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Duncan, R.; Cellier, F.
Westinghouse Electric Corp., Pittsburgh, Pa. (USA)1975
Westinghouse Electric Corp., Pittsburgh, Pa. (USA)1975
AbstractAbstract
[en] A fuel rod is positioned in axial alignment with a stationary set of cutters on a table and a winch on the other end of the table pulls the rod through the cutters and in so doing, cuts a groove almost through the opposite sides of the rod. As the machine continues pulling the rod, it is caused to spread open and drop fuel rod pellets into a receptacle for later disposition. (Patent Office Record)
Primary Subject
Secondary Subject
Source
9 Sep 1975; 15 p; CA PATENT DOCUMENT 974202; Available from Commissioner of Patents, Ottawa.
Record Type
Patent
Country of publication
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INIS VolumeINIS Volume
INIS IssueINIS Issue
Whatley, M.E.
Oak Ridge National Lab., Tenn. (USA)1977
Oak Ridge National Lab., Tenn. (USA)1977
AbstractAbstract
[en] To organize data being obtained in an existing experimental program on the dispersion coefficient for material in a rotating kiln, a dimensional analysis was performed using all of the variables now thought to be relevant. Rotary kilns are being considered for use in the voloxidation process for the recovery of tritium from spent nuclear power reactor fuels. Design for the efficient recovery of tritium stipulates a residence time distribution for material within the kiln; therefore, a consideration of material dispersion is important. The study revealed that the system is fairly tightly constrained. Of all possible dimensionless groups formed from the process variables, only three remained after those groups consisting of ratios of length were extracted and allowance was made for implicit relations among variables. The set that describes the system includes the velocity number, the Watt number, and the fraction of the kiln filled with solids. Since the velocity number divided by the operating slope of the kiln behaves as a constant (at least for first-order effects), the program should correlate the Watt number with fraction full and the dimensionless numbers that relate the geometry of the system, including size of the feed material and flight dimensions
Primary Subject
Source
Jul 1977; 18 p; Available from NTIS., PC A02/MF A01
Record Type
Report
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INIS IssueINIS Issue
Shin, Jin Myeong; Park, J. J.; Lee, J. W.; Lee, J. W.
Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)2010
Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)2010
AbstractAbstract
[en] Design of an engineering-scale trapping system to be used in PRIDE (Pyroprocess Integrated Inactive Demonstration) facility of KAERI to remove semi-volatile fission gases generated from the advanced vololoxdation process of 50 kg-SF/batch was performed. The design was performed to produce flow diagram for the off-gas trapping system. The gaseous waste arisings for off-gas trapping system was estimated considering the release rate of each target fission product. To design the off-gas trapping system, zero release concept was taken to the environment through off-gas trapping system. Each unit process in the trapping system is arranged to effectively remove the species of interest by considering the chemical properties of the target fission products to be trapped. Cs and Rb are trapped on a fly ash filter at around 900 .deg. C. Tc, Te, Se, and Mo on a calcium filter are trapped at about 700 .deg. C, and I on a AgX is trapped at about 250 .deg. C. Off-gas trapping system was designed based on the design requirements such as trapping media, fission products to be trapped, design temperatures of the trapping units, optimum operation temperatures and specifications of the filters. Off-gas trapping system was also designed based on the design requirements such as reomoteability, accessibility, operationability and flexibility of instrument, separability of trapping basket, material of instrument
Primary Subject
Source
Dec 2010; 38 p; Also available from KAERI; 7 refs, 16 figs, 9 tabs
Record Type
Report
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Reference NumberReference Number
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INIS IssueINIS Issue
AbstractAbstract
[en] The selection of mechanical dismantling and cutting methods instead of thermal cutting by grinding, for example, is a decision taken for reasons of radiological safety, in order to prevent entrainment of radioactivity. Radiological protection is one of the main reasons leading to application of mechanical methods for dismantling, as the thermal dismantling and thermal grinding methods produce dust and other debris that are a hazard to the personnel, not only due to the radioactivity. Mechanical dismantling work does not require protective means such as tents, hoods, or the like. (orig./DG)
[de]
Die Auswahl von mechanischer Demontage- bzw. Zerlegetechnik anstelle von thermischer Technik oder Zerlegetechnik mittels Trennschleifen ist bereits eine Entscheidung, die aus Strahlenschutzgruenden auf dem Hintergrund der Vermeidung von Kontaminationsverschleppung getroffen wurde. Dies ist einer der wesentlichen Gruende fuer die Anwendung der mechanischen Trenntechnik, denn thermische Verfahren und auch Trennschleifverfahren produzieren Staub und Dreck, die das Personal belasten - nicht nur radiologisch - und die Anlage verdrecken. Insofern sind bei der mechanischen Zerlegetechnik auch keine Schutzmassnahmen wie Einzelten, Maskentragen, usw. erforderlich. (orig./DG)Original Title
Mechanische Demontage- und Zerlegetechnik
Primary Subject
Source
Bundesministerium fuer Umwelt-, Naturschutz und Reaktorsicherheit, Bonn (Germany, F.R.); Veroeffentlichungen der Strahlenschutzkommission; v. 11; 223 p; ISBN 3-437-11238-4;
; 1988; p. 137-141; Fischer; Stuttgart (Germany, F.R.); Closed meeting of the Strahlenschutzkommission on radiation protection principles for management of solid radioactive waste; Gundremmingen (Germany, F.R.); 6-7 Nov 1986

Record Type
Book
Literature Type
Conference
Country of publication
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INIS IssueINIS Issue
Jubin, R.T.; Patton, B.D.; Ramey, D.W.; Spencer, B.B.
