CA1132413A - Nuclear steam generator tubesheet shield - Google Patents
Nuclear steam generator tubesheet shieldInfo
- Publication number
- CA1132413A CA1132413A CA347,315A CA347315A CA1132413A CA 1132413 A CA1132413 A CA 1132413A CA 347315 A CA347315 A CA 347315A CA 1132413 A CA1132413 A CA 1132413A
- Authority
- CA
- Canada
- Prior art keywords
- tubesheet
- shell
- fluid
- steam generator
- shaped tubes
- 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
Links
- 239000012530 fluid Substances 0.000 claims abstract description 33
- 238000005253 cladding Methods 0.000 claims abstract description 16
- 239000000463 material Substances 0.000 claims description 6
- 229910019589 Cr—Fe Inorganic materials 0.000 claims description 4
- 229910045601 alloy Inorganic materials 0.000 claims description 4
- 239000000956 alloy Substances 0.000 claims description 4
- 238000004326 stimulated echo acquisition mode for imaging Methods 0.000 abstract description 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 6
- XLYOFNOQVPJJNP-ZSJDYOACSA-N Heavy water Chemical compound [2H]O[2H] XLYOFNOQVPJJNP-ZSJDYOACSA-N 0.000 description 4
- 238000009835 boiling Methods 0.000 description 4
- 230000035882 stress Effects 0.000 description 4
- 239000007791 liquid phase Substances 0.000 description 2
- 230000035939 shock Effects 0.000 description 2
- 230000001052 transient effect Effects 0.000 description 2
- 238000005452 bending Methods 0.000 description 1
- 238000005336 cracking Methods 0.000 description 1
- 210000003041 ligament Anatomy 0.000 description 1
- 239000007788 liquid Substances 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 238000005192 partition Methods 0.000 description 1
- 239000012071 phase Substances 0.000 description 1
- 238000006467 substitution reaction Methods 0.000 description 1
- 230000008646 thermal stress Effects 0.000 description 1
- KUAZQDVKQLNFPE-UHFFFAOYSA-N thiram Chemical compound CN(C)C(=S)SSC(=S)N(C)C KUAZQDVKQLNFPE-UHFFFAOYSA-N 0.000 description 1
Classifications
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F22—STEAM GENERATION
- F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
- F22B1/00—Methods of steam generation characterised by form of heating method
- F22B1/02—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers
- F22B1/023—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers with heating tubes, for nuclear reactors as far as they are not classified, according to a specified heating fluid, in another group
- F22B1/025—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers with heating tubes, for nuclear reactors as far as they are not classified, according to a specified heating fluid, in another group with vertical U shaped tubes carried on a horizontal tube sheet
Landscapes
- Engineering & Computer Science (AREA)
- Life Sciences & Earth Sciences (AREA)
- Sustainable Development (AREA)
- Sustainable Energy (AREA)
- Physics & Mathematics (AREA)
- Thermal Sciences (AREA)
- Mechanical Engineering (AREA)
- General Engineering & Computer Science (AREA)
- Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
Abstract
NUCLEAR STEAM GENERATOR TUBESHEET SHIELD
ABSTRACT
A nuclear steam generator is provided which includes an integral preheater zone. The upper face of the tubesheet in the preheater zone is provided with ductile cladding which acts as a thermal shield to prevent incoming feed fluid from thermally shocking the tubesheet.
ABSTRACT
A nuclear steam generator is provided which includes an integral preheater zone. The upper face of the tubesheet in the preheater zone is provided with ductile cladding which acts as a thermal shield to prevent incoming feed fluid from thermally shocking the tubesheet.
Description
.3~3 NUCLEAR STEAM GENER~ R TUBESHEET SHIELD
~, - BACKGROUND OF THE INVEMTION
~`
This invention relates to U-tube type heat exchangers, and more particularly, to nuclear steam generators. In U-tube type heat exchanges a first heat exchange fluid is passed into a shell within which a bundle of upstanding U-shaped tubes is disposed, with the ends of the tubes being secured in a tubesheet adjacent the bottom of the heat exchanyer.
