US20160225470A1 - Apparatus for degassing a nuclear reactor coolant system - Google Patents

Apparatus for degassing a nuclear reactor coolant system Download PDF

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Publication number
US20160225470A1
US20160225470A1 US14/612,461 US201514612461A US2016225470A1 US 20160225470 A1 US20160225470 A1 US 20160225470A1 US 201514612461 A US201514612461 A US 201514612461A US 2016225470 A1 US2016225470 A1 US 2016225470A1
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US
United States
Prior art keywords
contactor
nuclear reactor
power plant
gas
outlet
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.)
Abandoned
Application number
US14/612,461
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English (en)
Inventor
Gary J. Corpora
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.)
Westinghouse Electric Co LLC
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Westinghouse Electric Co LLC
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 Westinghouse Electric Co LLC filed Critical Westinghouse Electric Co LLC
Priority to US14/612,461 priority Critical patent/US20160225470A1/en
Assigned to WESTINGHOUSE ELECTRIC COMPANY LLC reassignment WESTINGHOUSE ELECTRIC COMPANY LLC ASSIGNMENT OF ASSIGNORS INTEREST (SEE DOCUMENT FOR DETAILS). Assignors: CORPORA, GARY J.
Priority to CN201680008509.8A priority patent/CN107206292A/zh
Priority to EP16746926.1A priority patent/EP3253476B1/fr
Priority to ES16746926T priority patent/ES2744438T3/es
Priority to RU2019133152A priority patent/RU2793943C2/ru
Priority to JP2017538334A priority patent/JP2018510326A/ja
Priority to TR2019/10817T priority patent/TR201910817T4/tr
Priority to KR1020177024555A priority patent/KR20170113616A/ko
Priority to PCT/US2016/012272 priority patent/WO2016126356A1/fr
Priority to CN202010971098.0A priority patent/CN112076501A/zh
Priority to RU2017130911A priority patent/RU2704220C2/ru
Priority to TW105103046A priority patent/TWI666652B/zh
Priority to TW108121756A priority patent/TWI690941B/zh
Publication of US20160225470A1 publication Critical patent/US20160225470A1/en
Priority to US15/407,508 priority patent/US10566101B2/en
Priority to JP2020081744A priority patent/JP2020126073A/ja
Abandoned legal-status Critical Current

