WO1996030912A1 - A system for the dissipation of heat from the interior of a containment structure of a nuclear reactor - Google Patents
A system for the dissipation of heat from the interior of a containment structure of a nuclear reactor Download PDFInfo
- Publication number
- WO1996030912A1 WO1996030912A1 PCT/EP1996/001213 EP9601213W WO9630912A1 WO 1996030912 A1 WO1996030912 A1 WO 1996030912A1 EP 9601213 W EP9601213 W EP 9601213W WO 9630912 A1 WO9630912 A1 WO 9630912A1
- Authority
- WO
- WIPO (PCT)
- Prior art keywords
- heat
- metal wall
- wall
- metal
- walls
- Prior art date
Links
- 229910052751 metal Inorganic materials 0.000 claims abstract description 61
- 239000002184 metal Substances 0.000 claims abstract description 61
- 239000012530 fluid Substances 0.000 claims abstract description 8
- 230000001174 ascending effect Effects 0.000 claims description 18
- 238000000605 extraction Methods 0.000 claims description 13
- 230000001464 adherent effect Effects 0.000 claims description 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 21
- 238000010438 heat treatment Methods 0.000 description 8
- 230000017525 heat dissipation Effects 0.000 description 7
- 230000000694 effects Effects 0.000 description 4
- 238000007710 freezing Methods 0.000 description 3
- 230000008014 freezing Effects 0.000 description 3
- 238000007789 sealing Methods 0.000 description 3
- 238000001816 cooling Methods 0.000 description 2
- 238000009434 installation Methods 0.000 description 2
- 230000007246 mechanism Effects 0.000 description 2
- 230000003014 reinforcing effect Effects 0.000 description 2
- DGAQECJNVWCQMB-PUAWFVPOSA-M Ilexoside XXIX Chemical compound C[C@@H]1CC[C@@]2(CC[C@@]3(C(=CC[C@H]4[C@]3(CC[C@@H]5[C@@]4(CC[C@@H](C5(C)C)OS(=O)(=O)[O-])C)C)[C@@H]2[C@]1(C)O)C)C(=O)O[C@H]6[C@@H]([C@H]([C@@H]([C@H](O6)CO)O)O)O.[Na+] DGAQECJNVWCQMB-PUAWFVPOSA-M 0.000 description 1
- 229910000831 Steel Inorganic materials 0.000 description 1
- 230000004913 activation Effects 0.000 description 1
- 239000004568 cement Substances 0.000 description 1
- 239000003795 chemical substances by application Substances 0.000 description 1
- 238000009833 condensation Methods 0.000 description 1
- 230000005494 condensation Effects 0.000 description 1
- 230000007423 decrease Effects 0.000 description 1
- 238000001704 evaporation Methods 0.000 description 1
- 230000008020 evaporation Effects 0.000 description 1
- -1 for example Substances 0.000 description 1
- 230000005484 gravity Effects 0.000 description 1
- 239000013529 heat transfer fluid Substances 0.000 description 1
- 239000011810 insulating material Substances 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 239000003758 nuclear fuel Substances 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 239000012857 radioactive material Substances 0.000 description 1
- 238000009877 rendering Methods 0.000 description 1
- 230000000284 resting effect Effects 0.000 description 1
- 230000000717 retained effect Effects 0.000 description 1
- 229920006395 saturated elastomer Polymers 0.000 description 1
- 229910052708 sodium Inorganic materials 0.000 description 1
- 239000011734 sodium Substances 0.000 description 1
- 239000007921 spray Substances 0.000 description 1
- 239000010959 steel Substances 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
- 238000006467 substitution reaction Methods 0.000 description 1
Classifications
-
- 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
- G21C15/18—Emergency cooling arrangements; Removing shut-down heat
-
- 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 to a system for dissipating heat from the interior of a containment structure of a nuclear reactor, particularly for the dissipation of heat which would be generated in the case of an unexpected and accidental malfunctioning of the normal cooling systems.
- nuclear reactors with their associated primary cooling circuit, are housed within a primary containment structure of steel or concrete usually made of several layers or walls.
- This primary containment structure is in turn housed within a building the side walls and the roof of which communicate with the external environment.