Simultaneously a second heat exchange fluid is passed through the tubes. As the first fluid passes over the outer surfaces of `- the tubes it comes in an indirect heat exchange relation with the second fluid that is passing through the tubes. When the , second fluid is at a higher temperature than the first fluid, the first fluid is thereby heated, ana a portion of the first fluid is converted to vapor. Heated first fluid rises within the heat exchanger, and the vapor is thereafter separated from the li~uid phase of the heated first fluid. The liquid phase of the heated first fluid is recirculated within the shell, being returned to the lower portion of the steam generator through a downcomer space defined between the inner wall of the heat exchanger shell and the outer wall of a shroud disposed around the tube bundle.
The thermal effectiveness of a U-tube heat exchanger, such as a nuclear steam generator, can sometimes be improved by $$
~ ,~
incorporating an integral preheater into -the unit. When an in-tegral preheater is employed, relati~ely cold feedwater is introduced in-to the heat exchanger just above -the tubeshee-t.
Feedwater temperature normally is within a range of from 115C.
-to approximately 190C., whereas the tubeshee-t temperature may be approximately 260C. When the relatively cold feedwater impinges upon the tubesheet, i-t can shock the tubesheet and result in fatigue cracking of the tubesheet.
It has previously been suggested that a plate be disposed above the tubesheet in the preheater zone in order to shield the tubesheet from the incoming feed water. However, when plate-type shields are used, cold feed water can leak from the preheater zone to the boiling zone through clearances existing between the tubes and tube holes formed through the shield. If the tubes are contact rolled into the plate-type shield to preclude such leakage, residual tube stresses can be imposed on the tubing. Furthermore, additional stresses, due to misalignment of tubes, radial differential thermal expansion between the tubesheet and the plate~type shield, and/or out-of-plane bending of the tubesheet because of differential pressureacross the tubesheet, can also be introduced when tubes are rolled into a plate-type shield. Another disadvantage of a plate-type shield is that uncertain ther~al/hydraulic conditions - can exist under the plate-type shield.
~, -2-~L3~L3 The presen-t invention provides a shield for -the upper I face of -the tubesheet which precludes thermal shock of the tubesheet and also avoids leakage and stress problems attendant to plate-type shields.
UMM RY OF THE INVENTION
~ In accordance wi-th an illustrative embodiment `: demonstrating features and advantages of the present invention, there is provided a nuclear steam generator of the type in which a plurality of U-shaped tubes are connected at opposite ends to a tubesheet and extend hetween inlet and outlet chambers, and the steam generator includes an integral preheater zone adjacent ;~ downflow legs of the U-shaped tubes. The improvement comprises a thermal shield disposed adjacent an upper face of the tubesheet within the preheater zone, the shield including ductile cladding material applied directly to the upper face of the tubesheet with the downflow legs of the U-shaped tubes extending through the cladding into the tubesheet. The ductile cladding acts as a thermal shield to prevent incoming feed fluid from thermally shocking the tubesheet, steady-state and transient thermal stress in ligaments of the tubesheet being ~!
primarily confined to the cladding material. Because of its ductility and fatigue properties, the cladding absorbs such stresses.
, ,~
~3~3 D SCRIPTION OF THE DR~WINC,S
FIG. ] is an elevational view of a nucJear steam gen erator incorporating the -thermal shield of the present invention;
and FI~. 2 is a sectional view of a portion of the steam generator of FIG. l.
DESCRIPTION OF THE PREFERRED EMBODIMENT
Referring to FIG. 1 there is shown a nuclear steam generator 10 which includes a cylindrical shell 12 within which a bundle of U-shaped tubes 14 is disposed. Tubes 14 include upflow legs 16 communicatiny with tubesheet 18 at one end and downflow legs 20 communicating with tubesheet 18 at another end thereof. A header 22 is attached to the underside of tube-sheet 18, and together with the underside of tubesheet 18 and a partition plate 24 define an inlet chamber 26 and an outlet chamber 28. An inlet 30 is provided for introducing a heat exchange fluid, such as heavy water, into inlet chamber 26;
this fluid is referred to as tubeside fluia. Similarly, an outlet 32 is provided for removal of tubeside heat exchange fluid from outlet chamher 28. An inlet 34 is provided for introducing another heat exchange fluid, referred to as shell-side fluid, into shell 12. The shellside heat exchange fluid, which could be water, for example, passes over the outer surfaces of tubes 14, and a por-tion of this fluid is vapor-ized. The heated shellside fluid thereafter rises into the upper section 36 above section 12 within which separators (not shown) are disposed for separating the vapor from the heated -- fluid. The vapor is ultimately removed from the steam gener-ator 10 through outlet 3~, while the liquid phase is recircu-lated through downcomer space 37 to boiling zone 39.
