Filters
Results 1 - 10 of 8074
Results 1 - 10 of 8074.
Search took: 0.043 seconds
Sort by: date | relevance |
AbstractAbstract
[en] Data are presented on 5 categories of nuclear facilities: 1) Decommissioned power, test and nuclear ship reactors in safe storage with continued license, 2) Decommissioned research reactors and critical facilities in safe storage with continued possession only licence, 3) Dismantled research reactors with license terminated, 4) Dismantled critical facilities with license terminated, and 5) Decommissioned demonstration nuclear power plants. For each decommissioned reactor listed in this paper the reactor type is shown, its power level, the location, and date the license was terminated or the present status if a license is still in effect
Primary Subject
Source
Anon; p. 337-348; 1980; p. 337-348; Plenum Press; New York, NY; Decontamination and decommissioning of nuclear facilities conference; Sun Valley, ID (USA); 16 - 19 Sep 1979
Record Type
Book
Literature Type
Conference
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Kaulard, Joerg; Francois, Patrice; Ljubenov, Vladan; O’Sullivan, Patrick; Pennington, Mark; Schruder, Kristan; Skanata, Dejan
Advancing the Global Implementation of Decommissioning and Environmental Remediation Programmes. Proceedings of an International Conference. Companion CD-ROM. Book of Abstracts2017
Advancing the Global Implementation of Decommissioning and Environmental Remediation Programmes. Proceedings of an International Conference. Companion CD-ROM. Book of Abstracts2017
AbstractAbstract
[en] In order to provide assistance and feedback on the application of risk management methodologies in preparation of and during decommissioning, IAEA’s International Decommissioning Network (IDN) launched in December 2012 the “Decommissioning Risk Management Project – DRiMa Project” which was completed in November 2015. The DRiMa project developed an approach for risk management which inter alia distinguishes between the need to manage uncertainties associated with assumptions (related to initial decommissioning plans) or with strategic decisions (setting the frame for final decommissioning plans), and the need to manage (operational) risks during the implementation of decommissioning activities (project risks). Central elements recommended by the DRiMa Project are the use of prompters to systematically analyze assumptions, strategic decisions and their uncertainties and (operational) risks and the use of registers to systematically manage these entities.
Primary Subject
Source
International Atomic Energy Agency, Waste Technology Section, Vienna (Austria); European Commission, Brussels (Belgium); OECD/Nuclear Energy Agency (NEA), Boulogne-Billancourt (France); European Bank for Reconstruction and Development, London (United Kingdom); [1 CD-ROM]; ISBN 978-92-0-111416-7;
; Jul 2017; 3 p; International Conference on Advancing the Global Implementation of Decommissioning and Environmental Remediation Programmes; Madrid (Spain); 23-27 May 2016; ISSN 0074-1884;
; Also available on-line: https://www.iaea.org/publications/11155/advancing-the-global-implementation-of-decommissioning-and-environmental-remediation-programmes?supplementary=39325 and on 1 CD-ROM attached to the printed STI/PUB/1759 from IAEA, Marketing and Sales Unit, Publishing Section, E-mail: sales.publications@iaea.org; Web site: http://www.iaea.org/books; 2 refs., figs.


Record Type
Book
Literature Type
Conference
Country of publication
Reference NumberReference Number
Related RecordRelated Record
INIS VolumeINIS Volume
INIS IssueINIS Issue
External URLExternal URL
AbstractAbstract
[en] The VEW AG, Dortmund, decided on the definite shut-down of this nuclear power plant. Their future tasks are to prepare and perform the safe enclosure and the later demolition of the plant as well as the reprocessing of the spent nuclear fuel. (DG)
[de]
Die VEW AG, Dortmund, beschloss die endgueltige Stillegung des KKW. Ihre zukuenftigen Aufgaben liegen im Vorbereiten und Herbeifuehren des gesicherten Einschlusses sowie des spaeteren Abbruchs der Anlage sowie der Wiederaufarbeitung des bestrahlten nuklearen Brennstoffs. (DG)Original Title
Bericht ueber das 18. Geschaeftsjahr vom 1. Januar bis 31. Dezember 1981
Primary Subject
Source
1982; 20 p
Record Type
Miscellaneous
Literature Type
Progress Report
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Lund, D.P.