- the manner in which the heat is dissipated must be of passive type, that is to say it must not depend upon the operation of manual or automatic control systems, the activation of pumps or the like, the opening of valves, or the availability of sources of energy of any type, but must be intrinsically activated by natural physical phenomena connected with permanent structural characteristics.
- the side walls and the top being insulating materials, constitute an obstacle to the dissipation of heat.
- Heat dissipation systems comprising hydraulic circuits which have external heat exchangers and heat exchangers within the containment structure through which a heat transfer fluid flows in natural circulation.
- the external heat exchangers must be of very large dimensions since they must have a particularly extensive heat exchange surface, and therefore have a high cost. Moreover, in normal operating conditions of the nuclear reactor and with winter temperatures outside, the heat exchange fluid contained in the external heat exchanger can freeze rendering the heat dissipation system ineffective.
- hydraulic circuits if subjected to rupture, constitute a preferential escape route from the containment structure for radioactive material.
- the object of the present invention is that of making available a system for the dissipation of heat which makes it possible for the above- mentioned disadvantages of the prior art to be overcome.
- This object is achieved by a system for the dissipation of heat, of the type specified, as defined in the characterising part of the attached Claim 1.
- FIG. 1 is a sectional view of a nuclear reactor containment building, of the type having two concrete walls, which incorporates a heat dissipation system according to the invention
- figure 2 is a perspective view, partially in section, of a detail of the system of figure 1 ;
- FIG. 3 is a partial sectioned view, of a containment building, of the single concrete wall type, of a nuclear reactor which incorporates a different embodiment of the system according to the invention
- - figure 4 is a schematic partial perspective view, in section, of a detail of the building and system of figure 3; and - figure 5 is a partially sectioned perspective view of a detail of the system of figure 3.
- a nuclear reactor containment building is generally indicated with the reference numeral 1. It houses the nuclear reactor itself, indicated 2.
- the building 1 comprises an inner concrete containment structure 3, of substantially cylindrical form, which has a base 4, side walls 5 and a top wall 6.
- the side and top walls 5, 6 have a common internal surface 7 which generally defines and encloses an internal environment 8 of the inner containment structure 3.
- the inner containment structure 3 of the reactor is enclosed in an outer concrete containment structure 9, also of substantially cylindrical form, which also rests on the base 4 and has side walls 5' and a top wall 6'.
- the containment building 1 is associated with a heat dissipation system generally indicated 10.
- This comprises a first metal wall 11 backing onto the side walls 5 and the top wall 6 within the said internal containment structure 3 in such a way as almost completely to cover the inner surface 7 but maintained from it by a substantially constant distance.
- the said first metal wall 11 is formed by a plurality of contiguous internal sheets 12 disposed in superimposed circumferential rows 13 starting from the base 4 of the inner containment structure 3 and entirely covering the top wall 6.
- Each successive row 13 is rested on horizontal beams 14, preferably of the double-T type, rigidly fixed to the inner surface 7 of the side and top walls 5, 6, which in succession form a ring 15 for each circumferential row 13 of inner plates 12 which, as well as being supported on the underlying horizontal double-T beams 14, is connected to the overlying horizontal double-T beams 14 in such a way as to be put in mechanical engagement between counter posed horizontal double-T beams 14.
- the system 10 includes a second metal wall 16 formed by a plurality of contiguous intermediate plates 17 corresponding to the inner plates 12, which rest on the horizontal double-T beams 14 and are rigidly fixed to the said internal surface 7 of the inner containment structure 3. Overall, then, the second metal wall 16 is adherent to the internal surface 7 and is rigidly fixed to it.
- the second metal wall 16 is also fixed in its own plane with respect to the side and top walls 5, 6.
- the installation 10 further includes an interspace 18 confined by the said first and second walls 1 1 , 16 and subdivided into a plurality of sectors 19 which are delimited by the horizontal double-T beams 14 and by vertical beams 20, preferably of the double-T type, disposed between the first and second walls 1 1 , 16 in engagement with the horizontal double-T beams 14 and corresponding to the contiguous edges of the internal and intermediate plates 12, 17.
- hydraulic sealing members 21 which in this example are bellows.
- the interspace 18 of each sector 19 is entirely sealed.
- the interspace 18 contains a heat collection fluid 20, in this embodiment water, which does not completely fill each sector 19 but leaves an air and steam header chamber 33.