Turniny to FIG. 2, a more detailed sectional view of the cylindrical shell 12 of steam generator 10 is shown.
_~ .
~L~32~3 Adjacen-t inle~ 3~ is a prehea-ter or econornizer zone ~0. The preheater zone ~0 is defined by -the inner wall of a generally semi-cylindrical sec-tion of shroud ~2, a section ~3 of the upper face of tubesheet 18, and a first plate 4~. Plate 4~ extends across a diametrial tube-free zone ~6 formed between upflow legs 16 and downflow legs 20 of U-tubes 14, and is welded to shroud 42 along its side edges. A second plate 9~ is also disposed within zone 46, being closer to upflow legs 16 than is first plate 44. Plate 48 is also welded to shroud 42, but extends beyond shroud 42 to shell 12.
E'eed water at a -temæerature within a range of from 115C. to approximately 190C is introduced through inlet 34 into preheater zone ~0. The tubesheet 18 and shell 12 are at a temperature of approximately 260~C. during normal full load op-eration of the steam generator 10. However, it should be- under-stood that the temperatures of the tubesheet and the feedwater can vary during transient conditions, and these "normal" temp-eratures are used herein only to illustrate possible temperature differences between the feedwater and the tubeshee-t. A thermal ; 20 shield 50 is disposed above section ~3 of the upper face of tubesheet 18 in the preheater zone 40. Thermal shield 50 comprises a weld deposit of ductile Ni-Cr-Fe alloy having a finished thick-ness of approximately 6.35mm. The weld deposit, or cladding, is applied to the tubesheet before holes are formed in the tube-sheet for receiving the ends of U-tubes 1~. Therefore a tight fit is assured between the thermal shield 50 and the tubes 1~.
Since the cladding is applied directly to the face of the tubesheet, thereby eliminating any space between the cladding and the tubeshee~
face, lea]cage of feed water from the preheater zone ~0 to the boil-ing zone 39 is not possible. Although in the preferred embodimenta Ni-Cr-Fe alloy ma-terial is used as cladding, other weld material haviny similar ductility and fatigue properties can be employed.
In operation relatlvely cold feedw~ter is introduced through inlet 34 into the preheater zone 40 of steam generator 10. Relatively hot fluid, such as heavy water, is introduced thro~lgh inlet 30 into chamber 26. The hot fluid rises through upflow l.egs 16 of U-tubes 14, coming .in contact with the colder shellside fluid and giving of a portion of its hea-t there-to.
The tubeside fluid is then returned through downflow legs 20 and empties into chamber 28 from which it is removed through outlet 32. The incoming feed water falls within shell.12 on to ~.hermal shi.eld 50 disposed above section 43 o:E the upper face of tubeshee-t 18 in preheater zone 40. Shield 50 acts to prevent the relatively cold shellside fluid from thermally shocking tubesheet 18. After the colder fluid is preheated :~ within zone 40, it rises and continues to absorb addltional heat as it contacts the outer surfaces of U-tubes 14. Upon ris-. ing into upper section 36, vapor is separated from the heated .~ shellside fluid, and is later removed through outlet 38. Sep-arated shellside liquid is recirculated through downcomer space 37 to boiling zone 39.
A latitude of modification, change and substitution is intended in the foregoing disclosure and in some instances some features of the invention will be employed without a corresponding use of other features. Accordingly, it is appropriate that the appended claims be construed broadly and in a manner consisten-t with the spirit and scope of the inven-tion herein.
~, - BACKGROUND OF THE INVEMTION
~`
This invention relates to U-tube type heat exchangers, and more particularly, to nuclear steam generators. In U-tube type heat exchanges a first heat exchange fluid is passed into a shell within which a bundle of upstanding U-shaped tubes is disposed, with the ends of the tubes being secured in a tubesheet adjacent the bottom of the heat exchanyer.
