Development of a high temperature treatment device for spent nuclear fuel
Autor: | Natalia Shcherbina, Ines Günther-Leopold, Niko Kivel |
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Jazyk: | angličtina |
Rok vydání: | 2018 |
Předmět: |
Fission products
Nuclear transmutation Hydrogen Chemistry 020209 energy Health Toxicology and Mutagenesis Nuclear engineering Radiochemistry Public Health Environmental and Occupational Health chemistry.chemical_element 02 engineering and technology Actinide 021001 nanoscience & nanotechnology 7. Clean energy Pollution Spent nuclear fuel Analytical Chemistry Nuclear Energy and Engineering Caesium 0202 electrical engineering electronic engineering information engineering Radiology Nuclear Medicine and imaging Inductively coupled plasma 0210 nano-technology Inductively coupled plasma mass spectrometry Spectroscopy |
Popis: | Novel reprocessing schemes and techniques are the focus of the Euratom FP7 project “Actinide Recycling for Separation and Transmutation” (ACSEPT), where the Paul Scherrer Institute (PSI) is represented in the pyrochemical domain. The subject of investigation is the selective separation of fission products (FPs) from spent nuclear fuel as a head-end step to either classical hydro based or pyro processes which are not yet applied on a large scale. The selective removal of FPs that are major contributors to the overall radiation dose or bear great potentials in terms of radiotoxicity (i.e. cesium or iodine), is advantageous for further processes. At PSI a device was developed to release volatile FPs by means of inductive heating. The heating up to 2,300 °C promotes the release of material that is further transported by a carrier gas stream into an inductively coupled plasma mass spectrometer for online detection. The carrier gas can be either inert (Ar) or can contain reducing or oxidizing components like hydrogen or oxygen, respectively. The development of the device by computer aided engineering approaches, the commissioning and evaluation of the device and data from first release experiments on a simulated fuel matrix are discussed. |
Databáze: | OpenAIRE |
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