- a heat collection fluid 20 in this embodiment water, which does not completely fill each sector 19 but leaves an air and steam header chamber 33.
- the absolute pressure within each sector 19 and therefore, generally, within the interspace 18 is at a predetermined value generally not greater than atmospheric pressure and advantageously less than 10,000 Pa.
- the air content is also limited to facilitate the heat exchange phenomenon by evaporation and condensation.
- each sector 19 is contained a vertical corrugated metal sheet
- the system 10 further includes means 24 for the passive extraction of the heat from the said interspace 18.
- the said means 24 for the passive extraction of heat comprise a plurality of inner condensers 25 contained in the space 30 between the containment structures 3 and 9.
- Each inner condenser 25 corresponds to a respective sector 19 of the interspace 18 located on the side walls 5 of the inner containment structure
- the means 24 further include a plurality of apertures 31 formed in the outer containment structure 9 between the outside and the space 30 and disposed close to the top walls 6, 6'.
- the said means 24 include a descending channel 33 within the space 30, starting from the said apertures 31 , and a corresponding ascending channel 34.
- the said channels 33, 34 are defined by a third metal wall 32 disposed vertically within the space 30 in an intermediate position between the side walls 5, 5' of the inner and outer containment structures 3, 9 and connected to the top wall 6' of the outer containment structure 9.
- the third metal wall 32 does not extend down to the base 4 such that it divides the space 30 into the descending channel 33, communicating with the outside through the apertures 31 , and the ascending channel 34, in which the internal condensers 25 are located, the said channels 33 and 34 therefore being concentric and communicating at their lower ends.
- the means 24 for the passive extraction of heat further includes a chimney 35 located centrally on the top wall 6' of the outer containment structure 9, which puts the ascending channel 34 into communication with the outside.
- the means 24 comprise a plurality of outer condensers 25' disposed outside the building 1 on the top wall 6' of the outer containment structure 9.
- These outer condensers 25' are in hydraulic communication with the said sectors 19 by means of tubes 36 and are preferably immersed in corresponding water-filled baths 37 formed on the top wall 6' of the outer containment structure 9.
- the outer condensers 25' are also located in elevated positions with respect to the corresponding sectors 19 of the interspace 18.
- the condensers 25, 25' are only filled with air and steam from the sector 19 to which they are connected and at the same pressure thereas.
- the temperature of the water 22 contained in the interspace 18 is largely influenced by the temperature of the environment 8 rather than the temperature outside the building 1 so that the said water 22 does not run the risk of freezing.
- the air within the containment structure 3 of the reactor 2 is subject to a strong heating.
- the nuclear reactor 2 is of the water-cooled type it is very probable that a large quantity of steam will also be liberated.
- each inner sheet 12 curves towards the interior of the sector 19 compressing the corrugated sheet 40.
- the second metal wall 16 will also be subjected to heating and, resting on the inner surface 7 of the inner containment structure 3 will compress transferring the force to which it is subjected directly to the structure 3.
- the water 22 in the interspace 18 begins to boil releasing saturated steam into each condenser 25, 25' which, consequently, will be subject to heating.
- the heating of the internal condensers 25 initiates natural circulation of the outside air through the apertures 31 , the descending and ascending channels 33, 34 and the chimney 35.
- the temperature of the outside air is generally less than the saturation temperature of the water 22 contained in the interspace 18 so that, within the tube bundles 28 the steam condenses returning by gravity to the interior of the respective sector 19.
- the outer condensers 25' heat the water in the baths 37 which evaporates condensing the steam contained in each outer condenser 25'.
- a containment building of a nuclear reactor is of the single concrete containment structure type, indicated 3, which has a base 4, side walls 5 and a top wall 6.
- the heat dissipation system 10 comprises a first metal wall 11 positioned as in the preceding embodiment, formed by a plurality of contiguous inner sheets 12 rigidly fixed together in such a way that the said first wall 11 is self supporting and rests on the base 4. Rings 15 of horizontal double-T beams 14 are suspended to the first metal wall 11 by means of a plurality of hooks 41.
- the system 10 further includes a second metal wall 16 positioned as in the previous example but spaced from the inner surface 7 in such a way as to leave free a space 30' between itself and the side and top walls 5, 6.