Westinghouse Hanford Co., Richland, WA (United States); FFTF Working Group. Funding organisation: USDOE Office of Environmental Restoration and Waste Management, Washington, DC (United States)1995
Westinghouse Hanford Co., Richland, WA (United States); FFTF Working Group. Funding organisation: USDOE Office of Environmental Restoration and Waste Management, Washington, DC (United States)1995
AbstractAbstract
[en] The document contains the functions, function definitions, function interfaces, function interface definitions, Input Computer Automated Manufacturing Definition (IDEFO) diagrams, and function hierarchy charts that describe what needs to be performed to deactivate FFTF
Primary Subject
Source
Sep 1995; 40 p; CONTRACT AC06-87RL10930; Also available from OSTI as DE97051234; NTIS; US Govt. Printing Office Dep
Record Type
Report
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Spruyt, A.; Peters, D.; Loon, W.M.G.M. van; Boekschoten, H.J.C.; Brugman, H.
Keuring van Electrotechnische Materialen NV, Arnhem (Netherlands)1991
Keuring van Electrotechnische Materialen NV, Arnhem (Netherlands)1991
AbstractAbstract
[en] In this report the decommissioning of the KEMA Suspension Test Reactor (KSTR) is described. This reactor was a 1 MWth aqueous homo-geneous nuclear reactor in which a suspension of a mixed oxide UO2/ ThO2 in light water was circulated in a closed loop through a sphere-shaped core vessel. The reactor, located on KEMA premises, made 150 MW of heat during its critical periods. Dismantling of this reactor, with its many connected subsystems, meant the mastering of activated components which were also contaminated on inner surfaces caused by small fuel deposits (alpha contaminants) and fission products (beta, gamma contaminants). A description is given of the save removal of the fuel, the remote dismantling of systems and components and the disposal of steel scrap and other materials. Important features are the measures to be taken and provisions needed for safe handling, for the reduction of the radiation dose for the working team and the prevention of spreading of activity over the working area and the environment. It has been demonstrated that safe dismantling and disposal of such systems can be achieved. Experience gained at KEMA for the proper dismantling and for safety measures to be taken for workers and the environment can be made available for similar dismantling projects. A cost break-down is included in the report. (author). 22 refs.; 52 figs.; 12 tabs
Primary Subject
Source
29 Jan 1991; 80 p; PROJECT NR. 61602-TFO; Photocopies available from Library KEMA; P.O.Box 9035, 6800 ET Arnhem, The Netherlands; A project on assignment of KEMA, Collective Assignment Production (COP); includes summary in Dutch.
Record Type
Report
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] The Nuclear Power Demonstration (NPD) generating station at Rolphton, Ontario began operating in 1962. It was intended to demonstrate the practicability of producing electricity with the CANDU reactor design. A pressure tube removed in 1987 showed hydrogen concentrations high enough to cause concern for the mechanical properties of the other tubes. When it was found that the problem was widespread, it was decided to shut the reactor down. The decommissioning of NPD is to be carried out in three stages: final operation - the removal of all fuel and heavy water and shutting down all systems; static state - a period of about 50 years of radioactive decay when the site will be unstaffed by monitored remotely; and ultimate disposal, when either all radioactive material will be removed to a permanent repository or the existing structure will be filled with concrete, sand or other material. The final operation stage is expected to be complete by September 1, 1988
Primary Subject
Source
Canadian Nuclear Society, Toronto, ON (Canada); 488 p; 1988; p. 194-196; Canadian Nuclear Society 9. annual conference; Winnipeg, MB (Canada); 13-15 Jun 1988
Record Type
Miscellaneous
Literature Type
Conference
Report Number
Country of publication
Reference NumberReference Number
Related RecordRelated Record
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] Short communication
Original Title
Raboty po dezaktivatsii i vyvodu iz ekspluatatsii yadernykh ustanovok v ANL
Primary Subject
Source
