactive waste solution.

关键词： Europium Graphene oxide Aspergillus niger Phosphor radioactive waste Rare earths

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Combustion synthesis of radioactive waste immobilization

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Rare Metals 2005年第2期24卷 119-124页

作者： ZHANGRuizhu GUOZhimeng LUXin JIAChengchang LINTao MaterialsScienceandEngineeringSchool UniversityofScienceandTechnologyBeijingBeijing100083China MaterialsScienceandEngineeringSchool UniversityofScienceandTechnologyBeijingBeijing100083China／／NorthChinaInstituteofWaterConservancyandHydroelectricPowerZhengzhou450011China

Using chromium oxide (CrO3) as an oxidant, the immobilization of simulating radioactive waste in perovskite (CaTiO3) structure by a combustion synthesis (CS) method was tested. The products were characterized by Archimedes liquid displacement technique, microhardness technique, X-ray diffraction, and scanning electron microscopy. The leaching rate was measured by the method of MCC-1 or MCC-2. The primary results show that the CS method can be used to solidify the immobilizate waste effectively.

关键词： combustion synthesis radioactive waste Immobilization perovskite

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Implications of safety requirements for the treatment of THMC processes in geological disposal systems for radioactive waste

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Journal of Rock Mechanics and Geotechnical Engineering 2017年第3期9卷 46-52页

作者： Frédéric Bernier Frank Lemy Pierre De Cannière Valéry Detilleux Federal Agency for Nuclear Control (FANC) Brussels 1000 Belgium Bel V Brussels 1070 Belgium

The mission of nuclear safety authorities in national radioactive waste disposal programmes is to ensure that people and the environment are protected against the hazards of ionising radiations emitted by the *** implies the establishment of safety requirements and the oversight of the activities of the waste management organisation in charge of implementing the *** Belgium,the safety requirements for geological disposal rest on the following principles:defence-in-depth,demonstrability and the radiation protection principles elaborated by the International Commission on Radiological Protection(ICRP).Applying these principles requires notably an appropriate identification and characterisation of the processes upon which the safety functions fulfilled by the disposal system rely and of the processes that may affect the system ***,research and development(R&D)on safety-relevant thermo-hydro-mechanical-chemical(THMC)issues is important to build confidence in the safety *** paper points out the key THMC processes that might influence radionuclide transport in a disposal system and its surrounding environment,considering the dynamic nature of these *** nature and significance are expected to change according to prevailing internal and external conditions,which evolve from the repository construction phase to the whole heatingecooling cycle of decaying waste after *** these processes have a potential impact on safety,it is essential to identify and to understand them properly when developing a disposal concept to ensure compliance with relevant safety *** particular,the investigation of THMC processes is needed to manage *** includes the identification and characterisation of uncertainties as well as for the understanding of their safety-relevance.R&D may also be necessary to reduce uncertainties of which the magnitude does not allow demonstrating the safety of the disposal system.

关键词： radioactive waste Geological disposal Performance assessment Safety assessment Safety functions Safety requirements

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On the thermal impact on the excavation damaged zone around deep radioactive waste disposal

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Journal of Rock Mechanics and Geotechnical Engineering 2013年第3期5卷 179-190页

作者： P.Delage Ecole des ponts ParisTech Navier/CERMES

Clays and claystones are considered in some countries （including Belgium, France and Switzerland） as a potential host rock for high activity long lived radioactive waste disposal at great depth. One of the aspects to deal with when assessing the performance of the disposal is related to the effects of the temperature elevation due to the placement of exothermic wastes on the host rock. The potential effects of the thermal impact on the excavation damaged zone （EDZ） in the near field are another important issue that was the goal of the TIMODAZ European research project. In this paper, some principles of waste disposal in clayey host rocks at great depth are first presented and a series of experimental investigations carried out on specific equipment specially developed to face the problem are presented. Both drained and undrained tests have been carried out to investigate the drained thermal volume changes of clays and claystone and the thermal pressurization occurring around the galleries. The importance of proper initial saturation （under in situ stresses） and of satisfactory drainage conditions （in spite of the significantly low perme- ability of claystones） is emphasized, leading to the development of a new hollow cylinder apparatus. It is observed that claystones cannot be considered as overconsolidated clays given that they can exhibit, as the Callovo-Oxfordian claystone does, a thermoplastic contraction. Mechanical and thermal hardenings are however observed, extending the knowledge already gained on clays to claystones. A new method of determining the thermal pressurization coefficient in the laboratory is described and the data obtained allow completing existing data in the field. Finally, the hollow cylinder apparatus makes it possible to demonstrate that the good self-sealing properties of clays and claystones can be extended to temperature effects, an important conclusion in terms of performance assessment.