- the second metal wall 16 is also self supporting and rests on the base 4. The first and second metal wall 11 , 16 are therefore free to move within their own planes with respect to the side and top walls 5, 6.
- first and second movable walls 11 , 16 are each free to move within their own planes with respect to the other.
- hydraulic sealing members 21 which, in this embodiment, are bellows.
- the system 10 includes a cage 42 of metal beams 43 located between the second metal wall and the side and top walls 5, 6 of the containment structure 3.
- the system 10 for the passive dissipation of heat further includes means 24 for the extraction of the heat from the said interspace 18, which in this embodiment of the invention includes the said second metal wall 16.
- the means 24 further include a plurality of apertures 31 formed in the containment structure 3 between the outside and the space 30' and disposed in proximity to the top wall 6, a descending channel 33 and an ascending channel 34 defined by the relative position of the metal beams 43 of the cage 42.
- the descending channel 33 communicates with the outside through the apertures 31 and the ascending channel 34 is delimited on one side by the said second metal wall 16.
- the means 24 for the passive extraction of heat further includes a chimney 35 located centrally on the top wall 6 of the containment structure 3, which puts the space 30' into communication with the outside.
- the thermal communication between the interspace 18 and the outside is ensured through the second metal wall 16 which presents a wide surface contacted by the air in natural circulation.
- the temperature of the water 22 contained in the interspace 18 is greatly influenced by the temperature of the environment 8 rather than the temperature outside the building 1 , so that the said water 22 does not run the risk of freezing.
- the second metal wall 16 will also be subject to heating but this too is free to expand, like the first metal wall 11 , contacting against the cage 42 which contains it by making use of the expansion space 44.
- Heating of the second metal wall 16 initiates natural circulation of outside air through the aperture 31 , the descending and ascending channels 33, 34 and the chimney 35 which cools the second metal wall 16 and therefore also the water 22 in the interspace 18.
- the increase of pressure in the interspace 18 is supported by the double-T beams 14, 20 and by the second metal wall 16 which, however, is held rigid being engaged with the beams 43 of the cage 42.
- the principal advantage associated with the heat dissipation system according to the present invention lies in the fact that the efficiency of the means for passive extraction of heat, increased by the effect of the mechanisms which increase the thermal exchange coefficients with the outside air, allows a reduction in the heat exchange surface.
- the freezing of the fluid which accumulates the heat is prevented by keeping it entirely within the reactor containment building.
- the metal walls provide a supplementary containment for preventing the escape of radioactive agents.
- the temperature within the reactor containment structure can be reduced progressively, after the occurrence of the accident situation, down to values below 100°C. Consequently, the pressure within the building can be held under control for an indefinite period.
- the presence of the double-T beams, supported either by the containment structure or by the second metal wall, increases the ability of the whole system to resist seismic events.
- the system according to the invention having an entirely passive function, lends itself to be integrated with any devices having an active function in such a way as to improve its performance if it is possible for them to be utilised.
- conventional cold water spray systems on the second metal wall can be envisaged to increase the extraction of heat from the interspace.
- This system can be applied also to preexisting containment buildings in substitution for, or in addition to, active intervention systems.
