EP2997579A1 - Système de décompression et de rétention de la radioactivité pour installation nucléaire - Google Patents

Système de décompression et de rétention de la radioactivité pour installation nucléaire

Info

Publication number
EP2997579A1
EP2997579A1 EP14726552.4A EP14726552A EP2997579A1 EP 2997579 A1 EP2997579 A1 EP 2997579A1 EP 14726552 A EP14726552 A EP 14726552A EP 2997579 A1 EP2997579 A1 EP 2997579A1
Authority
EP
European Patent Office
Prior art keywords
pressure relief
containment
pressure
line
adsorber
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.)
Withdrawn
Application number
EP14726552.4A
Other languages
German (de)
English (en)
Inventor
Robert Feuerbach
Axel Hill
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Areva GmbH
Original Assignee
Areva GmbH
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Areva GmbH filed Critical Areva GmbH
Publication of EP2997579A1 publication Critical patent/EP2997579A1/fr
Withdrawn legal-status Critical Current

Links

Classifications

    • 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
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C13/00—Pressure vessels; Containment vessels; Containment in general
    • G21C13/02—Details
    • G21C13/022—Ventilating arrangements
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
    • G21C9/004—Pressure suppression
    • 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
    • G21F9/04—Treating liquids
    • G21F9/06—Processing
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/28—Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core
    • G21C19/30—Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core with continuous purification of circulating fluent material, e.g. by extraction of fission products deterioration or corrosion products, impurities, e.g. by cold traps
    • G21C19/317—Recombination devices for radiolytic dissociation products
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D3/00—Control of nuclear power plant
    • G21D3/04—Safety arrangements
    • G21D3/06—Safety arrangements responsive to faults within the plant
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Definitions

