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Desmouliere, F.; Leorier, C.; Donnet, L.; Vaudez, S.; Bonnerot, J.M.
CEA Marcoule, DEN/UCCAP, BP 17171, F-30207 Bagnols-sur-Ceze cedex (France)2008
CEA Marcoule, DEN/UCCAP, BP 17171, F-30207 Bagnols-sur-Ceze cedex (France)2008
AbstractAbstract
[en] Transmutation of highly active long-lived nuclides into shorter life nuclides is a promising option for the reduction of the nuclear waste radiotoxicity. Previous irradiation experiments which were carried out on 241Am bearing spinel targets have shown a significant volume swelling that results from helium production. As a consequence, the helium release and trapping is considered as a key parameter for fuels and targets design. In this way, HELIOS irradiation experiment aims to increase knowledge between microstructure and in pile fuel behaviour for minor actinides transmutations in heterogeneous mode: 'once through'. For this program, five pins containing either Am based cercer or cermet (solid solution) were prepared. The Cea was responsible for fabricating the pin containing Am2Zr2O7 pyrochlore in a MgO matrix which was chosen for its satisfying thermal property and irradiation behaviour. Research, development and fabrication steps carried out in Cadarache and Atalante facility to achieve the compound preparation are described in this paper. The first results on the obtained pyrochlore show that the materials exhibit the expected properties. (authors)
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2008; 4 p; Atalante 2008: Nuclear fuel cycle for a sustainable future; Montpellier (France); 19-23 May 2008; 3 refs.
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AbstractAbstract
[en] The paper presents the optimal conditions for radiochemical separation of 241Am from environmental samples.
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Journal Article
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Journal of Radiation Researches; ISSN 2312-3001;
; v. 5(2); p. 263-264

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AbstractAbstract
[en] The γ spectrum of 241Am was reinvestigated using Ge(Li) detectors. 115 photons were found in this study, 46 of them for the first time
[fr]
Le spectre γ qui accompagne la decroissance de 241Am a ete remesure au moyen de detecteurs Ge(Li). 115 photons ont pu etre observes dans cette etude, 46 d'entre eux le sont pour la premiere foisOriginal Title
Nouvelles transitions electromagnetiques dans le noyau 237Np formees par decroissance α de 241Am
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Journal Article
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Comptes Rendus Hebdomadaires des Seances de l'Academie des Sciences. Serie B; v. 287(1); p. 13-16
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AbstractAbstract
[en] Objective: To study the influence of crosstalk phenomenon on the measurement of gross radioactivity in drinking water. Methods: The gross activity in different standard materials with different thickness and area was measured using national standard method. Results: There was no obvious change in crosstalk factor with the increase of "2"4"1Am powder amount in the measurement, whereas the larger amount of uranium used might lead to larger crosstalk factor. The different measurement channels resulted in different crosstalk factors. The influence of beta radioactivity on alpha radioactivity measurement was significant. On the contrary, the alpha-to-beta crosstalk factor was negligible. The area of sample plate imposed no significant influence on crosstalk factor. Conclusions: The gross beta activity can be corrected to decrease the influence of alpha radioactivity using powder standard samples, when simultaneous alpha and beta counting mode is applied in measurement grass radioactivity in drinking water. (authors)
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2 figs., 2 tabs., 8 refs.; http://dx.doi.org/10.3760/cma.j.issn.0254-5098.2014.10.016
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Journal Article
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Chinese Journal of Radiological Medicine and Protection; ISSN 0254-5098;
; v. 34(10); p. 780-782