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Classifications

    • 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
    • G21C19/303—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 specially adapted for gases
    • 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
    • B—PERFORMING OPERATIONS; TRANSPORTING
    • B01—PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL
    • B01D—SEPARATION
    • B01D19/00—Degasification of liquids
    • B01D19/0031—Degasification of liquids by filtration
    • B—PERFORMING OPERATIONS; TRANSPORTING
    • B01—PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL
    • B01D—SEPARATION
    • B01D19/00—Degasification of liquids
    • B01D19/0036—Flash degasification
    • B—PERFORMING OPERATIONS; TRANSPORTING
    • B01—PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL
    • B01D—SEPARATION
    • B01D53/00—Separation of gases or vapours; Recovering vapours of volatile solvents from gases; Chemical or biological purification of waste gases, e.g. engine exhaust gases, smoke, fumes, flue gases, aerosols
    • B01D53/22—Separation of gases or vapours; Recovering vapours of volatile solvents from gases; Chemical or biological purification of waste gases, e.g. engine exhaust gases, smoke, fumes, flue gases, aerosols by diffusion
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • 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
    • G21C19/307—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 specially adapted for liquids
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D3/00—Control of nuclear power plant
    • 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
    • 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
    • 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
    • G21C19/20—Arrangements for introducing objects into the pressure vessel; Arrangements for handling objects within the pressure vessel; Arrangements for removing objects from the pressure vessel
    • G21C19/207—Assembling, maintenance or repair of reactor components
    • 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
    • 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 present invention relates generally to a process for removing dissolved gasses from reactor coolant in a nuclear power plant and more particularly to apparatus for removing dissolved hydrogen and fission gases from the reactor coolant by passing the coolant over a membrane and extracting the gasses by applying a vacuum.
  • some fission gases e.g., xenon and krypton, created by the fission reactions occurring in the nuclear fuel, may enter the reactor coolant system and become dissolved in the reactor coolant.
  • the concentration of radioactive gases and hydrogen must be reduced to avoid excessive radiation exposure to plant maintenance inspection personnel and reduce the likelihood of an explosion due to a potential spark setting off a flammable mixture of air and hydrogen in the containment atmosphere.
  • Reactor coolant has previously been degassed using a volume control tank connected to the reactor coolant system.
  • the reactor coolant system primarily includes such nuclear steam supply system components as the reactor vessel, the steam generators, the reactor coolant pumps and the connecting piping.
  • the volume control tank is part of the system known as the chemical and volume control system which operates in the degassing mode by flashing the dissolved hydrogen and radioactive gases out of the reactor coolant and into the vapor space of the volume control tank.
  • An example of such a system could be found in U.S. Pat. No. 4,647,425.
  • letdown flow a relatively small flow of reactor coolant referred to as the letdown flow is diverted from the reactor coolant system and through the chemical and volume control system.
  • This stream is first cooled then purified in a mixed bed demineralizer, filtered to remove dissolved ionic or suspended particulate material and passed to the volume control tank.
  • U.S. Pat. No. 4,647,425 proposes an improvement to this chemical and volume control system procedure and reduces the time required to effectively degas the reactor coolant.
  • the method proposed by the patent provides for vacuum degassing a reactor coolant system. The method comprises draining down the reactor coolant system to approximately the mid-point of the hot leg and maintaining the reactor coolant system in an unvented condition during the drain-down operation. Any flashed reactor coolant in the primary side of the steam generator is then refluxed.
  • flashed reactor coolant means liquid coolant which flashes into the steam phase as a result of lower ambient pressure. Refluxed means condensed and cooled.
  • the bulk of the reactor coolant as well as the refluxed reactor coolant, are circulated through a residual heat removal system to cool the reactor coolant.
  • a vacuum is drawn on the reactor coolant system to evacuate any gas stripped from the reactor coolant.
  • the step of draining the coolant system establishes a partial vacuum in the unvented reactor vessel and reactor coolant system during drain-down. The partial vacuum is sufficient to cause the reactor coolant to boil at the prevailing temperatures in the reactor coolant system whereby the degassing occurs during the drain-down step.
  • FIG. 1 shows one prior art embodiment of a vacuum degassing system 10 that is currently in use.
  • the letdown flow enters the system at the inlet 12 and is directed to an inlet 14 of a degasifier column vessel 16 where it enters the interior of the vessel through a spray head 18 .
  • a vacuum is drawn on the vessel through conduit 20 by the degasifier vacuum pumps 36 .
  • Excess reactor coolant which is not evaporated is drawn from the vessel by discharge pumps 22 , with pulse dampeners 24 employed to smooth out the pulses generated by the diaphragm discharge pumps 22 .
  • the coolant that is drawn through the discharge pumps 22 is exhausted to a holding tank 26 for return to the system or disposal.
  • the water vapor and non-condensable gases that are separated from the coolant in the degasifier column 16 are routed through a demister 28 to remove any entrained coolant and conveyed to a vapor condenser 30 in which it is placed in heat exchange relationship with chilled water that enters and exits the vapor condenser through inlets and outlets 32 and 34 .