  • the invention relates to a pressure relief and activity restraint system for a nuclear installation, in particular for a nuclear power plant. It also relates to an associated operating method.
  • nuclear power plants can be designed for venting the containment as required by venting the containment atmosphere (venting).
  • a pressure relief line can be connected to the containment of a nuclear facility.
  • radioactive material such as noble gases, iodine or aerosol, which could enter the vicinity of the nuclear power plant on venting.
  • Airborne activity levels (aerosols) within the containment can occur in particularly high concentrations, especially in the case of comparatively severe incidents with potentially occurring meltdown, so that in the presence of high leaks or in the formation of impermissible overpressure situations, significant quantities of such aerosols or quantities of activity are released into the environment of the nuclear facility could occur.
  • Such airborne activities may be particularly due to the high half lives of possibly entrained components such as Iodine or cesium isotopes cause a relatively long-lasting land contamination.
  • the pressure relief systems provided for venting the containment atmosphere are usually provided with filter or retaining devices intended to prevent the release of airborne activity quantities entrained in the containment atmosphere to the environment.
  • filter or retaining devices intended to prevent the release of airborne activity quantities entrained in the containment atmosphere to the environment.
  • the containment atmosphere contains radioactive noble gases such as xenon and krypton, which are currently not sufficiently retained during pressure relief and, depending on weather conditions, in particular make the power plant site inaccessible to accident countermeasures.
  • radioactive noble gases such as xenon and krypton
  • Object of the present invention is therefore to remedy this situation and to provide a device and an associated method with which in a simple and cost-effective manner a reliable retention of noble gases in venting the containment of a nuclear installation can be realized, so that the otherwise expected negative Impact on the environment can be avoided.
  • a pressure relief and activity restraint system for a nuclear facility provided with a containment enclosed by a containment to which a pressure relief line for pressure relief in case of accidents or accidents is connected, with the following components are connected in series in the pressure relief line in the flow direction of the pressure relief flow :
  • At least one of the adsorber columns can be decoupled from the pressure relief stream for the initiation of a rinsing operation in which noble gases accumulated in this adsorber column are rinsed back into the containment with the aid of a rinsing agent,
  • the inventive concept consists essentially of a filtered pressure relief of the containment for the separation of the aerosol-supported activities and a downstream passive process for inert gas delay with recirculation into the containment.
  • two adsorber columns are preferably provided in twin configuration and with a switchover facility in order to enable backwashing of the columns during ongoing venting operation.
  • the advantages achieved thereby are, in particular, that in addition to the airborne activities of the aerosols and organoiodine, the noble gases are retained.
  • the activity-containing noble gases are namely recirculated into the containment.
  • An essential aspect is the pressure relief with simultaneous delay and the return of the noble gases in the containment, where they can safely submerge included.
  • Even long-living noble gas isotopes such as krypton 85 can be separated from the vent flow with the process.
  • the harmless gases like nitrogen, oxygen and steam, on the other hand, are discharged to the environment via a chimney after filtering and lead to pressure relief of the containment.
  • the procedural conditions in the adsorber columns required for the Edelgasabscheiderati be passively generated, preferably with superheated steam through a jet pump and taking advantage of the Nachzerfallsterrorism the accumulated fission products in the wet scrubber.
  • the Nachzerfallswar is thus out of the preferably designed as Venturi scrubber wet scrubber and used to generate steam for the backwashing and vacuum generation in the adsorber columns.
  • the water reservoir in the venturi container is cooled and thus remains available for longer without such a measure.
  • FIG. FIG. 1 shows a nuclear installation with a containment shell and with a first variant of a pressure relief and activity retention system for the enclosure enclosed by the containment shell based on a wet wash of the pressure relief flow
  • FIG. FIG. 2 shows a second variant of the pressure relief and activity retention system based on dry filtering of the pressure relief flow
  • FIG. 3 is a modification of the concept of FIG. 2, which also applies to the variant according to FIG. 1 is applicable. Identical parts are provided with the same reference numerals in all figures.
  • FIG. 1 schematically illustrated pressure relief and activity restraint system 2 allows a filtered pressure relief (venting) referred to as containment 4 safety enclosure a nuclear facility 6, in particular a nuclear power plant in accident or accident situations with significant pressure build-up in the containment 4.
  • containment 4 safety enclosure a nuclear facility 6, in particular a nuclear power plant in accident or accident situations with significant pressure build-up in the containment 4.