Simultaneously a second heat exchange fluid is passed through the tubes. As the first fluid passes over the outer surfaces of `- the tubes it comes in an indirect heat exchange relation with the second fluid that is passing through the tubes. When the , second fluid is at a higher temperature than the first fluid, the first fluid is thereby heated, ana a portion of the first fluid is converted to vapor. Heated first fluid rises within the heat exchanger, and the vapor is thereafter separated from the li~uid phase of the heated first fluid. The liquid phase of the heated first fluid is recirculated within the shell, being returned to the lower portion of the steam generator through a downcomer space defined between the inner wall of the heat exchanger shell and the outer wall of a shroud disposed around the tube bundle.
The thermal effectiveness of a U-tube heat exchanger, such as a nuclear steam generator, can sometimes be improved by $$
~ ,~
incorporating an integral preheater into -the unit. When an in-tegral preheater is employed, relati~ely cold feedwater is introduced in-to the heat exchanger just above -the tubeshee-t.
Feedwater temperature normally is within a range of from 115C.
-to approximately 190C., whereas the tubeshee-t temperature may be approximately 260C. When the relatively cold feedwater impinges upon the tubesheet, i-t can shock the tubesheet and result in fatigue cracking of the tubesheet.
It has previously been suggested that a plate be disposed above the tubesheet in the preheater zone in order to shield the tubesheet from the incoming feed water. However, when plate-type shields are used, cold feed water can leak from the preheater zone to the boiling zone through clearances existing between the tubes and tube holes formed through the shield. If the tubes are contact rolled into the plate-type shield to preclude such leakage, residual tube stresses can be imposed on the tubing. Furthermore, additional stresses, due to misalignment of tubes, radial differential thermal expansion between the tubesheet and the plate~type shield, and/or out-of-plane bending of the tubesheet because of differential pressureacross the tubesheet, can also be introduced when tubes are rolled into a plate-type shield. Another disadvantage of a plate-type shield is that uncertain ther~al/hydraulic conditions - can exist under the plate-type shield.
~, -2-~L3~L3 The presen-t invention provides a shield for -the upper I face of -the tubesheet which precludes thermal shock of the tubesheet and also avoids leakage and stress problems attendant to plate-type shields.
UMM RY OF THE INVENTION
~ In accordance wi-th an illustrative embodiment `: demonstrating features and advantages of the present invention, there is provided a nuclear steam generator of the type in which a plurality of U-shaped tubes are connected at opposite ends to a tubesheet and extend hetween inlet and outlet chambers, and the steam generator includes an integral preheater zone adjacent ;~ downflow legs of the U-shaped tubes. The improvement comprises a thermal shield disposed adjacent an upper face of the tubesheet within the preheater zone, the shield including ductile cladding material applied directly to the upper face of the tubesheet with the downflow legs of the U-shaped tubes extending through the cladding into the tubesheet. The ductile cladding acts as a thermal shield to prevent incoming feed fluid from thermally shocking the tubesheet, steady-state and transient thermal stress in ligaments of the tubesheet being ~!
primarily confined to the cladding material. Because of its ductility and fatigue properties, the cladding absorbs such stresses.
, ,~
~3~3 D SCRIPTION OF THE DR~WINC,S
FIG. ] is an elevational view of a nucJear steam gen erator incorporating the -thermal shield of the present invention;
and FI~. 2 is a sectional view of a portion of the steam generator of FIG. l.
