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AbstractAbstract
[en] The decommissioning and dismantling of the german pilot plant for reprocessing of nuclear fuel (WAK) is performed in six steps with the task of recultivation the site at the Research Centre in Karlsruhe to became a open-quotes green meadowclose quotes. Since 70 m3 of high active waste concentrate (HAWC) are still stored on the site presently all dismantling measures arc concentrated on the former reprocessing building
Primary Subject
Source
Anon; 843 p; 1996; p. 1765-1768; American Nuclear Society, Inc; La Grange Park, IL (United States); SPECTRUM '96: international conference on nuclear and hazardous waste management; Seattle, WA (United States); 18-23 Aug 1996; American Nuclear Society, Inc., 555 N. Kensington Avenue, La Grange Park, IL 60526 (United States)
Record Type
Book
Literature Type
Conference
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INIS VolumeINIS Volume
INIS IssueINIS Issue
Kuhn, K.D.; Willax, H.O.
Wiederaufbereitungsanlage Karlsruhe Betriebsgesellschaft mbH (WAK), Eggenstein-Leopoldshafen (Germany, F.R.)1986
Wiederaufbereitungsanlage Karlsruhe Betriebsgesellschaft mbH (WAK), Eggenstein-Leopoldshafen (Germany, F.R.)1986
AbstractAbstract
[en] After a short description of the WAK plant and its reprocessing and intervention activities, types and sources of WAK wastes are described. Roughly half of the waste volume is generated during reprocessing, the other half during intervention periods. Most of the waste is transported to KfK for conditioning. Only waste from the head end cell is cementated on the spot. HLLW is stored in stainless steel tanks. Some results from analyzing this stuff are given. The corrosion behavior is acceptable for medium term storage. (orig.)
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Secondary Subject
Source
1986; 10 p
Record Type
Miscellaneous
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AbstractAbstract
No abstract available
Original Title
Bekanntmachung ueber die Auslegung von fuenf atomrechtlichen Teilgenehmigungen fuer die Wiederaufarbeitungsanlage Karlsruhe (WAK)
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Secondary Subject
Source
Short communication only.
Record Type
Journal Article
Journal
Bundesanzeiger; v. 27(219); p. 6
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INIS IssueINIS Issue
AbstractAbstract
No abstract available
Original Title
Bekanntmachung ueber die Erteilung einer atomrechtlichen Genehmigung. Genehmigung zur Vornahme von Aenderungen an der Wiederaufarbeitungsanlage Karlsruhe
Primary Subject
Source
Published in summary form only.; CODEN: BDZRA.
Record Type
Journal Article
Journal
Bundesanzeiger; ISSN 0344-7634;
; v. 36(114); p. 5990

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INIS IssueINIS Issue
AbstractAbstract
No abstract available
Original Title
Bekanntmachung ueber die Erteilung einer Atomrechtlichen Genehmigung zur Vornahme von Aenderungen in der Wiederaufarbeitungsanlage Karlsruhe
Primary Subject
Secondary Subject
Source
Published in summary form only.; CODEN: BDZRA.
Record Type
Journal Article
Journal
Bundesanzeiger; ISSN 0344-7634;
; v. 37(10); p. 445

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INIS IssueINIS Issue
AbstractAbstract
[en] Short communication
Original Title
Bekanntmachung ueber die Erteilung einer atomrechtlichen Genehmigung fuer die Stillegung in der Wiederaufarbeitungsanlage Karlsruhe
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Secondary Subject
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Journal Article
Journal
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Reference NumberReference Number
INIS VolumeINIS Volume
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AbstractAbstract
No abstract available
Original Title
Bekanntmachung ueber die Erteilung einer Atomrechtlichen Genehmigung. 4. Nachtrag zur 9. Teilgenehmigung fuer die Errichtung der Wiederaufarbeitungsanlage Karlsruhe
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Secondary Subject
Source
Published in summary form only.; CODEN: BDZRA.
Record Type
Journal Article
Journal
Bundesanzeiger; ISSN 0344-7634;
; v. 35(197); p. 11365

Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Becker, H.J.; Schultes, E.; Wieses, H.
International meeting on monitoring of Pu-contaminated waste. Proceedings. Ispra, 25-28 September 19791979
International meeting on monitoring of Pu-contaminated waste. Proceedings. Ispra, 25-28 September 19791979
AbstractAbstract
[en] The experience gained to date, during the testing of Pu-monitors in the reprocessing plant at Karlruhe (WAK), is described in this paper. These monitors are a part of the instrumentation for Pu-control in the planned German nuclear fuel cycle centre (NEZ). It is a basic principle for the planning engineer to design a process only on instruments which have been shown to work successfully in actual plant operations, either in the WAK plant, or in other comparable industrial plants. This design requirement necessitates the development of such devices, taking into account both the designers specification and the special conditions and circumstances of the test facility, e.g. the WAK plant. In the WAK plant the following monitors are tested which are designed for the NEZ: fuel element monitor, hull monitor, neutron monitor, alpha-monitor, off-gas monitor. For each of these monitors the method employed and actual stage of development, are described shortly and, from the operational experience gained up to now, conclusions are drawn for the future running operation of the NEZ
Source
Commission of the European Communities, Ispra (Italy). Joint Research Centre; 630 p; 1979; p. 481-496; International meeting on monitoring of Pu-contaminated waste; Ispra, Varese, Italy; 25 - 28 Sep 1979
Record Type
Report
Literature Type
Conference
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Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Original Title
Bekanntmachung ueber die Erteilung einer Atomrechtlichen Genehmigung
Primary Subject
Secondary Subject
Source
Published in summary form only.; CODEN: BDZRA.
Record Type
Journal Article
Journal
Bundesanzeiger; ISSN 0344-7634;
; v. 36(182); p. 10929

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INIS IssueINIS Issue
Engelhardt, C.; Schneider, G.; Marx, R.
The 1st JSME/ASME joint international conference on nuclear engineering1991
The 1st JSME/ASME joint international conference on nuclear engineering1991
AbstractAbstract
[en] After nearly twenty years of operation WAK-GmbH, the company operating WAK, discontinued operation of the plant. Preparatory planning to decommissioning was performed the results of which will be reported here. Based on experience a mixed concept of manual and remote disassembly was chosen for the dismantling operations. This is considered to constitute the optimized solution in terms of economy and taking into consideration the stipulations of the Atomic Energy Act. Detailed documents have already been elaborated for this task. (author)
Primary Subject
Source
Japan Society of Mechanical Engineers, Tokyo (Japan); 1273 p; 1991; v. 2 p. 31-35; Japan Society of Mechanical Engineers; Tokyo (Japan); 1. JSME/ASME joint international conference on nuclear engineering; Tokyo (Japan); 4-7 Nov 1991
Record Type
Book
Literature Type
Conference
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
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