关键词： radioactive waste Thermal impact Hollow cylinder triaxial Thermal behaviour Thermal pressurization Clay Claystone

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Medium-Deep or Very Deep Disposal of Highly radioactive waste？

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Journal of Civil Engineering and Architecture 2013年第12期7卷 1548-1565页

作者： Roland Pusch Gunnar Ramqvist Sven Knutsson Mohammed Hatem Mohammed Department of Civil Environmental and Natural Resources Engineering Lulea University of Technology Lulea SE-971 87Sweden Eltekno AB Figeholm SE-57295 Sweden

Commonly proposed concepts, like KBS-3V, for disposal of highly radioactive waste imply construction at medium depth （400-600 m） in granitic rock, which is excellent for constructing a stable repository. VDH （very deep boreholes） represent an altemative concept with the advantage that the rock is much less permeable and that the very salt, heavy groundwater is stagnant. Both require engineered barriers in the form of canisters and waste-embedding clay but for somewhat different purposes. Canisters are the most important waste-isolating barriers for KBS-3V but are less important for VDH. The waste-embedding clay is needed for preserving the KBS-3V canisters by being tight and ductile, but plays a minor role for the VDH. The backfilled deposition tunnels in a KBS-3V repository provide very limited hindrance of radionuclides to move to the biosphere while the clay seals of VDH effectively prevent possibly released radionuclides to reach up to the biosphere. Comparison of the KBS-3V and VDH concepts indicates that the last mentioned one has several advantages but that certain issues remain to be worked on for becoming a number one candidate.

关键词： Canisters deep boreholes groundwater radioactive waste site selection super containers waste disposal

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Indonesia’s Local Material Effect in Clay-Based Ceramic Filter Fabrication as an Alternative for Liquid radioactive waste Processing Material

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Materials Sciences and Applications 2016年第7期7卷 371-379页

作者： Widya Rosita Ferdiansjah Antonius Wisnu Yogha Pamungkas Tri Joko Prihatin Department of Engineering Physics Universitas Gadjah Mada Yogyakarta Indonesia

One of the procedures to handle liquid radioactive waste is by filtration process. To do this process, suitable filter should be used because of radioactive nature of the waste. Ceramic filter is one of the suitable filters that could be used for this purpose. This paper will discuss about producing ceramic filter from local clay and test its performance. Performance of the filter is given by its flux, compressive strength, Decontamination Factor (DF) and adsorption efficiency. The results show that there are almost no effects of casting pressure on both flux and compressive strength of ceramic filter, but zeolite addition produces different effect. The higher concentration of zeolite will decrease the filter flux and increase filter compressive strength. The optimal composition from this research is 70% w/o clay-25% w/o zeolite-5% w/o charcoal. It has adsorption efficiency (60.36) and Decontamination Factor (2.52). Besides, Sr concentration after filtration is still higher than environmental standard for Sr-90 and more studies are still needed.

关键词： Local Clay Zeolite Charcoal Filter radioactive waste

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MANAGEMENT AND IMPROVEMENT OF radioactive waste IN DAYA BAY AND LING AO NUCLEAR POWER STATION

MANAGEMENT AND IMPROVEMENT OF RADIOACTIVE WASTE IN DAYA BAY ...

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第二届废物地下处置学术研讨会

作者： Huang Lai-xi (Daya Bay Nuclear Operations & Management Co. Ltd, Shenzhen of Guangdong prov.China)

This paper describes the main sources,types and treatment processes of radioactive waste from Guangdong Daya Bay Nuclear Power Station (GNPS) and Ling Ao Nuclear Power Station (LNPS).Several measures that can substantially reduce amount of waste are proposed through analysis of the main factors affecting production of *** measures have been proved to be feasible,effective and critical for reduction of radioactive waste during the maintenance activities from 2002 to 2007.

关键词： Nuclear power station radioactive waste Measures Development

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Activation and Environmental Aspects of In-Vacuum Vessel Components of CFETR

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Plasma Science and Technology 2016年第11期18卷 1130-1138页

作者： ZHANG Xiaokang LIU Songlin ZHU Qingjun GAO Fangfang LI Jia Institute of Plasma Physics Chinese Academy of SciencesHefei 230031China University of Science and Technology of China Hefei 230027China