  • containment 4 safety enclosure a nuclear facility 6, in particular a nuclear power plant in accident or accident situations with significant pressure build-up in the containment 4.
  • containment 4 safety enclosure a nuclear facility 6, in particular a nuclear power plant in accident or accident situations with significant pressure build-up in the containment 4.
  • containment 4 safety enclosure a nuclear facility 6, in particular a nuclear power plant in accident or accident situations with significant pressure build-up in the containment 4.
  • a special emphasis of the interpretation laid on the retention of radioactive noble gases in addition to the rear - attitude of radioactive aerosols and iodine / iodine compounds a special emphasis of
  • the pressure relief and activity restraint system 2 comprises a pressure relief line 10 led outwardly from the containment 8 through the containment 8 (also referred to as containment) and into the environment into which various devices for treatment and purification / filtration of the conduit pass flowing pressure relief flow are switched.
  • the portion of the pressure relief line 10 located within the containment 8 has downstream of the inlet port 12 for the gas and vapor mixture (vent gas) flowing from the containment 4 into the pressure relief line 10 in depressurization operation, a recombiner 14 of known design for flameless recombination of hydrogen entrained in the pressure relief stream with oxygen to water vapor.
  • a recombiner 14 of known design for flameless recombination of hydrogen entrained in the pressure relief stream with oxygen to water vapor.
  • a first cooling of the pressure relief flow to a manageable in the downstream cleaning and filtering devices temperature level is still within the containment 8 by a here only schematically indicated, downstream of the recombiner 14 arranged gas cooler 16, the example is recooled by natural draft (natural convection) within the containment 4.
  • the gas cooler 16 can be recooled on the secondary side by a cooling liquid, which is preferably sucked passively by means of a jet pump or the like from a corresponding template within the containment (not shown here).
  • the recooling can also take place partially or completely outside the containment 4.
  • two check valves 20 are connected in series in the pressure relief line 10, which are closed during normal operation of the nuclear facility 6 and to initiate the pressure relief operation in accidents or incidents with significant pressure increase within the containment enclosed by the containment 4 4th be opened.
  • a recuperative heat exchanger 22 is connected in the pressure relief line 10, also referred to as venting line, in which the vent gas is further cooled.
  • the re-cooling of the heat exchanger 22 is preferably carried out by the pressure relief flow at a lower temperature level in a further downstream section of the pressure relief line 10 (see below).
  • the wet scrubber 24 comprises a washing container 26 surrounded on all sides by a surrounding wall with cleaning or washing liquid 28 held therein up to a maximum level, namely essentially water.
  • the vent gas flowing into the wash tank 26 via the pressure relief line 10 enters the washing liquid 28 via a number of parallel-connected venturi nozzles 30.
  • the venturi nozzles 30 are arranged below the liquid level 32.
  • the aerosol particle purified vent gas accumulates in a plenum 34 above the liquid level 32, passes through a liquid separator 36 and then exits the wash tank 26 by entering the next portion of the pressure relief line 10 which is connected to the top of the wash tank 26 is.
  • a throttle valve 38 is connected in the pressure relief line 10, which causes a relaxation and, consequently, a drying of the vent gas (expansion drying).
  • the molecular sieve 42 is primarily for the retention of iodine and iodine-containing compounds, in particular organic compounds with lower Chain length (organoiodine), designed and realized for this purpose, for example, as a zeolite-based sorption filter. Deviating from the graphic representation, the molecular sieve 42 can be structurally integrated into the wet scrubber 26 and directly thermally coupled.
  • the molecular sieve 42 provided for the purpose of iodine retention can as a rule not be regenerated, in contrast to the activated carbon which is used for inert gas retention (see below). It is therefore preferably designed in terms of capacity for the complete pressure relief process, from the beginning to the end. However, it may be a division of the retention capacity provided on several paralall connected molecular sieves.
  • the vent gas discharged from the aerosol filtration in the wet scrubber 24 receives a portion of the heat content from the vent gas entering the wet scrubber 24.
  • the vapor components in the downstream noble gas adsorber columns are reliably prevented from condensing.
  • the pressure relief line 10 in the 3-way valve 46 branches into two parallel sub-strands, in each of which a noble gas adsorber, short adsorber 44, is switched.
  • the two sub-strands in the analogous to the 3-way valve 46 constructed 3-way valve 48 are brought together again (twin arrangement).
  • the two 3-way valves 46, 48 are preferably coupled to each other mechanically or by an associated control electronics, so that in the pressure relief operation, depending on the valve position either one or the other of the two adsorber columns 44 is flowed through by the Ventgas.
  • each active moderately active adsorber 44 contained in the vent gas noble gases, in particular xenon and krypton, retained by dynamic adsorption to an adsorbent.
