DE2548734A1 - Removing hydrogen isotopes from gas circuit in nuclear reactor - by diffusion of esp. tritium into heated containers placed in gas stream - Google Patents
Removing hydrogen isotopes from gas circuit in nuclear reactor - by diffusion of esp. tritium into heated containers placed in gas streamInfo
- Publication number
- DE2548734A1 DE2548734A1 DE19752548734 DE2548734A DE2548734A1 DE 2548734 A1 DE2548734 A1 DE 2548734A1 DE 19752548734 DE19752548734 DE 19752548734 DE 2548734 A DE2548734 A DE 2548734A DE 2548734 A1 DE2548734 A1 DE 2548734A1
- Authority
- DE
- Germany
- Prior art keywords
- gas
- tritium
- hydrogen isotopes
- temperature
- devices
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Ceased
Links
Classifications
-
- C—CHEMISTRY; METALLURGY
- C01—INORGANIC CHEMISTRY
- C01B—NON-METALLIC ELEMENTS; COMPOUNDS THEREOF; METALLOIDS OR COMPOUNDS THEREOF NOT COVERED BY SUBCLASS C01C
- C01B4/00—Hydrogen isotopes; Inorganic compounds thereof prepared by isotope exchange, e.g. NH3 + D2 → NH2D + HD
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/02—Treating gases
Abstract
Description
Dr.Dietrich Bachner, 53 Bonn-Bad Godesberg, Viktoriaplatz 3Dr Dietrich Bachner, 53 Bonn-Bad Godesberg, Viktoriaplatz 3
Dipl.Phys. Günter Morlock, 75 Karlsruhe 41, Christofstraße 19 Dr.Johannes Wiesemes, 56 Wuppertal 1, CäcilienstraBe 7 Vorrichtung zur Entfernung von Wasserstoff-Isotopen aus Gasphasen,insbesondere zur Entfernung von Tritium aus dem Primärgas von Hochtemperatur-Reaktoren (Zusatz zu Patent Patentanmeldung P 25m6798.0) Die Erfindung betrifft ein Verfahren und gegenüber Patent (Patentantrieldung P 2536798.0) modifizierte Vorrichtungen zur Entfernung von Wasserstoff-Isotopen aus Gasphasen,wobei mit Hilfe dieses Verfahrens und dieser modifizierten Vorrichtungen eine Tritiumentfernung aus dem Primärgas'von Hochtemperatur-Reaktoren ermöglicht wird.Dipl.Phys. Günter Morlock, 75 Karlsruhe 41, Christofstrasse 19 Dr Johannes Wiesemes, 56 Wuppertal 1, CäcilienstraBe 7 Device for removing hydrogen isotopes from gas phases, especially for removing tritium from the primary gas of high-temperature reactors (Addition to patent patent application P 25m6798.0) The invention relates to a method and compared to patent (patent application P 2536798.0) modified devices for the removal of hydrogen isotopes from gas phases, using this procedure and these modified devices include tritium removal from the primary gas High temperature reactors is made possible.
In Patent (Patentanmeldung P 2536798.0) wird die Einstellung geeigneter Funktionstemperaturen der Vorrichtungen durch elektrische Heizeinrichtungen erreicht.In patent (patent application P 2536798.0) the setting is more suitable Functional temperatures of the devices achieved by electrical heating devices.
Die in Patent (Patentanmeldung P 2536798.0) beschriebene Temperatureinstellung der Wandung der Vorrichtungen durch elektrische Heizung ist bei einem Einsatz in Hochtemperatur-Reaktoren nicht befriedigend,da durch das vorbeiströmende Primärgas die Temperatur der Vorrichtungen wesentlich vorbestimmt wird.In dem Patent.........The temperature setting described in patent (patent application P 2536798.0) the wall of the devices by electrical heating is when used in High-temperature reactors are unsatisfactory because of the primary gas flowing past them the temperature of the devices is essentially predetermined. In the patent .........
(Patentanmeldung P 2536798.0) fehlen Angaben zum Einsatz der beschriebenen Vorrichtungen zur Tritiumentfernung aus dem Primärgas von Hochtemperatur-Reaktoren,bei denen eine Reduzierung des Tritiumgehalts des Primärgases angestrebt wird.(P.G. Fischer,D. Stöver1H.D. Röhrig,R. Hecker: t*Untersuchungen zum Tritiumtransportverhalten in Hochtemperatur-Reaktoren Reaktortagung Berlin 2.-5. April 1974 5.420 - 423) Der Erfindung liegt die Aufgabe zugrunde,die in Patent.......(Patent application P 2536798.0) there is no information on the use of the described Devices for removing tritium from the primary gas of high-temperature reactors aiming to reduce the tritium content of the primary gas (P.G. Fischer, D. Stöver1H.D. Röhrig, R. Hecker: t * Studies on tritium transport behavior in high-temperature reactors Reaktortagung Berlin 2.-5. April 1974 5,420 - 423) The The invention is based on the object described in patent .......