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] Full text of publication follows: ORNL is conducting a complete, coupled end-to-end (CETE) demonstration of advanced nuclear fuel reprocessing to support the Global Nuclear Energy Partnership (GNEP). These small scale reprocessing operations provide a unique opportunity to test integrated off-gas treatment systems designed to recover the primary volatile fission and activation products (3H, 14C, 85Kr, and 129I) released from the spent nuclear fuel (SNF). The CETE project will demonstrate an advanced head-end process referred to as 'Voloxidation' designed to condition the spent nuclear fuel, separate the SNF from the cladding, and release of tritium contained in the fuel matrix. The off-gas from this process as well as from the more traditional fuel dissolution process will be treated separately and the volatile components recovered. This paper will provide descriptions of the off-gas treatment systems for both the Voloxidation process and for the fuel dissolution process, and provide preliminary results from the initial CETE processing runs. Impacts of processing parameters on the relative quantities of volatile components released and recovery efficiencies will be evaluated. (authors)
Primary Subject
Source
2008; 1 p; Atalante 2008: Nuclear fuel cycle for a sustainable future; Montpellier (France); 19-23 May 2008; Available in abstract form only, full text entered in this record
Record Type
Miscellaneous
Literature Type
Conference
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Tucoulat, D.; Kerlau, D.; Colas, J.; Dubost, R.; Seyfried, P.
Societe Generale pour les Techniques Nouvelles (SGN), 78 - Saint-Quentin-en-Yvelines (France)1989
Societe Generale pour les Techniques Nouvelles (SGN), 78 - Saint-Quentin-en-Yvelines (France)1989
AbstractAbstract
[en] For reprocessing spent fuel elements are cut by series of 3 to 8 offset blades, distance between edges of parallelepipedic blades is equal to the thickness of the fuel element bundle
[fr]
En vue du retraitement on tronconne les tubes contenant le combustible irradie par une serie de 3 a 8 lames decalees, la distance entre les bords d'attaque des couteaux parallelepipediques etant egale a la largeur du faisceauOriginal Title
Dispositif de coupe pour cisaille a deplacement alternatif utilisee dans l'industrie nucleaire
Primary Subject
Source
15 Dec 1989; 9 Jun 1988; 6 p; FR PATENT DOCUMENT 2632764/A/; FR PATENT APPLICATION 8807711; Available from Institut National de la Propriete Industrielle, Paris (France); Application date: 9 Jun 1988
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Spilker, H.
Deutsche Gesellschaft fuer Wiederaufarbeitung von Kernbrennstoffen m.b.H. (DWK), Hannover (Germany, F.R.)1986
Deutsche Gesellschaft fuer Wiederaufarbeitung von Kernbrennstoffen m.b.H. (DWK), Hannover (Germany, F.R.)1986
AbstractAbstract
[en] After separation of the top piece and bottom piece, the spacer grid devices are progressively separated in layers from fuel rod level to fuel to fuel rod level and are removed from the fuel rods. The released fuel rods are then taken from the fuel element in layers and are placed in a more compact configuration. A separating tool with a separating disc head is used for separation. The release of the fuel rods is done using pliers, which bend the separated spacer grid open in steps. (orig./HP)
[de]
Nach Abtrennung des Kopfstueckes und des Fussstueckes werden lagenweise von Brennstabebene zu Brennstabebene fortschreitend die Abstandshaltergitteranordnung aufgetrennt und von den Brennstaeben entfernt. Danach werden die freigelegten Brennstaebe entsprechend lagenweise aus dem Brennelement aufgenommen und in eine kompaktere Konfiguration umgesetzt. Zum Auftrennen dient ein Trennwerkzeug mit einem Trennscheibenkopf. Das Freilegen der Brennstaebe erfolgt mit Hilfe einer Greifzange, die schrittweise das aufgetrennte Abstandshaltergitter aufbiegt. (orig./HP)Original Title
Verfahren und Vorrichtung zur Vereinzelung von Brennstaeben eines Brennelementes
Primary Subject
Secondary Subject
Source
21 Aug 1986; 15 Feb 1985; 7 p; DE PATENT DOCUMENT 3505242/A1/; ?: 15 Feb 1985
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
John, C.D. Jr.