  • adsorbent / adsorbents can be constructed, for example, from a plurality of layers and / or from a plurality of successive zones of activated carbon and / or zeolite and / or molecular sieves in the flow direction.
  • the throttle valve 38 arranged in the middle line section of the pressure relief line 10 between the wet scrubber 26 and the adsorber columns 44 is set such that a pressure reduction of the vent gas takes place with respect to the first line section, in which the pressure essentially corresponds to the containment pressure, but that there is still an excess pressure Relation to the atmospheric pressure is present.
  • the adsorber columns 44 are thus operated in overpressure in order to reduce the gas volume flowing through them.
  • another throttle valve 50 is disposed in the pressure relief line 10 to effect pressure equalization to the surrounding atmosphere.
  • the pressure relief line thus has a high-pressure section upstream of the throttle valve 38, a middle-pressure section between the two throttle valves 38 and 50 and a low-pressure section downstream of the throttle valve 50.
  • a filter 52 Downstream of the throttle valve 50, a filter 52 for retaining adsorbent particles, which possibly dissolve in the adsorber columns 44 from the adsorbents, into the last line section of the pressure relief line 10th connected. Finally, the cleaned and filtered vent stream is blown into the environment via a chimney 54.
  • both adsorber columns 44 have their maximum uptake and retention capacity.
  • the first one shown in FIG. 1 left adsorber 44 is actively switched, while the right adsorber 44 is decoupled from the pressure relief flow and thus, as it were kept in a standby state.
  • the left Adsorberkolonne 44 is now a selective separation of the noble gases from the carrier gas stream. The column is loaded. Shortly before reaching the capacity limit ("breakthrough") of the left adsorber 44 is then switched to the right adsorber 44.
  • the noble gases previously adsorbed in the left adsorber column 44 are fed back into the containment 4 during the adsorption operation of the right adsorber column 44 (and vice versa after the next switching operation).
  • the adsorber column 44 located in the backwashing operation is thereby regenerated.
  • a rinsing and recirculation system 56 for the adsorber columns 44 is provided, which will be described in more detail below.
  • the purge and recovery system 56 preferably operates passively and is powered by the (post) decay heat of the decay products and activity carriers contained in the containment atmosphere and / or in the pressure relief stream.
  • FIG. 1 variant is shown using the heat of decomposition of the accumulated in the wet scrubber 24 cleavage products a water supply evaporated.
  • the water vapor generated in this way serves as a flushing medium for the adsorber columns 44 and at the same time as a driving medium for a jet pump 58 for transport / promotion of the flushing medium.
  • a steam boiler 62 filled at least partially with water 60, which is thermally attached to the wash tank 26 of the wet scrubber 24 in such a way. is coupled, that a heat transfer from the enriched in the course of the pressure relief operation with fission products washing liquid 28 takes place on the water feed in the steam boiler 62.
  • the steam boiler as shown in FIG. 1 structurally integrated into the wet scrubber 24 or arranged immediately adjacent.
  • the washing liquid 28 and the water 60 in the steam boiler are preferably separated from one another by partitions.
  • water 66 another vaporizable liquid which fulfills the requirements placed on it as a flushing medium and / or as a propellant (see below) could also be provided.
  • a natural circulation loop 64 projecting on the one hand into the washing liquid 28 of the wet scrubber 24 and on the other hand into the water reservoir of the steam boiler 62, in which a suitable transfer medium (heat transfer medium, eg a refrigerant or thermal oils) by natural convection in the manner of a thermosyphon or a heat pipe (heat pipe) circulates with or without phase change and thereby causes the desired heat transfer.
  • a suitable transfer medium heat transfer medium, eg a refrigerant or thermal oils
  • heat pipe heat pipe
  • the steam boiler 62 may be equipped with an auxiliary heater 66 which alternatively operates, preferably also passively, by means of a flow medium heated by the decay heat of the nuclear reactor or for example by means of electrical energy stored in electrical accumulators becomes.
  • the pressurized steam 67 produced in this manner forms above the water level 68 a steam cushion 70 in the steam boiler 62 (steam storage).
  • a removal of the steam takes place with the shut-off Valve 72 via the steam extraction line 74.
  • a first partial flow of the steam flow is used to drive a jet pump 58 (English Steam Injector).
  • a branch line 76 is led from the steam extraction line 74 to the propellant connection 77 of the motive nozzle of the jet pump 58 (of course, instead of a branch line, a direct connection to the steam boiler 62 could also be provided, see also the variant according to FIG.
  • a second partial flow of the steam 67 with a lower mass flow in relation to the first partial flow is conducted via the branch line 80 provided with a throttle valve 78 as the flushing medium to the adsorber column 44, which is currently not active and is decoupled from the pressure relief flow.
  • the branch line 80 can therefore also be referred to as a flushing agent supply line.
  • a branching 82 and downstream shut-off valves 84 alternatively a 3-way valve at the branch 82, the supply of the flushing medium to the currently in flushing adsorber 44 occurs.
  • the flushing takes place here expediently contrary to the present in the adsorption flow.
