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Avenhaus, R; Spannagel, G.
Los Alamos National Lab., NM (USA)
Los Alamos National Lab., NM (USA)
AbstractAbstract
[en] Monitoring and control of complex processes as encountered primarily in modern industry, today require operators of above-average experience and ability. In the interest of a secure and continuous operation it is thus necessary to seek methods which will support a process control so that the operator can recognize the reasons for malfunctions as quickly as possible. Regardless of whether the particular problems are encountered in every technical process, in the present report process steps for the planned reprocessing plant are considered. Besides the control of such a plant, a monitoring of the core material is necessary to maintain a control of the movement of fissionable materials. The test methods described also apply to this problem. 5 references, 4 figures
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Source
nd; 13 p; Translated from KFK-Nachr.; 14: 193-197(1982).
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Report
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AbstractAbstract
No abstract available
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Source
18. annual American Nuclear Society conference; Las Vegas, Nev; 18 Jun 1972; Published in summary form only.
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Journal Article
Literature Type
Conference
Journal
Trans. Amer. Nucl. Soc; v. 15(1); p. 96-97
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AbstractAbstract
No abstract available
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8 Mar 1972; 2 p
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Report
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AbstractAbstract
[en] The evoluation of a catalogue of incidents of the SRL-study showed that all mentioned events are included in the PSE-investigations. For media supply facilities such as cooling water, heating water, process steam, compressed air, sampling, acid recuperation the possible incidents are not very likely (e.g. failure of the cooling systems, entrainment of activity into the media circuits) and the quantities of released activity are low. (DG)
[de]
Durch Auswertung eines Stoerfallkataloges der SRL-Studie wurde gezeigt, dass alle genannten Ereignisse im Rahmen der PSE-Arbeiten beruecksichtigt sind. Fuer Medienversorgungseinrichtungen wie Kuehlwasser, Heizwasser, Prozessdampf, Druckluft, Probenahme, Saeurerueckgewinnung sind die moeglichen Stoerfaelle sehr unwahrscheinlich (z.B. Ausfall der Kuehlsysteme, Aktivitaetsverschleppung in die Medienkreislaeufe) und die freigesetzten Mengen gering. (DG)Original Title
Vereinfachte Betrachtungen zur Sicherheit einer Wiederaufarbeitungsanlage
Primary Subject
Source
Hahn-Meitner-Institut fuer Kernforschung Berlin G.m.b.H. (Germany, F.R.). Projekt Sicherheitsstudien Entsorgung (PSE); 94 p; Mar 1983; p. 50-62
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Miscellaneous
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Smith, J.G.
Technical Information Center (AEC), Oak Ridge, Tenn1972
Technical Information Center (AEC), Oak Ridge, Tenn1972
AbstractAbstract
No abstract available
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Source
14 Jan 1972; 12 p
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Report
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AbstractAbstract
No abstract available
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Source
18. annual American Nuclear Society conference; Las Vegas, Nev; 18 Jun 1972; Published in summary form only.
Record Type
Journal Article
Literature Type
Conference
Journal
Trans. Amer. Nucl. Soc; v. 15(1); p. 94-95
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Hayashi, S.; Araya, S.; Tanaka, I.
Proceedings of the specialist meeting on decommissioning requirements in the design of nuclear facilities, Paris, 17-19 March 19801980
Proceedings of the specialist meeting on decommissioning requirements in the design of nuclear facilities, Paris, 17-19 March 19801980
AbstractAbstract
[en] Replacement of the failed Acid Recovery Evaporator was completed in October 1979. Before dismantling of the evaporator, the equipment and pipes in acid recovery cell were decontaminated with HNO3-NaOH, and subsequently with alkaline KMnO4-HNO3-EDTA. Dismantling of the evaporator was conducted for about 3 months with about 9 thousand man-days. The evaporator, cut into 7 pieces, was taken out from the cell, put in stainless steel containers and stored on the site. Our view obtained through above practice is presented for review of the designers of nuclear facilities
Primary Subject
Source
Nuclear Energy Agency, 75 - Paris (France); 296 p; ISBN 92-64-02099-3; 
; 1980; p. 177-185; OECD; Paris, France; NEA specialist meeting on decommissioning requirements in the design of nuclear facilities; Paris, France; 17 - 19 Mar 1980
; 1980; p. 177-185; OECD; Paris, France; NEA specialist meeting on decommissioning requirements in the design of nuclear facilities; Paris, France; 17 - 19 Mar 1980
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Book
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Conference
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AbstractAbstract
[en] The reqiurements to be met by the valves concerning choice of materials, design, construction, calculation, manufacturing, and testing are determined by the type of fluid, its radioactivity, operational pressure and temperature. Demands resulting from the radioactivity of the fluid lead to the following objectives in normal operation and in case of accident: 1) There must not be any excessive activity release to the environment 2) The radiation exposure of the personnel must be below the permissible limits, as low as possible. For better and safe interchangeability, flanges are on principle to be used rather than welds. This may be unnecessary if wear parts within the valves can easily be replaced. Valves that are likely to be contaminated are to be provided with extra containments (e.g. boxes, glove boxes, no-access rooms). The classification of components, depending on the ease of access and maintenance, is done by the plant designer. The categories of service requirements defined herein apply. (orig./HP)
[de]
Die Anforderungen an Armaturen bezueglich Werkstoffauswahl, Auslegung, Konstruktion, Berechnung, Fertigung und Pruefung richten sich nach der Art des Fluids, dessen Radioaktivitaet sowie dessen Betriebsdruck und -temperatur. Die Anforderungen, die aus der Radioaktivitaet des Fluids resultieren, fuehren zu der Zielsetzung, dass im bestimmungsgemaessen Betrieb und bei Stoerfaellen 1) keine unzulaessige Aktivitaetsfreisetzung in die Umgebung erfolgen darf, 2) die Strahlenexposition des Personals unterhalb der zulaessigen Grenzen moeglichst gering gehalten wird. Um eine schnelle und sichere Austauschbarkeit sicherzustellen, sind Flanschverbindungen grundsaetzlich Schweissverbindungen vorzuziehen. Dies kann entfallen, wenn die Verschleissteile innerhalb der Armatur leicht austauschbar sind. Fuer Armaturen, bei denen mit hoher Kontamination gerechnet werden muss, sind zusaetzliche Umschliessungen (z.B. Boxen, Handschuhkaesten, abgeschlossener Raum) vorzusehen. Die Einstufung der Komponenten, abhaengig von der Zugaenglichkeit und Instandhaltbarkeit, erfolgt durch den Anlagenplaner in die hier definierten Anforderungsklassen. (orig./HP)Original Title
Komponenten fuer nukleare Wiederaufarbeitungs-, Ver- und Entsorgungsanlagen
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Source
Dec 1983; 35 p; Beuth; Berlin (Germany, F.R.); DIN--25461(PT.1)
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Book
Literature Type
Standard
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AbstractAbstract
No abstract available
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20 Jan 1972; 9 p
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Report
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AbstractAbstract
[en] This paper summarises in tabular form the main specifications of the base case reprocessing plant, together with those of the national reference case plants contributed by France, Federal Republic of Germany, India, Japan and the United Kingdom
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Secondary Subject
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Sep 1979; 4 p
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Report
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