Zobrazeno 1 - 9
of 9
pro vyhledávání: '"J L, Gascón"'
Autor:
J A, Suárez-Navarro, V M, Expósito-Suárez, M T, Crespo, B, Sánchez-Castaño, M J, Suárez-Navarro, C, Gascó, M, Barragán, J L, Gascón, R, Pecker, L, Sánchez-Pérez, L, González-Cano, A, Rosario
Publikováno v:
Applied radiation and isotopes : including data, instrumentation and methods for use in agriculture, industry and medicine. 187
The aim of this work was to improve the commonly used method for
Autor:
J. L. Gascón, A. Muñoz
Publikováno v:
Journal of Radioanalytical and Nuclear Chemistry. 257:371-374
In radiochemical analysis, specially by using high resolution alpha-spectrometry, a key issue is the determination of the radiochemical yield. Radiochemical yield allows to determine the concentration of the radionuclide of interest and the quality o
Autor:
M. Rodríguez, J. L. Gascón
Publikováno v:
Radiochimica Acta. 90:7-11
Summary The characterisation of alpha-emitting nuclides in low and medium level radioactive waste from Spanish nuclear power reactors leads to several difficulties because they cannot be assayed by non-destructive methods due to their low concentrati
Autor:
H. Wershofen, J. L. Gascón, Y. Bourlat, M. Magnoni, M.J. Woods, Michael Youngman, D. Andrew, J. Desmond, G. Sutton, P. De Felice, Aldo Fazio, D. S. Popplewell, R. S. Grieve, R. Bojanowski, A. R. Byrne, Dirk Arnold, K. J. Odell, Simon Jerome, I. Adsley, A. S. Holmes, M.T. Crespo, I. Poupaki, M. W. Wakerley, J. Toole, M. Korun
Publikováno v:
Applied Radiation and Isotopes. 49:1295-1300
The characterisation of an intertidal sediment, containing enhanced levels of radioactivity, collected from the Cumbrian coast of the U.K. by the Laboratory of the Government Chemist for the Department of the Environment is described. A wide variety
Publikováno v:
Talanta. 45:181-187
This paper describes the experimental studies carried out to determine 238 Pu, 239/40 Pu, 241 Pu, 241 Am, 242 Cm and 244 Cm in samples from nuclear power plants (mainly spent ion exchange resins and evaporator concentrates) using an organophosphorus
Publikováno v:
Journal of Radioanalytical and Nuclear Chemistry Articles. 207:63-69
The determination of Am and Cm in typical waste streams from nuclear power plants using anion exchange chromatography has some drawbacks like the contamination by Pu and Po. This improved procedure solves these problems, and it has been applied with
Autor:
J. L. Gascón
Publikováno v:
Journal of Radioanalytical and Nuclear Chemistry. 252:175-177
In radiochemical analysis, the storage of a tracer solution is an important issue to bear in mind. The evaporation of the tracer solution depends on the type of container used for storing. In this paper the evaporation rate in four kinds of container
Publikováno v:
Journal of Alloys and Compounds. :557-559
Accurate and reliable analytical methods have been developed for the measurement of Pu, Am and Cm in typical waste streams from nuclear power plants. Pu, Am and Cm were separated using anion exchange and coprecipitation techniques. The solution of Am
Publikováno v:
The Environmental Challenges of Nuclear Disarmament ISBN: 9780792362036
Low- and medium-level nuclear wastes are generated mainly in the operation of nuclear power plants. The radiological characterisation of these wastes is required during their treatment and conditioning as well as during their storage as a final produ
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7e6954859ef2141e5fba96856f31e819
https://doi.org/10.1007/978-94-011-4104-8_25
https://doi.org/10.1007/978-94-011-4104-8_25