  • the inlet side for the pressure relief flow forms the outlet side for the detergent flow and vice versa.
  • the noble gases previously adsorbed (adsorbed) in the respective adsorber column 44 are released again (desorbed) and carried away with the flushing agent stream.
  • the adsorber column 44 is thereby refreshed again for the next adsorption cycle.
  • the noble gases dissolved in the rinsing process from the respective adsorber column 44 are conveyed back into the containment 4.
  • the flushing agent discharge line 90 leading away from the adsorber columns 44 is connected to the suction connection 92 of the jet pump 58 and continues on the outlet side in the return line 94, which is guided through the containment 8 into the containment 4.
  • the rinsing agent loaded with inert gases (water vapor under relatively low pressure) is sucked in by the propellant (water vapor under relatively high pressure and high flow velocity), mixed with it under momentum transfer and compressed and via the return line 94 into the Containment 4 transported back.
  • the flushing agent discharge line 90 and the return line 94 together can also be referred to as the recirculation line.
  • two check valves 96 are connected in series in the immediate vicinity of the containment shell 8 so as to be able to close the return line 94 securely in the event of a line break or a leak. As a result, leakage of the containment atmosphere via this line into the environment is prevented in such cases.
  • the connecting line 98 between the washing tank 26 and the return line 94 is used to empty the wet scrubber 24 after completion of the containment pressure relief (venting).
  • the design of the relevant system components of the rinsing and recirculation system 56 on the one hand such that the delivery pressure of the jet pump 58 is sufficient on the pressure side to promote the mixed with the blowing agent, activity-loaded rinse against the prevailing system pressure in the containment 4 back ,
  • the resulting increase in pressure in the containment 4 is small compared to the pressure relief via the pressure relief line 10, so that in fact there is a significant net pressure relief of the containment 4.
  • the jet pump 58 can be operated with a separate propellant gas, in particular nitrogen, which is kept under pressure in a corresponding storage container.
  • jet pump 58 instead of a jet pump 58, other pump types can be used to recover the loaded with inert gases flushing medium in the containment 4.
  • such pumps are passively driven by the decay heat contained in the containment 4.
  • FIG. 2 illustrated variant of the pressure relief and activity restraint system 2 is in contrast to the in FIG. 1 variant shown instead of a wet scrubber 26, a dry filter 100, z. As a sand bed filter, connected in the pressure relief line 10.
  • an alternative heating of the steam boiler 62 may be provided by the decay heat present in the containment 4, as indicated schematically by the double arrow 102.
  • the decay heat present in the containment 4 For this purpose, for example, operated in natural circulation with or without phase transition convection cycles can be led out of the containment 4 through the containment 8.
  • heat pump circuits may also be used, the feed pump of which is preferably driven passively by the available heat sources in the containment 4, possibly also via the detour of other forms of energy (eg compressed air, electricity).
  • the heat source used in this context is, in particular, the catalytic recombiner 14 within the containment 4 and / or the gas cooler 16 downstream of it.
  • nitrogen or another purge gas
  • a separate heating of the adsorber columns 44 can be provided beyond the inherent heating through the vent gas conducted through to the noble gas adsorption.
  • FIG. 3 An advantageous in this context recuperative heating variant, which with the in FIG. 1 and FIG. 2 illustrated embodiments can be combined, is shown in FIG. 3 shown.
  • the hot vent gas is first passed to the adsorber 44 after passing through the security envelope 8 and brought into thermal contact with them for the purpose of heat transfer, before then in the manner described above, a dry filter 100 (alternatively a wet scrubber 24 as in 1) and finally enters the adsorber columns 44 and interacts there with the adsorbents.
  • a dry filter 100 alternatively a wet scrubber 24 as in 1
  • the respective adsorber column 44 may, for example, have a double jacket, wherein the good heat-conducting inner jacket encloses the flow channel containing the adsorbents for the medium-pressure relief stream pre-cleaned in the dry filter 100 (alternatively in the wet scrubber 24).
  • the good heat-conducting inner jacket encloses the flow channel containing the adsorbents for the medium-pressure relief stream pre-cleaned in the dry filter 100 (alternatively in the wet scrubber 24).
  • high-pressure relief flow preferably in countercurrent to the medium-pressure relief flow, and there is a part of its heat content to the inside for heating the adsorber.
  • a passive heat storage may be integrated into the adsorber columns 44, such as a heat storage plate or the like.
  • the depressurization and activity retention system according to the invention is preferably used in a nuclear power plant with a nuclear reactor enclosed by a containment shell, other applications are also possible, for example in a research reactor or in a plant for processing nuclear fuel.
  • an application in non-nuclear industrial plants is conceivable in which hazardous substances are processed within a hermetically sealed containment envelope, and in which accident situations over-design overpressure conditions can occur.

