摘要:
In a method and an apparatus for inspecting an annular weld (10) on a main coolant pipe (4) connected to a reactor pressure vessel (2) in a nuclear power plant, a self-propelled submersible vehicle (12) is introduced into the open, flooded reactor pressure vessel (2), said vehicle (12) comprising at least one inspection device (20) that can be placed against the internal peripheral surface of the main coolant pipe (4) and can be moved in the peripheral direction of the pipe (4). The submersible vehicle (12) is advanced into the main coolant pipe (4), which is also flooded, and is fixed in the region of the weld (10) by means of radially deployable extension arms (16). The inspection device (20) is then placed against the weld (10) and is moved therealong in the peripheral direction.
摘要:
Die Erfindung betrifft ein Verfahren und eine entsprechende Vorrichtung zur Druckentlastung eines Kernkraftwerks (2) mit einer Sicherheitshülle (4) zum Einschluss von Aktivitätsträgern und mit einem Auslass (10) für einen Entlastungsstrom, wobei der Entlastungsstrom über eine mit einem Filtersystem versehene Entlastungsleitung (12) aus der Sicherheitshülle (4) in die Atmosphäre geführt wird, wobei das Filtersystem eine Filterkammer (16) mit einem Filterkammereinlass (84), einem Filterkammerauslass (86) und einem dazwischen liegenden Sorbensfilter (18) umfasst, wobei der Entlastungsstrom in einem Hochdruckabschnitt (38) der Entlastungsleitung (12) zumindest teilweise an der Filterkammer (16) vorbei geführt wird und diese dabei durch Wärmeübertrag beheizt wird, und wobei der Entlastungsstrom am Ende des Hochdruckabschnitts (38) durch Expansion an einer Drossel (40) entspannt und getrocknet wird. Um eine besonders effiziente und wirksame Rückhaltung von im Entlastungsstrom enthaltenen Aktivitätsträgern, insbesondere von jodhaltigen organischen Verbindungen, zu ermöglichen, ist erfindungsgemäß vorgesehen, dass der Entlastungsstrom - anschließend durch einen Sand- oder Kiesbettfilter (14) geleitet wird, - anschließend in einem Überhitzungsabschnitt (50) an dem Hochdruckabschnitt (38) der Entlastungsleitung (12) vorbeigeführt und dabei durch Wärmeübertrag erhitzt wird, - direkt anschließend in diesem Zustand durch die Filterkammer (16) mit dem Sorbensfilter (18) hindurch geleitet wird, und - schließlich in die Atmosphäre ausgeblasen wird.
摘要:
A method for monitoring the fill level of a liquid (F) in a liquid container, in particular for monitoring the coolant fill level in a reactor pressure vessel (4) of a pressurized water reactor system, wherein a determination is made about the drop in the liquid level (10) below the installed height of a heated thermal element (HT) by way of the temperature difference (DT) measured between said heated thermal element (HT) and an unheated thermal element (UHT) associated therewith, both of said elements being disposed in the liquid container, said method comprising the especially reliable triggering of an alarm with a short response time while maintaining a low level of physical and controls engineering complexity when the liquid level to be monitored falls below a critical value. To this end, according to the invention the temporal progression of the temperature difference (DT) is continuously monitored for any significant increase, in particular sudden increase, within a time interval of pre-determined duration (Δt) prior to the respective evaluation time (t 0 ), wherein an alarm signal is issued as soon as the change (ΔDT) in the temperature difference (DT) within said time interval reaches or exceeds a pre-determined limit value.
摘要:
The invention relates to a method for chemically decontaminating the surface of a metal component of the primary circuit of a pressurized-water reactor, said surface comprising an oxide layer. The method is divided into two process stages and is further implemented as follows: - in the first process stage, at least one treatment cycle is performed, comprising an oxidation step, a reduction step, and a subsequent first decontamination step, wherein the component is treated in the oxidation step with an aqueous solution comprising an oxidizing agent, which converts trivalent chrome present in the oxide layer into hexavalent chrome; the component is treated in the reduction step with an aqueous solution comprising a reducing agent for reducing excess oxidation agent from the oxidation step; the component is treated in the first decontamination step with an aqueous solution comprising exclusively or predominantly at least one decontamination acid that forms no antisoluble deposits with metal ions present in the solution, in particular bivalent metal ions; and the solution is fed through an ion exchanger for removing metal ions present in the solution, which metal ions originate from the oxide layer and/or the base metal of the component, - in the second process stage, at least one treatment cycle is performed, comprising a second decontamination step, wherein the component is treated with an aqueous solution comprising exclusively or predominantly oxalic acid as a decontamination acid.
摘要:
The invention relates to a cleaning method for removing deposits containing magnetite out of a pressure vessel of a power plant, during which the deposits are treated with an aqueous cleaning solution, which contains a reducing agent and which is heated to an elevated cleaning temperature, in order to reduce iron III ions to iron II ions. The invention is characterized in that a cleaning solution is introduced into the pressure vessel. This cleaning solution contains an initial substance that releases the reducing agent under the conditions existing during cleaning. Hexamethylenetetramine is preferably used as the initial substance.
摘要:
In a fuel element for a pressurized-water reactor, in addition to spacers (6), flow-guiding structural parts (8) are arranged which comprise four outer webs (20) which, in a plane oriented perpendicularly to the central longitudinal axis (4), surround a square inner region (24) of which the centre point (M) lies on the central longitudinal axis (4). At their lower longitudinal side facing the flowing cooling water in the operating state, the outer webs are provided with deflection lugs (30) pointing towards the inner region and are structurally identical, wherein mutually opposite outer webs (20) are arranged mirror-symmetrically with respect to a centre plane (21) extending in the axial direction. Such a structural part (8) forms, at most for a number of fuel rods (2) which is smaller than their total number in the fuel element, cells (12) through which a respective fuel rod (2) is guided, wherein the number of these cells (27), which are situated in a row (14) or column (16), is smaller than the number of the fuel rods (2) respectively situated in this row (14) or column (16).
摘要:
The invention (2) relates to a device (2) that is simply constructed and displays a high fail safeness for using heated thermoelements (HT) and unheated thermoelements (UHT) as transmitters for measuring a liquid in a liquid container, in particular in the reactor container (4) of a nuclear installation, makes an especially precise and reliable measurement of the level height (H) possible. In addition, the invention proposes a plurality of elongated measuring tubes (6), at a distance from one another, wherein each measuring tube (6) exhibits a number of thermoelements (HT, UHT) arranged such that they are distributed in a longitudinal direction, and wherein an unheated thermoelement (UHT), acting as a reference transmitter, is allocated to a thermoelement (HT), acting as a primary transmitter, arranged at a first measuring tube (6) and heated by a heating element (HE) and which is arranged at a measuring tube (6) that is different from the first measuring tube (6).
摘要:
The invention relates to a method for conditioning a precipitating solution that arises during the wet-chemical cleaning of conventional or nuclear plants, said solution containing organic substances and metals in ionic form, in which at least a portion of the organic substance is decomposed through electrochemical treatment or UV radiation of the precipitating solution and wherein at least one metal precipitates with the addition of phosphoric acid, and the resultant phosphate precipitate is removed from the precipitating solution.