CA1114585A - Process and apparatus for controlling atmospheric gas inside containment vessel of reactor - Google Patents

Process and apparatus for controlling atmospheric gas inside containment vessel of reactor

Info

Publication number
CA1114585A
CA1114585A CA331,077A CA331077A CA1114585A CA 1114585 A CA1114585 A CA 1114585A CA 331077 A CA331077 A CA 331077A CA 1114585 A CA1114585 A CA 1114585A
Authority
CA
Canada
Prior art keywords
atmospheric gas
cold water
containment vessel
jet pump
reactor
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.)
Expired
Application number
CA331,077A
Other languages
French (fr)
Inventor
Yoichi Takashima
Sadao Hattori
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.)
Doryokuro Kakunenryo Kaihatsu Jigyodan
Original Assignee
Doryokuro Kakunenryo Kaihatsu Jigyodan
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 Doryokuro Kakunenryo Kaihatsu Jigyodan filed Critical Doryokuro Kakunenryo Kaihatsu Jigyodan
Application granted granted Critical
Publication of CA1114585A publication Critical patent/CA1114585A/en
Expired legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C9/00Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
    • G21C9/004Pressure suppression
    • G21C9/012Pressure suppression by thermal accumulation or by steam condensation, e.g. ice condensers
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C13/00Pressure vessels; Containment vessels; Containment in general
    • G21C13/02Details
    • G21C13/022Ventilating arrangements
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

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

Abstract

ABSTRACT
A process for controlling an atmospheric gas inside a containment vessel of a reactor, which comprising leading the atmospheric gas to an intake port of a water jet pump to contact the atmospheric gas with a jet cold water in the jet pump and taking out the atmospheric gas with the jet cold water from the water jet pump. During the contact of the atmospheric gas with the jet cold water, vapor in the atmospheric gas is condensed and floating particles and radioactive materials contained in the atmospheric gas are taken into the jet cold water. Thus, a temperature, humidity, pressure and cleanliness of the atmospheric gas are controlled during normal operation of the reactor, and a pressure and temperature of the atmospheric gas are reduced and the atmospheric gas is purified at the time of accident of the reactor.

Description

5Ei ~
BACKGROUND OF THE INVENTION

This invention re]ates to a process and apparatus for controlling an atmospheric gas inside a containment vessel of a nuclear reactor. More specifically, it relates to a process and apparatus enabling to control an atmospheric gas inside a containment vessel of a reactor during normal opera-tion of the reactor, and also to conduct the reduction of the pressure and temperature of the atmospheric gas and the purification of the atmospheric gas at the time of accident of the reactor.
As an apparatus for controlling an atmospheric gas inside a containment vessel of a reactor, there have convention-ally been provided two loops, i.e., a recycling loop of the atmospheric gas inside the containment vessel during normal operation of the reactor and a spray loop inside the contain-ment vessel at the time of accident of the reactor. These two . ~ . .. ;r loops are disposed independently of each other.
The recycling loop system of the atmospheric gas inside the containment vessel during normal operation of the reactor generally comprises, as illustrated in Figure 1, a pre-filter 1, a heating coil 2, a cooling coil 3, a high performance filter 4, a blower 5, a heater 6,acharcoal filter7, a charcoal filter by-pass valve 8 for normal operation and so on. This recycling loop system removes floating particles and radioac-tive materials contained in the atmospheric gas inside the containment vessel 10 of the reactor and also controls its temperature or the like.

On the other hand, the spray loop system of the contain-m0nt vessel comprises, as shown ir. Figure 2, sparger headers ~'` ..
- 2 - ~