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Plasma & Fusion (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

L'invention concerne un système de décompression et de rétention de la radioactivité (2) destiné à une installation nucléaire (6), en particulier une centrale nucléaire, comprenant un confinement (4) entouré d'une enceinte (8) auquel est reliée une conduite de décompression (10) servant à la décompression en cas de défaillance ou d'accident. Vus dans le sens d'écoulement du flux de décompression, les composants suivants sont montés en série dans la conduite de décompression (10) : un recombineur catalytique (14) servant à transformer l'hydrogène contenu dans le flux de décompression en vapeur d'eau avec de l'oxygène, un dépoussiéreur par voie humide (24) ou en variante un filtre à sec (100) servant à séparer les aérosols du flux de décompression, un segment de conduite comprenant au moins deux tronçons parallèles comportant chacun une colonne d'adsorption (44) destinée à retenir des gaz rares contenus dans le flux de décompression. Un système de lavage et de retour (56) est en outre relié aux colonnes d'adsorption (44), au moins une des colonnes d'adsorption (44) peut être découplée du flux de décompression et mise en mode lavage au moyen de vannes (46, 48, 84, 86) associées. Ce mode lavage permet de refouler dans le confinement (4) les gaz rares accumulés dans cette colonne d'adsorption (44) au moyen d'un produit de lavage et le système de lavage et de retour (56) est conçu comme un système passif qui est entraîné par la chaleur résiduelle contenue dans le confinement (4) ou dans le flux de décompression.
EP14726552.4A 2013-05-17 2014-05-15 Système de décompression et de rétention de la radioactivité pour installation nucléaire Withdrawn EP2997579A1 (fr)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
DE102013209191.5A DE102013209191A1 (de) 2013-05-17 2013-05-17 Druckentlastungs- und Aktivitätsrückhaltesystem für eine kerntechnische Anlage
PCT/EP2014/059950 WO2014184296A1 (fr) 2013-05-17 2014-05-15 Système de décompression et de rétention de la radioactivité pour installation nucléaire

Publications (1)

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EP2997579A1 true EP2997579A1 (fr) 2016-03-23

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EP (1) EP2997579A1 (fr)
JP (1) JP2016521843A (fr)
CN (1) CN105210153A (fr)
DE (1) DE102013209191A1 (fr)
WO (1) WO2014184296A1 (fr)

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CN110523182B (zh) * 2019-09-06 2024-04-12 长江勘测规划设计研究有限责任公司 地下核电站气载放射性过滤***
CN110648770B (zh) * 2019-10-24 2023-02-03 中国舰船研究设计中心 一种反应堆舱超压保护***
JP7266006B2 (ja) * 2020-03-13 2023-04-27 日立Ｇｅニュークリア・エナジー株式会社 原子炉格納容器ベント装置および原子力発電プラント
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WO2014184296A1 (fr) 2014-11-20
DE102013209191A1 (de) 2014-11-20
JP2016521843A (ja) 2016-07-25

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