The water-cooled ceramic breeder （WCCB） blanket is one of the three candidates of China＇s Fusion Engineering Test Reactor （CFETR）. The evaluation of the radioactivity and decay heat produced by neutrons for the in-vacuum vessel components is essential for the assessment of radioactive wastes and the safety of CFETR. The activation calculation of CFETR in-vacuum vessel components was carried out by using the Monte Carlo N-Particle Transport Code MCNP, IAEA Fusion Evaluated Nuclear Data Library FENDL2.1, and the nuclear inventory code FISPACT-2007 and corresponding EAF-2007 libraries. In these analyses, the three-dimensional （3-D） neutronics model was employed and the WCCB blanket, the divertor, and the shield were modeled in detail to provide the detailed spatial distribution of the neutron flux and energy spectra. Then the neutron flux, energy spectra and the materials specification were transferred to FISPACT for the activation calculation with an assumed irradiation scenario of CFETR. This paper presents the main results of the activation analysis to evaluate the radioactivity, the decay heat, the contact dose, and the waste classification of the radioactive materials. At the time of shutdown, the activity of the WCCB blanket is 1.88×1019 Bq and the specific activity, the decay heat and the contact dose rate are 1.7× 1013 Bq/kg, 3.05 MW, and 2.0 × 103 Sv/h respectively. After cooling for 100 years, 79% （4166.4 tons） radioactive wastes produced from the blanket, divertor, high temperature shield （HTS） and low temperature shield （LTS） need near surface disposal, while 21% （1112.3 tons） need geological disposal. According to results of the contact dose rate, all the components of the blanket, divertor, HTS and LTS could potentially be recycled after shutdown by using advanced remote handling equipment. In addition, the selection of Eurofer97 or RAFM for the divertor is better than that of SS316 because SS316 makes the activity of the divertor-body keep at a relativel

关键词： CFETR blanket activation radioactive waste

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Safety assessment methodology for a German high-level waste repository in clay formations

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Journal of Rock Mechanics and Geotechnical Engineering 2017年第5期9卷 856-876页

作者： M.Jobmann A.Bebiolka V.Burlaka P.Herold S.Jahn A.Lommerzheim J.MaBmann A.Meleshyn S.Mrugalla K.Reinhold A.Rübel L.Stark G.Ziefle DBE TECHNOLOGY GmbH Eschenstra 55 Peine D-31224 Germany Bundesanstalt für Geowissenschaften und Rohstoffe (BGR) Stilleweg 2 Hannover D-30655 Germany Gesellschaft fur Anlagen- und Reaktorsicherheit (GRS) gGmbH Theodor-Heuss-Stra 4 Braunschweig D-38122 Germany

In the ANSICHT project that was jointly carried out by DBE TECHNOLOGY Gmb H,BGR,and GRS g Gmb H,two generic geological site models were used to develop a first draft of a methodology to demonstrate the safety of a high-level waste(HLW) repository in argillaceous formations in Germany,taking into account the regulatory *** main results of the project are characterised by the developed repository concepts adapted to the geological *** specific quantifications of the integrity criteria and their exemplary application with calculational proofs were used to demonstrate the integrity of the host *** development of site-specific FEP(features,events,and processes) cataloges provided a complete system description for evaluation of the repository *** developed work flow of the demonstration concept illustrated the complete sequence of the safety proof in a transparent *** shows that various steps have to be performed,possibly iteratively,to provide a successful safety *** results form a useful tool in the pending search for a HLW repository site,especially when providing a basis for comparing safety analyses of different sites in Germany.

关键词： Clay radioactive waste Safety demonstration method Barrier integrity FEP(features events and processes) cataloge

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Experiments on thermo-hydro-mechanical behaviour of Opalinus Clay at Mont Terri rock laboratory, Switzerland

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Journal of Rock Mechanics and Geotechnical Engineering 2017年第3期9卷 120-128页

作者： Paul Bossart David Jaeggi Christophe Nussbaum Swiss Geological Survey at swisstopo Wabern Switzerland

Repositories for deep geological disposal of radioactive waste rely on multi-barrier systems to isolate waste from the biosphere.A multi-barrier system typically comprises the natural geological barrier provided by the repository host rock e in our case the Opalinus Clay e and an engineered barrier system(EBS).The Swiss repository concept for spent fuel and vitrified high-level waste(HLW)consists of waste canisters,which are emplaced horizontally in the middle of an emplacement gallery and are separated from the gallery wall by granular backfill material(GBM).We describe here a selection of five in-situ experiments where characteristic hydro-mechanical(HM)and thermo-hydro-mechanical(THM)processes have been *** first example is a coupled HM and mine-by test where the evolution of the excavation damaged zone(EDZ)was monitored around a gallery in the Opalinus Clay(ED-B experiment).Measurements of pore-water pressures and convergences due to stress redistribution during excavation highlighted the HM *** same measurements were subsequently carried out in a heater test(HE-D)where we were able to characterise the Opalinus Clay in terms of its THM *** yielded detailed data to better understand the THM behaviours of the granular backfill and the natural host *** a presentation of the Swiss concept for HLW storage,we designed three demonstration experiments that were subsequently implemented in the Mont Terri rock laboratory:(1)the engineered barrier(EB)experiment,(2)the in-situ heater test on key-THM processes and parameters(HE-E)experiment,and(3)the full-scale emplacement(FE)*** first demonstration experiment has been dismantled,but the last two ones are on-going.

关键词： Deep geological disposal radioactive waste Demonstration experiments Engineered barrier system(EBS) Granular backfill material(GBM) Bentonite Thermo-hydro-mechanical(THM) behaviour

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