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11 disposed at the upper part in the containment vessel 10 of the reactor, a cold water pool 12 below a floor 12 at the bottom of the containment vessel, a cooling system 14 equip-ped to the cold water pool 13 and a piping arrangement that is equipped with a valve and a pump 15 and connects the cold water pool 13 to the sparger headers 11. When coolant of the reactor is discharged into the containment vessel at the time of accident of the reactor and the internal pressure of the containment vessel is thereby elevated, this spary loop system sprays the cold water and rapidly reduces the pressure in order to reduce possible leak of radioactive materials inside the containment vessel to the outside. Hence, this loop is not at all necessary during normal operation of the reactor.
However, one serious problem with this spray loop system of the containment vessel is that its actual running test is extremely difficult. Although performance tests of the spary loop system are carried out under the test conditions as close as possible to the actual operating conditions such as the initial performance test after construction of the loop system or the periodical performance test during its operation in order to ensure its full performance, the possible range of these tests is lnevitably restricted in comparison with the actual operation of the loop system. Of greater importance is the fact that when the spray loop system operates erroneous-y, intruments inside the containment vessel would be submerged with water. As matters now stand, therefore, installation of an automatic operation signal system has been avoided for fear of this trouble or an interlocking arrangement has been made to preventthe erroneous action of the spray loop system.

~' 5~i In other words, in this kind of conventional setups, the spray loop system of the containment vessel must be disposed, although it is not at all necessary for the normal operation of the reactor. Moreover, the spray loop system itself is not yet free from several problems in its reliability such ~ as in its responsibility and action.

; SUMMARY OF THE INVENTION
'' ; It is therefore an object of the present invention to provide a process and apparatus for controlling an atmospheric gas inside a containment vessel of a reactor which can solve the abovementioned drawbacks of the prlor art and can be used as a controlling system of the atmospheric gas inside the containment vessel during normal operation of the reactor and also as pressure reducing-, cooling- and purifying-systems at the time of accident.
, It is another object of the present invention to provide a process and apparatus for controlling an atmospheric gas 1 inside a containment vessel of a reactor having high relia-;'l bility in operation which not only can be used during normal operation of the reactor, but also make effective pressure-control at the time of accident.
Briefly stated, in accordance with a process of the in-vention for controlling an atmospheric gas inside a contain-ment vessel of a reactor, the atmospheric gas is first led to an intake port of a water jet pump, then brought into con-tact with a jet cold water in the jet pump and taken out ; together with the jet cold water from the water jet pump.

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During the contact of the atmospheric gas with the jet cold water, vapor contained in the atmospheric gas is condensed, the gas is cooled and such matters as floating particles and radioactive materials contained in the atmospheric gas are taken into the jet cold water. In this manner, it is possible, during normal operation of the reactor, to control the tem-perature, humidity, pressure and cleanliness of the atmospheric ; gas and at the time of accident of the reactor, to reduce the pressure and temperature of the atmospheric gas and to make its purification.
The apparatus for controlling the atmospheric gas inside the containment vessel of the reactor for practising the abovementioned process in accordance with the present invention comprises a water jet pump, a cold water pool and means for feeding the cold water from the cold water pool to the water :; jet pump. The atmospheric gas is adapted to be led to an intake port of the water jet pump.
In an embodiment of the present invention, the water jet pump is placed in the space inside the containment vessel ; while the cold water pool is disposed at the bottom of the ~s containment vessel. The cold water is supplied from this cold water pool to the water jet pump. The cold water jetted ~ from the water jet pump is returned to the cold water pool at -~ the bottom of the containment vessel while the gas taken out from the water jet pump together with the;jet cold water is agaln diffused into the containment vessel as the atmospheric gas.
At the time of accident of the reactor, the jet cold water and the atmospheric gas that are jetted together from the water jet pump may be withdrawn outside the containment , - 5 -.. ' , ' ', . ~ .. ', ' ' .. ' . . ' .~

vessel, and then subjected to the gas-liquid separation whereby the cold water is returned to the cold water pool and the atmospheric gas may be purified and then discharged through a smokestack.
The present invention will be more apparent from the fol-` lowing description of the preferred embodiments, taken in ; conjunction with the accompanying drawings.

. ~ .
BRIEF DESCRIPTION OF THE DRAWINGS
, . ~
Figure 1 is a schematic view of a conventional recycling loop system of an atmospherlc gas in a containment vessel of a reactor;
Figure 2 is a schematic view of a conventional spray loop j system of a containment vessel;
Figure 3 is a schematic view of an embodiment of the .~ , .
~ present invention;
:: I
` `~ Figure 4 is a schematic view illustrating a construction of an example of a water jet pump to be used in the present d nventlon, an ' Figure 5 is a schematic view of another embodiment of the :. . ~ ~ .
~present invention.
,''.'`' .,, ::, , .
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~ DETAIL DESCRIPTION OF THE INVENTION
;
Referring now to Figure 3, two water jet pumps 20 are disposed to face downwardly at two positions of different heights inside a containment vessel 10 of a reactor, and a ,, - . . ~ ., . . . . . . . - . . . . . .