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Emswiler, T.R.
Battelle Columbus Labs., OH (USA)1985
Battelle Columbus Labs., OH (USA)1985
AbstractAbstract
[en] Phase I consisted of the primary decontamination, packaging, and shipment of all 241Am-contaminated gloveboxes, vent system, and miscellaneous waste items located in the laboratory restricted area in the J.C. Haynes house. The primary goals of Phase I were to locate and account for a major quantity of 241Am which was unaccounted for and to remove all radioactive materials and contamination posing an imminent hazard to public health and safety. All Phase I operations were conducted under a Quality Assurance (QA) Program Plan and QA procedures written specifically for this program. In addition, certain generic Battelle QA procedures were used for routine tasks. All operations were conducted under strict health physics supervision and procedures. Cognizant ORAU and US Nuclear Regulatory Commission (NRC) personnel were on site during the entire Phase I operation and provided support and approval in the daily operations. All staff members had participated in previous decontamination and decommissioning programs involving transuranic waste and completed Phase I in a well controlled, timely, and safe manner
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Nov 1985; 152 p; Available from NTIS, PC A08/MF A01; 1 as DE86004518; Portions of this document are illegible in microfiche products. Original copy available until stock is exhausted.
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Konings, R.J.M.; Conrad, R.; Dassel, G.; Pijlgroms, B.J.; Somers, J.; Toscano, E., E-mail: konings@itu.fzk.de2000
AbstractAbstract
[en] In the EFTTRA-T4 experiment the irradiation behaviour of a target containing americium dispersed in MgAl2O4 was studied. Pellets containing 10-12 wt% 241Am were fabricated by the infiltration method. However, it was found that the americium, intended to be present as AmO2-x, formed a compound, probably AmAlO3, during sintering. The T4 target was irradiated in the High Flux Reactor (HFR) Petten from August 1996 to January 1998 (358.4 fpd's). Post-test burn-up calculations indicated that the 241Am concentration is reduced to 4% of the initial value at the end of the irradiation. The fraction of the initial americium atoms that were fissioned is 28%. Non-destructive and destructive examinations of the target indicated that swelling of the target pellets occurred. This is attributed to accumulation of helium, produced by alpha decay of 242Cm that occurs in the transmutation scheme of 241Am
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S0022311500004116; Copyright (c) 2000 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.; Country of input: International Atomic Energy Agency (IAEA)
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ACTINIDE COMPOUNDS, ACTINIDE NUCLEI, ALPHA DECAY RADIOISOTOPES, AMERICIUM ISOTOPES, DEFORMATION, ELEMENTS, FLUIDS, GASES, HEAVY NUCLEI, ISOTOPES, NONMETALS, NUCLEI, ODD-EVEN NUCLEI, RADIATION EFFECTS, RADIOISOTOPES, RARE GASES, SPONTANEOUS FISSION RADIOISOTOPES, TARGETS, TRANSPLUTONIUM COMPOUNDS, TRANSURANIUM COMPOUNDS, YEARS LIVING RADIOISOTOPES
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Rozhko, A.T.; Bondareva, L.G.; Kudryasheva, N.S.; Vydryakova, G.A.
Proceedings of 15th International Conference on Heavy Metals in the Environment2010
Proceedings of 15th International Conference on Heavy Metals in the Environment2010
AbstractAbstract
No abstract available
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Source
Barganska, Z.; Beyer, A; Klimaszewska, K.; Namiesnik, J.; Tobiszewski, M.; Rutkiewicz, I. (Department of Analytical Chemistry, Chemical Faculty, Gdansk University of Technology - GUT, Gdansk (Poland)); Department of Analytical Chemistry, Chemical Faculty, Gdansk University of Technology, Gdansk (Poland); 1071 p; ISBN 978-83-928986-5-8;
; 2010; p. 84; 15. International Conference on Heavy Metals in the Environment; Gdansk (Poland); 19-23 Sep 2010; Also available from Department of Analytical Chemistry, Chemical Faculty, Gdansk University of Technology - GUT, Gdansk

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AbstractAbstract
[en] Two gamma spectra in the 1MeV region, from 241Am decay, were recorded, four gamma peaks supporting a 989.5keV, 9/2-[505] 237Np level
[fr]
On a enregistre deux spectres gamma dans la region du MeV, provenant de la desintegration de 241Am, quatre raies gamma appuient l'existence d'un niveau 9/2-[505] du 237Np a 989,5keVOriginal Title
Spectrometrie gamma au voisinage de 1MeV de 237Np* forme par desintegration alpha de 241Am
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CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Dept. de Physique Nucleaire; p. 54; nd
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Progress Report
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AbstractAbstract
No abstract available
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Israel Atomic Energy Commission, Tel Aviv; p. 246-247; Jul 1982; p. 246-247; Published in summary form only.
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Bondareva, L.; Vlasova, I.; Mogilnaya, O.; Bolsunovsky, A.; Kalmykov, S., E-mail: lydiabondareva@gmail.com2010
AbstractAbstract
[en] A submerged macrophyte of the Yenisei River, Elodea canadensis, was used to study the microdistribution of the artificial radionuclide 241Am among different components of the plant. The total amount of 241Am added to the experimental system was 1850 ± 31 Bq/L. The total amount of 241Am accumulated by the plants was 182 Bq per sample, or 758,333 ± 385 Bq/kg dry mass. It has been found that the major portion of 241Am accumulated by E. canadensis, up to 85%, was bound to solid components of the cells. It is observed that the microdistribution of 241Am within different components of the submerged plant E. canadensis was not uniform. 241Am distribution vary depending on the age of the leaf blades, the state of the cells and morphological features of the plant stem.
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S0265-931X(09)00176-3; Available from http://dx.doi.org/10.1016/j.jenvrad.2009.08.003; Copyright (c) 2009 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.; Country of input: International Atomic Energy Agency (IAEA)
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