DESCRIPTION OF THE PREFERRED EMBODIMENT
Referring to FIG. 1 there is shown a nuclear steam generator 10 which includes a cylindrical shell 12 within which a bundle of U-shaped tubes 14 is disposed. Tubes 14 include upflow legs 16 communicatiny with tubesheet 18 at one end and downflow legs 20 communicating with tubesheet 18 at another end thereof. A header 22 is attached to the underside of tube-sheet 18, and together with the underside of tubesheet 18 and a partition plate 24 define an inlet chamber 26 and an outlet chamber 28. An inlet 30 is provided for introducing a heat exchange fluid, such as heavy water, into inlet chamber 26;
this fluid is referred to as tubeside fluia. Similarly, an outlet 32 is provided for removal of tubeside heat exchange fluid from outlet chamher 28. An inlet 34 is provided for introducing another heat exchange fluid, referred to as shell-side fluid, into shell 12. The shellside heat exchange fluid, which could be water, for example, passes over the outer surfaces of tubes 14, and a por-tion of this fluid is vapor-ized. The heated shellside fluid thereafter rises into the upper section 36 above section 12 within which separators (not shown) are disposed for separating the vapor from the heated -- fluid. The vapor is ultimately removed from the steam gener-ator 10 through outlet 3~, while the liquid phase is recircu-lated through downcomer space 37 to boiling zone 39.
Turniny to FIG. 2, a more detailed sectional view of the cylindrical shell 12 of steam generator 10 is shown.
_~ .
~L~32~3 Adjacen-t inle~ 3~ is a prehea-ter or econornizer zone ~0. The preheater zone ~0 is defined by -the inner wall of a generally semi-cylindrical sec-tion of shroud ~2, a section ~3 of the upper face of tubesheet 18, and a first plate 4~. Plate 4~ extends across a diametrial tube-free zone ~6 formed between upflow legs 16 and downflow legs 20 of U-tubes 14, and is welded to shroud 42 along its side edges. A second plate 9~ is also disposed within zone 46, being closer to upflow legs 16 than is first plate 44. Plate 48 is also welded to shroud 42, but extends beyond shroud 42 to shell 12.
E'eed water at a -temæerature within a range of from 115C. to approximately 190C is introduced through inlet 34 into preheater zone ~0. The tubesheet 18 and shell 12 are at a temperature of approximately 260~C. during normal full load op-eration of the steam generator 10. However, it should be- under-stood that the temperatures of the tubesheet and the feedwater can vary during transient conditions, and these "normal" temp-eratures are used herein only to illustrate possible temperature differences between the feedwater and the tubeshee-t. A thermal ; 20 shield 50 is disposed above section ~3 of the upper face of tubesheet 18 in the preheater zone 40. Thermal shield 50 comprises a weld deposit of ductile Ni-Cr-Fe alloy having a finished thick-ness of approximately 6.35mm. The weld deposit, or cladding, is applied to the tubesheet before holes are formed in the tube-sheet for receiving the ends of U-tubes 1~. Therefore a tight fit is assured between the thermal shield 50 and the tubes 1~.
Since the cladding is applied directly to the face of the tubesheet, thereby eliminating any space between the cladding and the tubeshee~
face, lea]cage of feed water from the preheater zone ~0 to the boil-ing zone 39 is not possible. Although in the preferred embodimenta Ni-Cr-Fe alloy ma-terial is used as cladding, other weld material haviny similar ductility and fatigue properties can be employed.
In operation relatlvely cold feedw~ter is introduced through inlet 34 into the preheater zone 40 of steam generator 10. Relatively hot fluid, such as heavy water, is introduced thro~lgh inlet 30 into chamber 26. The hot fluid rises through upflow l.egs 16 of U-tubes 14, coming .in contact with the colder shellside fluid and giving of a portion of its hea-t there-to.
The tubeside fluid is then returned through downflow legs 20 and empties into chamber 28 from which it is removed through outlet 32. The incoming feed water falls within shell.12 on to ~.hermal shi.eld 50 disposed above section 43 o:E the upper face of tubeshee-t 18 in preheater zone 40. Shield 50 acts to prevent the relatively cold shellside fluid from thermally shocking tubesheet 18. After the colder fluid is preheated :~ within zone 40, it rises and continues to absorb addltional heat as it contacts the outer surfaces of U-tubes 14. Upon ris-. ing into upper section 36, vapor is separated from the heated .~ shellside fluid, and is later removed through outlet 38. Sep-arated shellside liquid is recirculated through downcomer space 37 to boiling zone 39.
A latitude of modification, change and substitution is intended in the foregoing disclosure and in some instances some features of the invention will be employed without a corresponding use of other features. Accordingly, it is appropriate that the appended claims be construed broadly and in a manner consisten-t with the spirit and scope of the inven-tion herein.