(Patentanmeldung P 2536798.0) beschriebenen Vorrichtungen für den Einsatz zur Tritiumentfernuno aus dem Primärgas von Hochtemperatur-Reaktoren zu modifizieren sowie ein Verfahren zun Einsatz dieser modifizierten Vorrichtungen zu entwickeln.(Patent application P 2536798.0) described devices for the Use for tritium removal from the primary gas of high-temperature reactors modify and a method of using these modified devices to develop.
Diese Aufgabe wird erfindungsgemäß dadurch gelöst, -daß die gegenüber Patent (Patentanmeldung P 2536798.0) für den Einsatz zur Tritiumentfernung aus dem Primärgas von Hochtemperatur-Reaktoren modifizierten Vorrichtungen aus Behältern bestehen, -die im Primärgasstrom angeordnet sind, -deren Wandungen -auf geeignete Temperatur gebrachtvorzugsweise für Wasserstoff-Isotope durchlässig sind, -die zur Erreichung von Festigkeit und Druckresistenz entweder mit einer kompakten und druckresistenten Schüttung geeigneter,fester Stoffe,z.B. Quarzsand gefüllt sind oder eine sonstige geeignete Stützkonstruktion enthalten und -die über Rohrleitungen mit reinem Heliumgas -z.B. aus der Gasreinigungsanlage- gespült werden, wobei die durch die Wandung diffundierten Wasserstoff-Isotope und damit auch das Tritium zur Gasreinigungsanlage transportiert werden, -daß in einer weiteren Ausgestaltung der Erfindung bei der Tritiumentfernung aus dem Primärgas von Hochtemperatur-Reaktoren die modifizierten Vorrichtungen an solchen Stellen im Primärgasstrom,ggf. in einem Primärgasteilstrom,angeordnet sind,dan die Temperatureinstellung der Vorrichtungen durch das Primärgas erfolgt,wobei eine für die Diffusion geeignete Temperatur z.B. durch Mischen von Gasströmen unterschiedlicher Temperaturen erreicht werden kann oder zu diesem Zweck z.B. Gas entsprechender Temperatur eingesetzt werden kannsdas an geeigneter Stelle z.B. am Dampferzeuger abgezweigt und nach Vorbeiströmen an den beschriebenen Vorrichtungen wieder zurückgeführt wird.This object is achieved according to the invention in that the opposite Patent (patent application P 2536798.0) for use in removing tritium from the Primary gas from high temperature reactors modified devices from containers exist, -which are arranged in the primary gas flow, -whose walls -on suitable Brought to temperature are preferably permeable to hydrogen isotopes, -those to Achieving strength and pressure resistance either with a compact and pressure-resistant Pour suitable, solid substances, e.g. Quartz sand are filled or another contain suitable support structure and -the via pipelines with pure helium gas -e.g. flushed out of the gas cleaning system, which diffused through the wall Hydrogen isotopes and thus also the tritium are transported to the gas cleaning plant -that in a further embodiment of the invention in the tritium removal the modified devices from the primary gas of high-temperature reactors such points in the primary gas flow, if necessary. are arranged in a primary gas partial flow, then the temperature setting of the devices is carried out by the primary gas, with a temperature suitable for diffusion e.g. by mixing gas streams of different Temperatures can be reached or for this purpose e.g. gas of the appropriate temperature can be used that branches off at a suitable point, e.g. on the steam generator and is returned after flowing past the devices described.
Durch die angegebenen Lösungen ergeben sich folgende Vorteile: 1.) Die beschriebenen modifizierten Vorrichtungen zur Tritium entfernung aus dem Primärgas von Hochtemperatur-Reaktoren bieten eine sehr einfache und damit sehr kostengünstige Möglichkeit,bei unveränderter Gasreinigungsanlage den Tritiumanteil im Primärgas von Hochtemperatur-Reaktoren erheblich zu senken.Dabei wird die Wirksamkeit der Gasreinigungsanlage dadurch verbessert,daß ihr in einem Teilstrom Heliumgas mit erhöhter Tritiumkonzentration zugeführt wird.The specified solutions result in the following advantages: 1.) The modified devices described for tritium removal from the primary gas of high temperature reactors offer a very simple and therefore very inexpensive Possibility of reducing the tritium content in the primary gas with the gas cleaning system unchanged of high-temperature reactors significantly, thereby reducing the effectiveness of the Gas cleaning system improved by the fact that you have helium gas in a partial flow increased tritium concentration is supplied.