;: :

cold water pool 13 is disposed below a floor 12 of the bottom of the containment vessel thereinside. The cold water pool 13 is equipped with a cooling system 14 so as to always cool the pool water. The cold water pool 13 is communicated with each water jet pump 20 by a piping system 21. Of course, the water jet pumps 20 are set in such a place that the cold water jetted from the pumps does not moisten instruments within the containment vessel 10. Thus, the water jet pump are preferably disposed in corners inside the containment vessel. If necessary, means for preventing scattering of water may be equipped below the water jet pumps.~
The water jet pump 20 used in the present invention is one which has conventionally been employed for taking out r ambient gas present therearound by means of water, and its schematic construction is shown in Figure 4. As can be seen clearly from this drawing, its principal portion consists of a cold water jet nozzle 22, a jet chamber 23, a throat 24 and a diffuser 25. When high pressure cold water i.e., driving fluid is jetted from the jet nozzle 22 toward the throat 24, ., gas inside the jet chamber 23 is taken out by the water and its pressure is reduced. Hence, the gas i.e., fluid to be driven, present around an intake port 26 is sucked into the jet chamber 23 through the intake port and at the same time, is carried away by the jet cold water.
The pool water, that is constantly cooled and stored in the cold water pool 13, is sucked up when the pump 15 is actuated, and is jetted from the jet nozzle 22 of each water jet pump 20. The atmospheric gas, generally an air~vapor mixture gas, inside the containment vessel present around the pump, is sucked by the jet of the cold water and floating :: ~ - :- . : : . : ::: : : , . . : : : .

1~145i~;3 particles and radioactive materials in the gas are taken into the cold water and thus removed. At the same time, the vapor is condensed and the atmospheric gas is cooled upon contact of the cold water with the atmospheric gas. The temperature and pressure of the atmospheric gas can be controlled by, for example, first detecting the temperature and pressure inside the containment vessel and then adjusting the opening of the *
discharge valve of the water jet pump 20 so as to control the output of the pump 20. During normal operation, the reactor is operated at its full output and its heat radiation quantity -, ... .
'r~' is great. Therefore, if the water jet pump having an air ex-traction capacity sufficient enough to remove such heat radia-~ tion quantity is provided, the contemplated object can be -~ ; accomplished even at the time of accident of the reactor.
It is of course easy to make such a design that the pres--sure-reducing effect and the cooling effect of the atmospheric gas are automatically enhanced at the time of accident.
,, Since the air control system for emergency use is constantly ;~ in operation to provide against the accident of the reactor during its normal operation, reliability of its action is ; extremely high. Further, the air control system which is ,~
~ constantly in operation, is caused to shift automatically to .
~` the air control system for emergency use at the time of ~ .
accident of the reactor. Accordingly, the pressure control effect is extremely excellent in comparison with the conven-tional spray loop system inside the containment vessel which starts to operate with a time lag of at least 10 minutes.
Figure 5 illustrates another embodiment of the present invention which has fundamentally the same construction as the embodiment shown in Figure 3, and which discharges the l~ s~i atmospheric gas inside the containment vessel through a smokestack after purifying the atmospheric gas. The water jet pump 20 is disposed to face downwardly in the upper space s inside the containment vessel 10 of the reactor and the cold , water pool 13 is disposed below the bottom floor 12 of the containment vessel thereinside. The cold water pool 13 is equipped with the cooling system 14. The pool water is con-~` ¦ stantly cooled by the cooling system 14, is sucked up by the pump 15 and supplied to the water jet pump 20. The atmospheric gas present around the pump 20 is taken out by the cold water strèam that is jetted from the cold water jet nozzle of the t water jet pump 20. A piping 30 extends through the wall of the containment vessel 10 from the diffuser porti-on, and the '~ jet water and the atmospheric gas are taken out of the con-tainment vessel 10 through this piping 30. A drain trap 31 is placed at the intermediate position of the p1ping 30 and the water content collected in the trap 31 is returned to the cold water pool 13 inside the containment vessel 10 through a return line 32. The gas containing the radioactive materials or the like is fed into a reservoir tank 34 by a compressor I ~ 33, is properIy controlled there, then purified through a rare gas hold-up column 35 and finally discharged outside through a smokestack 36.
, `j .
, Though the cold water pool is shown disposed inside the , ~ ' 1, containment vessel in the abovementioned embodiments, it may - of course be disposed outside the containment vessel. The water jet pump also may be disposed outside the containment vessel. In such a case, the containment vessel and the intake port of the water jet pump are communicated with each other by a piping.
.. .
"J _ g _ - : :: ::: : : ' . : . . :: : : :- :': ,.::: . . . ..
. ~ . ~ , ,: .. : . . . ~, -- :- :

