[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

[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.

[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)

[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

[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

[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

[en] Short communication

[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

[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)

[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)