Claims (4)
1. A nuclear steam generator of the type in which a plurality of U-shaped tubes are connected at opposite ends to a tubesheet and extend between inlet and outlet chambers, said steam generator including an integral preheater zone adjacent downflow legs of said U-shaped tubes, the improvement comprising a thermal shield disposed adjacent an upper face of said tubesheet within said preheater zone, said shield including ductile cladding material applied directly to said upper face of said tube-sheet, said downflow legs of said U -shaped tubes extending through said cladding into said tubesheet.
2. The improvement of claim 1 in which said ductile cladding material comprises a weld deposit having a thickness of at least approximately 6.35 mm.
3. The improvement of claim 1 in which said cladding material comprises Ni-Cr-Fe alloy.
4. A nuclear steam generator comprising:
(a) a generally cylindrical shell, (b) a plurality of U-shaped tubes disposed within said shell, the ends of said U-shaped tubes disposed adjacent the bottom of said shell, (c) a tubesheet disposed adjacent the bottom of said shell, said tubesheet having holes formed there-through for receiving said ends of said U-shaped tubes, (d) a header disposed below said tubesheet and connected to said tubesheet, said header including inlet and outlet chambers, (e) means for introducing a first heated fluid to said inlet chamber of said header, (f) means for removing said first fluid from said outlet chamber of said header, (g) means for introducing a relatively cold heat exchange fluid into said shell, (h) means defining a preheater zone within said shell adjacent said inlet means for introducing said relatively cold fluid into said shell, said means in-cluding a semi-cylindrical shroud disposed within said shell, and a plate extending across the upper face of said tubesheet, connected at opposite ends thereof to the inner walls of said shell, and (i) a thermal shield disposed above said tube-sheet within said preheater zone, said thermal shield comprising cladding applied directly to the upper face of said tubesheet, said cladding comprising a Ni-Cr-Fe alloy.
(a) a generally cylindrical shell, (b) a plurality of U-shaped tubes disposed within said shell, the ends of said U-shaped tubes disposed adjacent the bottom of said shell, (c) a tubesheet disposed adjacent the bottom of said shell, said tubesheet having holes formed there-through for receiving said ends of said U-shaped tubes, (d) a header disposed below said tubesheet and connected to said tubesheet, said header including inlet and outlet chambers, (e) means for introducing a first heated fluid to said inlet chamber of said header, (f) means for removing said first fluid from said outlet chamber of said header, (g) means for introducing a relatively cold heat exchange fluid into said shell, (h) means defining a preheater zone within said shell adjacent said inlet means for introducing said relatively cold fluid into said shell, said means in-cluding a semi-cylindrical shroud disposed within said shell, and a plate extending across the upper face of said tubesheet, connected at opposite ends thereof to the inner walls of said shell, and (i) a thermal shield disposed above said tube-sheet within said preheater zone, said thermal shield comprising cladding applied directly to the upper face of said tubesheet, said cladding comprising a Ni-Cr-Fe alloy.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CA347,315A CA1132413A (en) | 1980-03-10 | 1980-03-10 | Nuclear steam generator tubesheet shield |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CA347,315A CA1132413A (en) | 1980-03-10 | 1980-03-10 | Nuclear steam generator tubesheet shield |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CA1132413A true CA1132413A (en) | 1982-09-28 |
Family
ID=4116436
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CA347,315A Expired CA1132413A (en) | 1980-03-10 | 1980-03-10 | Nuclear steam generator tubesheet shield |
Country Status (1)
| Country | Link |
|---|---|
| CA (1) | CA1132413A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4537157A (en) * | 1982-06-30 | 1985-08-27 | Bbc Brown, Boveri & Company, Limited | Vertical, collector-type high-pressure feed water preheater, with a desuperheater casing |
-
1980
- 1980-03-10 CA CA347,315A patent/CA1132413A/en not_active Expired
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4537157A (en) * | 1982-06-30 | 1985-08-27 | Bbc Brown, Boveri & Company, Limited | Vertical, collector-type high-pressure feed water preheater, with a desuperheater casing |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| MKEX | Expiry |