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As explained above, the present invention has such a con-struction that the floating particles and radioactive materials i in the atmospheric gas are collected into water by permitting , ~ I ,.*
i the atmospheric gas to be sucked into the water jet pump and at the same time, the vapor contained in the atmospheric gas is condensed and the gas itself is cooled upon its contact with .. . .
``~ the cold water. Accordingly, the invention is able not only , to control the temperature, pressure, humidity and cleanliness"~
of the atmospheric gas inside the containment vessel during the normal operation of the reactor but also to function as a ~ ~ safety system which restricts the pressure elevation inside 1~ the containment vessel and removes the radioactive materials at the time of accident of the reactor such as a loss of ,.", , coolant of the reactor. Since the system of the invention is .:
constantly in operation during normal operation of the reactor, .~ reliability of its action at the time of accident of the reactor , ~ is inherently high. Further, the system of the present inven-tion eliminates the troublesome test procedures of the con-, ventional spray loop system inside the containment vessel which requires the incessant and periodical preformance tests in order to secure and confirm its action to cope with the accident of the reactor. It is still another excellent advan-age realized by the present invention that the system of the invention is free from the problem of the conventional spray loop system which, upon its mal-function, hinders the reactor :itself in its subsequent operation.
While the invention has been described with respect to preferred embodiments, it should be apparent to those killed in the art that numerous modifications may be made thereto without departing from the scope of the invention.

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Claims (11)

THE EMBODIMENTS OF THE INVENTION IN WHICH AN EXCLUSIVE
PROPERTY OR PRIVILEGE IS CLAIMED ARE DEFINED AS FOLLOWS:
1. A process for controlling an atmospheric gas inside a containment vessel of a reactor, which comprising:
leading the atmospheric gas to an intake port of a water jet pump to contact the atmospheric gas with a jet cold water in the water jet pump; and taking out the atmospheric gas with the jet cold water from the water jet pump;
during the contact of the atmospheric gas with the jet cold water, vapor in the atmospheric gas being condensed, the gas being cooled, and floating particles and radioactive materials contained in the atmospheric gas being taken into the jet cold water, whereby the temperature, humidity, pressure and cleanliness of the atmospheric gas are controlled during normal operation of the reactor, and the reduction of the pressure and temperature of the atmospheric gas and the purification of the atmospheric gas are accomplished at the time of accident of the reactor.
2. The process according to claim 1, wherein the tempera-ture and pressure of the atmospheric gas are controlled by first detecting the temperature and pressure inside the con-tainment vessel and then controlling the output of the water jet pump.
3. The process according to claim 1, wherein the gas taken out together with the jet cold water from the water jet pump is again diffused into the containment vessel as an atmospheric gas thereof.
4. The process according to claim 1, wherein the gas taken out together with the jet cold water from the water jet pump is discharged outside the containment vessel.
5. The process according to claim 1, wherein the jet cold water is supplied from a cold water pool disposed at the bottom of the containment vessel and the cold water jetted from the water jet pump is returned to the cold water pool.
6. The process according to claim 1, wherein the jet cold water is supplied from a cold water pool disposed outside the containment vessel and the cold water jetted from the water jet pump is returned to the cold water pool.
7. An apparatus for controlling an atmospheric gas inside a containment vessel of a reactor, which comprising :
a water jet pump, the atmospheric gas being led to an intake port of the pump;
a cold water pool; and means for supplying the cold water from the cold water pool to the water jet pump.
8. The apparatus according to claim 7, wherein the water jet pump is disposed inside the containment vessel.
9. The apparatus according to claim 7, wherein the water jet pump is disposed outside the containment vessel, and the inside of the containment vessel is communicated with the intake port of the water jet pump by a piping.
10. The apparatus according to claim 7, wherein the cold water pool is disposed at the bottom of the containment vessel thereinside.
11. The apparatus according to claim 7, wherein the cold water pool is disposed outside the containment vessel.
CA331,077A 1978-07-14 1979-07-04 Process and apparatus for controlling atmospheric gas inside containment vessel of reactor Expired CA1114585A (en)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
JP53-85730 1978-07-14
JP8573078A JPS5513829A (en) 1978-07-14 1978-07-14 Method of preparing surrounding gas in nuclear reactor containment vessel