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- 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
Description
Claims
Priority Applications (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
EP96909102A EP0818044A1 (en) | 1995-03-30 | 1996-03-21 | A system for the dissipation of heat from the interior of a containment structure of a nuclear reactor |
AU52726/96A AU5272696A (en) | 1995-03-30 | 1996-03-21 | A system for the dissipation of heat from the interior of a containment structure of a nuclear reactor |
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
IT95MI000640A IT1275709B1 (en) | 1995-03-30 | 1995-03-30 | SYSTEM FOR THE DISPOSAL OF HEAT FROM THE INSIDE OF A CONTAINMENT STRUCTURE OF A NUCLEAR REACTOR |
ITMI95A000640 | 1995-03-30 |
Publications (1)
Publication Number | Publication Date |
---|---|
WO1996030912A1 true WO1996030912A1 (en) | 1996-10-03 |
Family
ID=11371130
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
PCT/EP1996/001213 WO1996030912A1 (en) | 1995-03-30 | 1996-03-21 | A system for the dissipation of heat from the interior of a containment structure of a nuclear reactor |
Country Status (4)
Country | Link |
---|---|
EP (1) | EP0818044A1 (en) |
AU (1) | AU5272696A (en) |
IT (1) | IT1275709B1 (en) |
WO (1) | WO1996030912A1 (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
KR101374751B1 (en) * | 2012-07-17 | 2014-03-17 | 한국수력원자력 주식회사 | Passive decay heat removal system using organoic fluid, method of driving heat removal system |
Citations (7)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2274120A1 (en) * | 1974-06-05 | 1976-01-02 | Teplotekhnichesky Inst Im | SYSTEM FOR LIMITING THE CONSEQUENCES OF AN ACCIDENT AT A NUCLEAR POWER PLANT |
GB2183894A (en) * | 1985-12-02 | 1987-06-10 | Gen Electric | Radiant vessel auxiliary cooling system |
EP0393805A2 (en) * | 1989-04-21 | 1990-10-24 | Westinghouse Electric Corporation | Passive containment cooling apparatus and method |
US5076999A (en) * | 1990-10-10 | 1991-12-31 | The United States Of America As Represented By The United States Department Of Energy | Passive decay heat removal system for water-cooled nuclear reactors |
JPH0472597A (en) * | 1990-03-27 | 1992-03-06 | Fuji Electric Co Ltd | Decay heat removing device for high temperature gas-cooled reactor |
DE4127313A1 (en) * | 1991-08-17 | 1993-02-18 | Kernforschungsz Karlsruhe | Passive heat removal from reactor safety vessel - includes splitting heat-entraining air flow in interspace into 2 streams, so that only smaller stream passes through filter, reducing filter area requirement |
US5255296A (en) * | 1992-06-24 | 1993-10-19 | Westinghouse Electric Corp. | Collecting and recirculating condensate in a nuclear reactor containment |
-
1995
- 1995-03-30 IT IT95MI000640A patent/IT1275709B1/en active IP Right Grant
-
1996
- 1996-03-21 AU AU52726/96A patent/AU5272696A/en not_active Abandoned
- 1996-03-21 EP EP96909102A patent/EP0818044A1/en not_active Withdrawn
- 1996-03-21 WO PCT/EP1996/001213 patent/WO1996030912A1/en not_active Application Discontinuation
Patent Citations (7)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2274120A1 (en) * | 1974-06-05 | 1976-01-02 | Teplotekhnichesky Inst Im | SYSTEM FOR LIMITING THE CONSEQUENCES OF AN ACCIDENT AT A NUCLEAR POWER PLANT |
GB2183894A (en) * | 1985-12-02 | 1987-06-10 | Gen Electric | Radiant vessel auxiliary cooling system |
EP0393805A2 (en) * | 1989-04-21 | 1990-10-24 | Westinghouse Electric Corporation | Passive containment cooling apparatus and method |
JPH0472597A (en) * | 1990-03-27 | 1992-03-06 | Fuji Electric Co Ltd | Decay heat removing device for high temperature gas-cooled reactor |
US5076999A (en) * | 1990-10-10 | 1991-12-31 | The United States Of America As Represented By The United States Department Of Energy | Passive decay heat removal system for water-cooled nuclear reactors |
DE4127313A1 (en) * | 1991-08-17 | 1993-02-18 | Kernforschungsz Karlsruhe | Passive heat removal from reactor safety vessel - includes splitting heat-entraining air flow in interspace into 2 streams, so that only smaller stream passes through filter, reducing filter area requirement |
US5255296A (en) * | 1992-06-24 | 1993-10-19 | Westinghouse Electric Corp. | Collecting and recirculating condensate in a nuclear reactor containment |
Non-Patent Citations (1)
Title |
---|
PATENT ABSTRACTS OF JAPAN vol. 016, no. 276 (P - 1374) 19 June 1992 (1992-06-19) * |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
KR101374751B1 (en) * | 2012-07-17 | 2014-03-17 | 한국수력원자력 주식회사 | Passive decay heat removal system using organoic fluid, method of driving heat removal system |
Also Published As
Publication number | Publication date |
---|---|
IT1275709B1 (en) | 1997-10-17 |
ITMI950640A0 (en) | 1995-03-30 |
EP0818044A1 (en) | 1998-01-14 |
AU5272696A (en) | 1996-10-16 |
ITMI950640A1 (en) | 1996-09-30 |
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