Koltysheva, G.I.; Perepelkin, I.G. (eds.); Ministerstvo Nauki-Akademiya Nauk, Almaty (Kazakstan); Minesterstvo Ehnergetiki i Ugol'noj Promyshlennosti, Alma-Ata (Kazakstan); Ministerstvo Ehkonomiki, Almaty (Kazakstan); Natsional'nyj Yadernyj Tsentr, Kurchatov (Kazakstan); Natsional'naya Aktsionernaya Kompaniya KATEhP, Almaty (Kazakstan); Nauchno-Issledovatel'skij Inst. Ehksperimental'noj i Teoreticheskoj Fiziki Natsional'nogo Gosudarstvennogo Univ., Almaty (Kazakstan); Agentstvo po Atomnoj Ehnergii, Alma-Ata (Kazakstan); Yadernoe Obshchestvo Respubliki Kazakhstan, Kurchatov (Kazakstan); Aktauskaya Gorodskaya Administratsiya, Aktau (Kazakstan); Mangyshlakskij Atomno-Ehnergeticheskij Kombinat, Aktau (Kazakstan); Ministerstvo Rossijskoj Federatsii po Atomnoj Ehnergii, Moscow (Russian Federation); Rossijskij Nauchnyj Tsentr 'Kurchatovskij Inst.', Moscow (Russian Federation); Gosudarstvennyj Nauchno-Issledovatel'skij Inst. NPO Luch, Podol'sk (Russian Federation); Yadernoe Obshchestvo, Moscow (Russian Federation); 150 p; Jun 1996; p. 19; Sigma; Kurchatov (Kazakstan); International scientific-practical conference: nuclear power engineering in the Republic of Kazakstan. Perspectives of development (NE-96); Mezhdunarodnaya nauchno-prakticheskaya konferentsiya: yadernaya ehnergetika v Respublike Kazakhstan. Perspektivy razvitiya (YaEh-96); Aktau (Kazakstan); 24-27 Jun 1996
Record Type
Miscellaneous
Literature Type
Conference
Report Number
Country of publication
Reference NumberReference Number
Related RecordRelated Record
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] This report presents the status of the problem with release of materials from decommissioned nuclear power plants in the European countries and Bulgaria and activities for adoption of standards in this area. The principles applied in developing of internationally approved criteria for releasing are discussed with regard of minimal impact on the environment
Original Title
Osnovni printsipi na osvobozhdavaneto ot kontrol na radioaktivni materiali pri izvezhdane na AETs Kozloduy ot eksploatatsiya
Primary Subject
Source
2000; 6 p; International Meeting '30 Years Nuclear Research and Design Activities in ENERGOPROEKT plc Bulgaria'; Varna (Bulgaria); 31 May - 2 Jun 2000; Available from Bulgarian INIS Centre in pdf format; 4 refs.
Record Type
Miscellaneous
Literature Type
Conference
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] Decommissioning work has been in progress on the Windscale advanced gas-cooled reactor (WAGR) since 1981 and on the Windscale piles since 1987. The work has more of the attributes of an r and d programme than a normal engineering project but it is generally on target for both. This article discusses the management and techniques of decommissioning the WAGR. A future article will report on progress with the Windscale piles. (author)
Primary Subject
Record Type
Journal Article
Journal
Professional Engineering; ISSN 0953-6639;
; v. 1(3); p. 34-38

Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] At the end of 1987, the work for preparing the safe enclosure of the reactor was completed, and on March 22, 1988 the supervisory authority gave permission to start operational activities for post-shutdown containment of the reactor, as of March 30, 1988. The personnel of KWL was reduced to 12 members in the reporting year. As financial reserves for decontamination and waste management, DM 14.6 millions were required, and DM 3.6 millions for reprocessing. The annual loss of DM 20.3 millions was compensated by VEW by mena of supplementary contributions. KWL also, as in previous years, contributed in 1987 to research projects of the European Commission (Euratom), the KWL programme covering the field of containment after decommissioning, and theoretical and experimental studies on the effects of ventilation and air-drying on activity release and corrosion in the plant. (orig./HP)
[de]
Zum Jahresende 1987 waren die Arbeiten zur Herbeifuehrung des Sicheren Einschlusses abgeschlossen. Am 22. Maerz 1988 erteilte die Genehmigungsbehoerde die Zustimmung zum Betrieb des Sicheren Einschlusses ab dem 30. Maerz des laufenden Geschaeftsjahres. Der Personalbestand von KWL wurde auf 12 Mitarbeiter abgebaut. Der Rueckstellung fuer Entsorgung mussten 14,6 Mio DM fuer die Stillegung und 3,6 Mio DM fuer die Wiederaufarbeitung zugefuehrt werden. Den Jahresfehlbetrag in Hoehe von 20,3 Mio DM hat VEW durch Nachschuesse ausgeglichen. KWL hat sich auch 1987 an Forschungsvorhaben der EG beteiligt. Das KWL-Programm umfasst fuer den Bereich des Sicheren Einschlusses theoretische und experimentelle Ermittlungen ueber die Auswirkungen von Belueftung und Lufttrocknung auf Aktivitaetsfreisetzung und Korrosion in der Anlage. (orig./HP)Original Title
KWL Bericht ueber das Geschaeftsjahr 1987
Primary Subject
Source
1987; 22 p
Record Type
Miscellaneous
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
1 | 2 | 3 | Next |