Publications (1)

Publication Number Publication Date
CA1114585A true CA1114585A (en) 1981-12-22

Family

ID=13866951

Family Applications (1)

Application Number Title Priority Date Filing Date
CA331,077A Expired CA1114585A (en) 1978-07-14 1979-07-04 Process and apparatus for controlling atmospheric gas inside containment vessel of reactor

Country Status (4)

Country Link
JP (1) JPS5513829A (en)
CA (1) CA1114585A (en)
DE (1) DE2928425C2 (en)
FR (1) FR2431164A1 (en)

Families Citing this family (10)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS57142589A (en) * 1981-02-27 1982-09-03 Hitachi Ltd Vent container
DE3127804A1 (en) * 1981-07-14 1983-02-10 Schweiger, W., Dr.-Ing., 8039 Puchheim METHOD FOR PREVENTING OR INHIBITING A MIXING OF THE ATMOSPHERES EXISTING IN A CLOSED ROOM WITH A GAS-LIKE MATERIAL IN THE ROOM
DE3143989C1 (en) * 1981-11-05 1983-02-03 Kraftwerk Union AG, 4330 Mülheim Nuclear power plant with a containment
JPS59121523U (en) * 1983-02-03 1984-08-16 三菱電機株式会社 bearing mechanism
ES2048264T3 (en) * 1989-10-26 1994-03-16 Siemens Ag PROCEDURE AND DEVICE FOR THE REDUCTION OF PRESSURE IN A PRESSURE DEPOSIT.
CN103871507A (en) * 2012-12-13 2014-06-18 中国核动力研究设计院 Pressurized water reactor nuclear power plant pressurizer spraying apparatus
CN104751910A (en) * 2013-12-31 2015-07-01 中国广核集团有限公司 Emergency spray cooling system for containment in accident condition of nuclear power plant
CN106158056B (en) * 2015-04-17 2018-06-08 国家电投集团科学技术研究院有限公司 For the cooling system and cooling means of nuclear power plant containment shell
JP6705730B2 (en) * 2016-10-14 2020-06-03 日立Geニュークリア・エナジー株式会社 Nuclear power generation system
JP6741618B2 (en) * 2017-03-29 2020-08-19 三菱重工業株式会社 PCV maintenance equipment

Family Cites Families (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
AT219724B (en) * 1959-04-25 1962-02-12 Bbc Brown Boveri & Cie Device for cooling and cleaning gases that escape from circuits in nuclear reactors in the event of leaks
DE1146598B (en) * 1961-06-14 1963-04-04 Siemens Ag Safety device for the buildings of power nuclear reactors
DE2203107C3 (en) * 1972-01-24 1981-06-04 Interatom Internationale Atomreaktorbau Gmbh, 5060 Bergisch Gladbach Method and device for accelerating the condensation of the steam emerging from the pressure vessel of a water-cooled nuclear reactor in the event of damage

Also Published As

Publication number Publication date
JPS5728918B2 (en) 1982-06-19
FR2431164A1 (en) 1980-02-08
JPS5513829A (en) 1980-01-31
FR2431164B1 (en) 1983-01-07
DE2928425C2 (en) 1986-02-20
DE2928425A1 (en) 1980-02-28

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