2.) Durch die gegenüber Patent (Patentanmeldung P 2536798.0) eingesparte Zwischenspeicherung des Tritiums in geeigneten Schüttungen erübrigt sich das sonst eventuell erforderliche häufige Ausheizen der Vorrichtungen beim Einsatz in Hochtemperatur-Reaktoren.2.) By saving compared to the patent (patent application P 2536798.0) Otherwise, there is no need to temporarily store the tritium in suitable beds If necessary, frequent bake-out of the devices when used in high-temperature reactors.
3.) Die leicht mögliche Reduzierung der Tritiumkonzentration im Primärkreislauf von Hochtemperatur-Reaktoren kann bei dem vorgesehenen Einsatz dieser Reaktoren zur Prozeßdampferzeugung einen dritten Kreislauf ersparen,der bei zu hoher Tritiumkonzentration im Primärgas und der bekannten Diffusion des Tritiums durch den Wärmetauscher (Dampferzeuger) in den Sekundärkreislauf gegebenenfalls notwendig wäre.3.) The easily possible reduction of the tritium concentration in the primary circuit of high temperature reactors can with the intended use of these reactors save a third circuit for process steam generation, the one if the tritium concentration is too high in the primary gas and the known diffusion of tritium through the heat exchanger (steam generator) in the secondary circuit would be necessary if necessary.
Claims (2)
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
DE19752548734 DE2548734A1 (en) | 1975-10-31 | 1975-10-31 | Removing hydrogen isotopes from gas circuit in nuclear reactor - by diffusion of esp. tritium into heated containers placed in gas stream |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
DE19752548734 DE2548734A1 (en) | 1975-10-31 | 1975-10-31 | Removing hydrogen isotopes from gas circuit in nuclear reactor - by diffusion of esp. tritium into heated containers placed in gas stream |
Publications (1)
Publication Number | Publication Date |
---|---|
DE2548734A1 true DE2548734A1 (en) | 1977-05-05 |
Family
ID=5960511
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
DE19752548734 Ceased DE2548734A1 (en) | 1975-10-31 | 1975-10-31 | Removing hydrogen isotopes from gas circuit in nuclear reactor - by diffusion of esp. tritium into heated containers placed in gas stream |
Country Status (1)
Country | Link |
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DE (1) | DE2548734A1 (en) |
Cited By (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
EP0069222A2 (en) * | 1981-05-27 | 1983-01-12 | Forschungszentrum Jülich Gmbh | Process for separating hydrogen and/or deuterium and tritium from a stream of inert gas, and device for performing this process in the gas cooling circuit of a gas-cooled nuclear reactor |
US5895519A (en) * | 1996-03-28 | 1999-04-20 | Saes Pure Gas, Inc. | Method and apparatus for purifying hydrogen gas |
DE19821334A1 (en) * | 1998-05-13 | 1999-11-25 | Uwe Kuhnes | Safety equipment especially intended to abstract hydrogen from containment of nuclear reactor |
US6068683A (en) * | 1993-05-20 | 2000-05-30 | The Regents Of The University Of California | Apparatus for separating and collecting hydrogen gas |
-
1975
- 1975-10-31 DE DE19752548734 patent/DE2548734A1/en not_active Ceased
Cited By (7)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4707342A (en) * | 1981-05-21 | 1987-11-17 | Kernforschungsanlage Julich Gesellschaft Mit Beschrankter Haftung | Process for separation of hydrogen and/or deuterium and tritium from an inert gas flow and apparatus for effectuation of process in the cooling gas circuit of a gas-cooled nuclear reactor |
EP0069222A2 (en) * | 1981-05-27 | 1983-01-12 | Forschungszentrum Jülich Gmbh | Process for separating hydrogen and/or deuterium and tritium from a stream of inert gas, and device for performing this process in the gas cooling circuit of a gas-cooled nuclear reactor |
EP0069222A3 (en) * | 1981-05-27 | 1985-12-27 | Kernforschungsanlage Julich Gesellschaft Mit Beschrankter Haftung | Process for separating hydrogen and/or deuterium and tritium from a stream of inert gas, and device for performing this process in the gas cooling circuit of a gas-cooled nuclear reactor |
US6068683A (en) * | 1993-05-20 | 2000-05-30 | The Regents Of The University Of California | Apparatus for separating and collecting hydrogen gas |
US5895519A (en) * | 1996-03-28 | 1999-04-20 | Saes Pure Gas, Inc. | Method and apparatus for purifying hydrogen gas |
DE19821334A1 (en) * | 1998-05-13 | 1999-11-25 | Uwe Kuhnes | Safety equipment especially intended to abstract hydrogen from containment of nuclear reactor |
DE19821334C2 (en) * | 1998-05-13 | 2002-07-11 | Uwe Kuhnes | Device for installation in a room or system, in particular a nuclear power plant, in which there is a risk of hydrogen release |
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Legal Events
Date | Code | Title | Description |
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8162 | Independent application | ||
8110 | Request for examination paragraph 44 | ||
8131 | Rejection |