Westinghouse Electric Corp., Pittsburgh, PA (USA)1977
Westinghouse Electric Corp., Pittsburgh, PA (USA)1977
AbstractAbstract
[en] This invention concerns an apparatus and process for recovering fuel pellets from nuclear fuel elements containing them. The main object of the invention is to provide a simple apparatus for easily removing fuel pellets from their cladding without damaging them. An opening is created in one end of the fuel element, a liquid at high pressure is introduced into the cladding by this aperture in order to place the fuel element under pressure and bring about the expansion of the metal cladding to clear the fuel pellets it contains. This cladding is then cut up to allow the fuel pellets to slide from the cladding
[fr]
La presente invention est relative a un appareil et a un procede pour la recuperation de comprimes de combustible au depart d'elements combustibles nucleaires qui les contiennent. Le but principal de l'invention est de prevoir un appareil simple permettant l'enlevement facile des comprimes de combustible hors de leur gaine, et ce sans abimer ces comprimes. Une ouverture est formee dans une extremite de l'element combustible, un liquide a haute pression est introduit dans la gaine par cette ouverture pour mettre ainsi interieurement sous pression l'element combustible et provoquer la dilatation de la gaine metallique a l'ecart des comprimes de combustible qu'elle contient, cette gaine etant decoupee pour permettre aux comprimes de combustible de glisser hors de cette gaineOriginal Title
Procede et appareil pour la recuperation de comprimes de combustible au depart d'elements combustibles nucleaires
Primary Subject
Source
12 Dec 1977; 14 p; FR PATENT DOCUMENT 2373859/A/; Available from Institut National de la Propriete Industrielle, Paris (France); Priority claim: 13 Dec 1976, US.
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Shin, Jin Myeong; Park, J. J.; Park, G. I.; Song, K. C.; Kim, J. H.; Lee, H. H.
Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)2007
Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)2007
AbstractAbstract
[en] The objective of this report is to develop the trapping concepts for immobilizing the volatiles from voloxidation process. KAERI supplied fly ash filters for cesium, calcium filters for ruthenium and technetium, and AgX for I to INL. Based on KAERI's experimental results and experience on the trapping characteristics of each gaseous fission product in terms of carrier gas and chemical species, INL hot experiments will be performed in off-gas treatment system (OTS) for a voloxidizer. This report will be used as useful means for providing the trapping methods for trapping semi-volatile fission products under air, oxygen, and vacuum conditions. As results of trapping experiments, it was found that trapping efficiency of cesium volatilized from CsI by fly ash filter was decreased in the order of Air> Ar > O2 > vacuum conditions. It was also found that higher trapping temperature, close to 1100 .deg. C, tends to give an improved trapping efficiency even at vacuum condition
Primary Subject
Source
Jun 2007; 48 p; Also available from KAERI; 2 refs, 37 figs, 10 tabs
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Report
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Park, Hee Seong; Lee, Jae Won; Park, Seung Kook; Moon, Jei kwon
Proceedings of the KNS 2014 spring meeting2014
Proceedings of the KNS 2014 spring meeting2014
AbstractAbstract
[en] The head-end process plays an important role in providing feed materials to electrolytic reduction after fabrication of the fuel fragments (crushed pellets) and the porous pellets feed materials. The head-end process is composed of various devices such as disassembling/rod extraction/rod cutting devices of the nuclear fuel assembly, oxidative decladding device, compaction, and pre-treatment device. The head-end process project currently has no hotcell. In addition, there are no tools validate core devices designed or manufactured. This paper introduces a head-end process fDMU (Functional DMU) being developed to solve this problem. To establish the efficiency and reliability of core devices based on a previous DMU environment, an advanced fDMU for the head-end process was designed. It was concluded that fDMU has great features such as a functional integration and validation of virtual mechatronic systems, couple the functional and geometry models within the total system model, and combine the functional simulation and interactive 3D visualization
Primary Subject
Secondary Subject
Source
Korean Nuclear Society, Daejeon (Korea, Republic of); [1 CD-ROM]; May 2014; [2 p.]; 2014 spring meeting of the KNS; Jeju (Korea, Republic of); 28-30 May 2014; Available from KNS, Daejeon (KR); 2 refs, 3 figs
Record Type
Miscellaneous
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Conference
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