Fuel desorption from JET-ILW materials: assessment of analytical approach and identification of sources of uncertainty and discrepancy

Nuclear Fushion

article

Y. Zayachuk¹  I. Jepu¹  M. Zlobinski³  C. Porosnicu²  N. Catarino⁴  E. Pajuste⁵  P. Petersson⁶  L. Dittrich⁶  J.P. Coad¹  E. Grigore²  C. Postolache⁷  E. Alves⁴  G. Kizane⁵  M. Rubel⁶  A. Widdowson¹ 

[1] United Kingdom Atomic Energy Authority, Culham Centre for Fusion Energy, Culham Science Centre;National Institute for Laser;Forschungszentrum Jülich GmbH, Institut für Energie- und Klimaforschung—Plasmaphysik;IPFN, Instituto Superior Técnico, Universidade de Lisboa;University of Latvia, Institute of Chemical Physics;KTH Royal Institute of Technology;National Institute for Physics and Nuclear Engineering

关键词: fuel retention;    thermal desorption;    dissolution;    JET-ILW;   

DOI  :  10.1088/1741-4326/ace2d2

来源: Institute of Physics Publishing Ltd.

【 摘 要 】

This work was carried out to identify sources of errors, uncertainties and discrepancies in studies of fuel retention in wall components from the JET tokamak using methods based on thermal desorption. Parallel aims were to establish good practices in measurements and to unify procedures in data handling. A comprehensive program designed for deuterium quantification comprised the definition and preparation of two types of materials (samples of JET limiter Be tiles and deuterium-containing targets produced in the laboratory by magnetron-assisted deposition), their pre-characterization, quantitative analyses of the desorption products in three different thermal desorption spectroscopy systems and a detailed critical comparison of the results. Tritium levels were also determined by several techniques in samples from JET and in tritiated targets manufactured specifically for this research program. Facilities available for studies of Be- and tritium-contaminated materials from JET are presented. Apparatus development, future research options and challenges are discussed.

【 授权许可】

Unknown