  • the radioactive gases and hydrogen are then drawn by vacuum pumps 36 to a degasifier separator 38 .
  • the separated coolant is then drawn off by the degasifier separator pumps 40 and discharged to the holding tank 26 .
  • the radioactive gas and hydrogen are vented from the degasifier separator 38 vapor space to the reactor plant radioactive waste gas system 42 .
  • the nitrogen purge line 44 is provided to purge any residual hydrogen and radioactive gases prior to maintenance.
  • a nuclear reactor power plant sub-system for removing radioactive gases and hydrogen gas from a reactor coolant.
  • the sub-system includes a contactor housing a membrane that divides an interior of the contactor housing into an inlet chamber and an outlet chamber, wherein the membrane has pores that pass the radioactive and the hydrogen gases from the inlet chamber to the outlet chamber, but prevent the reactor coolant from passing through to the outlet chamber.
  • a vacuum generator is connected to the outlet chamber for drawing a vacuum on the outlet chamber.
  • a liquid outlet conduit is connected to an outlet nozzle on the inlet chamber for conveying a degasified portion of the reactor coolant to a desired location.
  • a gas outlet conduit is connected to an outlet nozzle on the outlet chamber for conveying the radioactive and hydrogen gases to a nuclear reactor power plant waste gas system.
  • a “sweep” gas system is connected to the outlet chamber for supplying a relatively small inert gas purge flow in the outlet chamber and preferably, the inert gas is nitrogen.
  • the sweep gas in combination with the application of a vacuum, enhances the efficiency of the membranes for dissolved gas removal, thus minimizing the required number of contactors.
  • the contactor housing comprises a plurality of contactor housings connected in parallel. Alternately, the contactor housings may be connected in series.
  • the contactor housing comprises a plurality of contactor housings with at least some of the plurality of contactor housings connected in parallel and some of the parallel connected contactor housings are connected in series with at least one other of the plurality of contactor housings.
  • the contactors may be operated without a sweep gas, but may require additional contactors in series and/or parallel.
  • FIG. 1 is a schematic layout of a prior art vacuum degasification system
  • FIG. 2 is a schematic layout of one embodiment of the components of this invention that replace the portion of the system of FIG. 1 within the dotted lines;
  • FIG. 3 is a schematic layout of the system of FIG. 2 with an additional contactor housing placed in series with the two parallel arrangements of contactor housings to further improve the quality of the output.
  • This invention utilizes a known and established technology of gas membranes to remove dissolved gases from the reactor coolant. While this is a known and proven technology for some applications, it has not been previously employed to handle mildly acidic and radioactive solutions as exists in interfacing with the primary coolant of a nuclear reactor system, as evidenced by the alternative reactor degasing systems proposed in the past and described in the evaluation of prior art set forth in the Background of U.S. Pat. No. 4,647,425.
  • one or more alternate “contactors” which respectively house a gas membrane are aligned in series and/or parallel, as required to handle the desired flow and the degree of gas removal.
  • a vacuum is applied to the gas side of the membrane to pull dissolved gases from the liquid through tiny pores in the walls of the membrane.
  • a small inert gas sweep gas e.g., nitrogen, flow on the vacuum side is used to enhance dissolved gas removal. This gas flow minimizes the number of required contactors.
  • FIGS. 2 and 3 show two contactors 46 in parallel though it should be appreciated that one, three or four or more contactors may be employed in parallel as necessary to handle the rate of flow that is required.
  • FIG. 3 shows the two contactors in parallel as shown in FIG. 2 , with a third contactor in series with the output of the two contactors in parallel to further reduce the amount of gases that may remain within the degassed coolant stream.
  • the letdown stream enters the system at the inlet 12 and is distributed through inlet conduit 48 to each of the inlets 50 on the contactors 46 .
  • a vacuum is applied to the gas side of the membrane at the gas outlet 52 by the vacuum pumps 54 and a small inert gas flow, preferably of nitrogen, is introduced at the gas inlets 56 from a nitrogen source 58 .
  • inert gas is meant a gas that will not react with the stripped gasses, i.e., the radioactive gases or hydrogen, to form an undesirable or hazardous gas mixture when vented to the waste gas system.
  • helium gas may be used, whereas oxygen may not be used.
  • the membrane within the contactor 46 has pores small enough to prevent the coolant from passing to the gas outlet 52 , but large enough to enable the hydrogen and radioactive gases to pass through the membrane.
  • Such contactors are available commercially, such as Liqui-Cel, available from Membrana Corporation, Charlotte, N.C.
  • the degasified coolant then exits the contactor 46 at the outlet 60 and is conveyed by the outlet conduit 62 to a holding tank 26 where it can be returned to the reactor system or disposed of.
  • As many contactors 46 can be arranged in parallel as necessary to handle as much volume of gas laden coolant as is needed to be recycled or disposed of.
  • the extracted hydrogen and radioactive gases and the nitrogen sweep gas are then circulated by the vacuum pumps 54 to the plant radioactive gas waste system 42 .
  • the nitrogen source 58 also provides flow in the gas lines to purge the gas exit side of the system, for maintenance.
  • a source of clean demineralized water 44 is provided for flushing of the liquid side of the contactors and piping prior to maintenance.
  • FIG. 3 is identical to FIG. 2 except an additional contactor 46 is positioned in series with the parallel arrangement of contactors 46 shown in FIG. 2 and provides another stage of degasification to enhance the purity of the coolant that exits the system. Sensors are provided throughout the system to monitor the efficacy of the process.

