摘要:
The invention relates to a pressure release system (18) for a containment structure (4) of a nuclear installation (2), having a pressure release line (16) which is guided through the containment structure (4) and which can be closed off by means of a shut-off fitting (30, 32), wherein a wet scrubber (36) for the pressure release gas flow generated during pressure release operation with the shut-off fitting (30, 32) open is connected into a section of the pressure release line (16) situated outside the containment structure (4). Based on this, it is the intention to permit effective and reliable operation of the wet scrubber (36) with a simultaneously compact design, in particular with regard to the amounts of washing fluid (52) that must be kept available. This is achieved according to the invention by means of • a reservoir (67) which is arranged in the containment structure (4) or connected in terms of flow thereto such that a positive pressure prevailing in the containment structure (4) in relation to the outside environment is at least partially, preferably predominantly or entirely, transmitted to the reservoir (67), and • a feed line (68), which leads from the reservoir (67) to the wet scrubber (36) and which can be closed off by means of a shut-off fitting (72), for the feed of liquid (14), which acts as washing fluid (52), from the reservoir (67) to the wet scrubber (36).
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 process for removal of tritium from materials that are contaminated thereby envisages the use of a detritiation reactor RT, in which the reaction for the removal of tritium from the waste takes place, said waste being recovered by means of a flow of moist inert gas in which an extremely low percentage of humidity is used. The heated waste releases a current of tritiated gases, said current of gases being removed from the reactor via the moist inert gas, which conveys it into a membrane reactor RM for decontamination. The membrane reactor, in fact, is able to remove selectively the tritium present in the mixture of gases: there is thus the dual advantage of purifying the mixture of gases and of recovering the tritium contained therein.
摘要:
Processes for the removal of technetium from contaminated uranium hexafluoride containing technetium, typically as technetium-99 (99Tc) in nominal chemical forms are provided. The processes involve contacting the contaminated uranium hexafluoride in liquid form with a metal fluoride, typically magnesium fluoride (MgF¿2?), for a period of time sufficient for the technetium to become adsorbed onto the metal fluoride thereby producing a purified uranium hexafluoride liquid; and removing the purified uranium hexafluoride liquid from the metal fluoride having adsorbed technetium.
摘要:
An organic waste decomposition system (10) and method is described having two reaction vessels (12, 14) in tandem, each using superheated steam augmented by oxygen for decomposing a wide variety of organic compounds to reduce both mass and volume. Decomposition takes place quickly when a steam/oxygen mixture is injected into a fluidized bed (50) of ceramic beads. The speed of the fluidizing gas mixture agitates the beads that then help to break up solid wastes, and the oxygen allows some oxidation to offset the thermal requirements of drying, pyrolysis, and steam reforming. Most of the pyrolysis takes place in the first stage, setting up the second stage for completion of pyrolysis and adjustment or gasification of the waste form using co-reactants to change the oxidation state of inorganics and using temperature to partition metallic wastes.