• 제목/요약/키워드: Nuclear material

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THE JHR, A NEW MATERIAL TESTING REACTOR IN EUROPE

  • Iracane Daniel
    • Nuclear Engineering and Technology
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    • v.38 no.5
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    • pp.437-442
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    • 2006

  • European Material Test Reactors (MTRs) have provided essential support for nuclear power programs over the last 40 years. MTRs are now ageing in Europe and they cannot ensure the securing of experimental capability for the next decades. In this context, a new Material Testing Reactor, named Jules Horowitz Reactor -JHR-, operated as an international user-facility, is under development in Europe. The European MTRs context and the JHR objectives and status will be presented. Emphasis will be put on experiments in the field of nuclear fuels and materials irradiation which are developed in the framework of European and international collaboration.

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Proposal of a prototype plant based on the exfoliation process for the treatment of irradiated graphite

  • Pozzetto, Silvia;Capone, Mauro;Cherubini, Nadia;Cozzella, Maria Letizia;Dodaro, Alessandro;Guidi, Giambattista
    • Nuclear Engineering and Technology
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    • v.52 no.4
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    • pp.797-801
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    • 2020

  • Most of irradiated graphite that should be disposed comes from moderators and reflectors of nuclear power plants. The quantity of irradiated graphite could be higher in the future if high-temperature reactors (HTRs) will be deployed. In this case noteworthy quantities of fuel pebbles containing semi-graphitic carbonaceous material should be added to the already existing 250,000 tons of irradiated graphite. Industry graphite is largely used in industrial applications for its high thermal and electrical conductivity and thermal and chemical resistance, making it a valuable material. Irradiated graphite constitutes a waste management challenge owing to the presence of long-lived radionuclides, such as 14C and 36Cl. In the ENEA Nuclear Material Characterization Laboratory it has been successfully designed a procedure based on the exfoliation process organic solvent assisted, with the purpose of investigate the possibility of achieving graphite significantly less toxic that could be recycled for other purpose [1]. The objective of this paper is to evaluate the possibility of the scalability from laboratory to industrial dimensions of the exfoliation process and provide the prototype of a chemical plant for the treatment of irradiated graphite.

  • https://doi.org/10.1016/j.net.2019.09.006 인용 PDF KSCI