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  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • High Energy & Nuclear Physics (AREA)
  • General Engineering & Computer Science (AREA)
  • Chemical & Material Sciences (AREA)
  • Plasma & Fusion (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Analytical Chemistry (AREA)
  • General Chemical & Material Sciences (AREA)
  • Oil, Petroleum & Natural Gas (AREA)
  • Degasification And Air Bubble Elimination (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
  • Separation Using Semi-Permeable Membranes (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
US14/612,461 2015-02-03 2015-02-03 Apparatus for degassing a nuclear reactor coolant system Abandoned US20160225470A1 (en)

Priority Applications (15)

Application Number Priority Date Filing Date Title
US14/612,461 US20160225470A1 (en) 2015-02-03 2015-02-03 Apparatus for degassing a nuclear reactor coolant system
RU2017130911A RU2704220C2 (ru) 2015-02-03 2016-01-06 Аппарат для дегазации системы охлаждения ядерного реактора
TR2019/10817T TR201910817T4 (tr) 2015-02-03 2016-01-06 Bir nükleer reaktör soğutucu sistemin gazdan giderilmesine yönelik aparat.
PCT/US2016/012272 WO2016126356A1 (fr) 2015-02-03 2016-01-06 Appareil de dégazage d'un système de refroidissement de réacteur nucléaire
ES16746926T ES2744438T3 (es) 2015-02-03 2016-01-06 Aparato para desgasificar un sistema refrigerante de reactor nuclear
RU2019133152A RU2793943C2 (ru) 2015-02-03 2016-01-06 Аппарат для дегазации системы охлаждения ядерного реактора
JP2017538334A JP2018510326A (ja) 2015-02-03 2016-01-06 原子炉冷却材系の脱ガス装置
CN201680008509.8A CN107206292A (zh) 2015-02-03 2016-01-06 用于为核反应堆冷却系统脱气的设备
KR1020177024555A KR20170113616A (ko) 2015-02-03 2016-01-06 원자로 냉각재 시스템을 탈가스시키기 위한 장치
EP16746926.1A EP3253476B1 (fr) 2015-02-03 2016-01-06 Appareil de dégazage d'un système de refroidissement de réacteur nucléaire
CN202010971098.0A CN112076501A (zh) 2015-02-03 2016-01-06 用于从核反应堆冷却剂中去除放射性气体和氢气的方法
TW108121756A TWI690941B (zh) 2015-02-03 2016-01-30 將放射性氣體及氫氣自一核反應器冷卻劑移除之方法
TW105103046A TWI666652B (zh) 2015-02-03 2016-01-30 核反應器冷卻劑系統之去氣裝置
US15/407,508 US10566101B2 (en) 2015-02-03 2017-01-17 Apparatus for degassing a nuclear reactor coolant system
JP2020081744A JP2020126073A (ja) 2015-02-03 2020-05-07 原子炉冷却材系の脱ガス装置

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US14/612,461 US20160225470A1 (en) 2015-02-03 2015-02-03 Apparatus for degassing a nuclear reactor coolant system

Related Child Applications (1)

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US15/407,508 Continuation US10566101B2 (en) 2015-02-03 2017-01-17 Apparatus for degassing a nuclear reactor coolant system

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US20160225470A1 true US20160225470A1 (en) 2016-08-04

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Application Number Title Priority Date Filing Date
US14/612,461 Abandoned US20160225470A1 (en) 2015-02-03 2015-02-03 Apparatus for degassing a nuclear reactor coolant system
US15/407,508 Active 2036-09-05 US10566101B2 (en) 2015-02-03 2017-01-17 Apparatus for degassing a nuclear reactor coolant system

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US15/407,508 Active 2036-09-05 US10566101B2 (en) 2015-02-03 2017-01-17 Apparatus for degassing a nuclear reactor coolant system

Country Status (10)

Country Link
US (2) US20160225470A1 (fr)
EP (1) EP3253476B1 (fr)
JP (2) JP2018510326A (fr)
KR (1) KR20170113616A (fr)
CN (2) CN107206292A (fr)
ES (1) ES2744438T3 (fr)
RU (1) RU2704220C2 (fr)
TR (1) TR201910817T4 (fr)
TW (2) TWI666652B (fr)
WO (1) WO2016126356A1 (fr)

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CN109323354A (zh) * 2018-09-27 2019-02-12 中国科学院上海应用物理研究所 一种熔盐仿真堆堆舱负压排风装置
WO2020244762A1 (fr) 2019-06-06 2020-12-10 Framatome Gmbh Système de dégazage pour centrale nucléaire et procédé de dégazage d'un flux de fluide de refroidissement de réacteur

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CN107680703A (zh) * 2017-11-08 2018-02-09 上海核工程研究设计院有限公司 一种核电站放射性废液系统的脱气子系统
FR3089673B1 (fr) 2018-12-05 2021-10-29 Electricite De France Procédé et système de traitement membranaire pour le dégazage d’effluents aqueux issus d’un circuit primaire de centrale nucléaire
CN111180096A (zh) * 2020-02-21 2020-05-19 三门核电有限公司 一种压水堆核电厂一回路物理除氧方法

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