GB1516624A

GB1516624A – Steam generator for a pressurised-water nuclear reactor
– Google Patents

GB1516624A – Steam generator for a pressurised-water nuclear reactor
– Google Patents
Steam generator for a pressurised-water nuclear reactor

Info

Publication number
GB1516624A

GB1516624A
GB11883/77A
GB1188377A
GB1516624A
GB 1516624 A
GB1516624 A
GB 1516624A
GB 11883/77 A
GB11883/77 A
GB 11883/77A
GB 1188377 A
GB1188377 A
GB 1188377A
GB 1516624 A
GB1516624 A
GB 1516624A
Authority
GB
United Kingdom
Prior art keywords
heating water
vessel
outlet
nuclear reactor
steam generator
Prior art date
1976-03-22
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
GB11883/77A
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.)

Kraftwerk Union AG

Original Assignee
Kraftwerk Union AG
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.)
1976-03-22
Filing date
1977-03-21
Publication date
1978-07-05

1977-03-21
Application filed by Kraftwerk Union AG
filed
Critical
Kraftwerk Union AG

1978-07-05
Publication of GB1516624A
publication
Critical
patent/GB1516624A/en

Status
Expired
legal-status
Critical
Current

Links

Espacenet

Global Dossier

Discuss

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

F22B1/026—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 tubes between to horizontal tube sheets

Abstract

1516624 Steam generators for use with pressurized water reactors KRAFTWERK UNION AG 21 March 1977 [22 March 1976] 11883/77 Heading F4A A steam generator comprises a vessel with feedwater inlet 10 and steam outlets 17, a bank of tubes 2 through which is passed pressurized heating water from a nuclear reactor, inlets 6 and outlets 8 for the heating water, and a sleeve 13 which extends about the tubes into a space provided between the wall of vessel 1 and a lower tube plate 4; compensators 9 being provided at the junction heating water inlet or outlet to allow for thermal expansion. In other embodiments either the heating water inlet (Fig. 2, not shown) or the outlet (Fig. 3, not shown) can extend through the centre of the tube bank so that inlet and outlet are at the same end of the vessel.

GB11883/77A
1976-03-22
1977-03-21
Steam generator for a pressurised-water nuclear reactor

Expired

GB1516624A
(en)

Applications Claiming Priority (1)

Application Number
Priority Date
Filing Date
Title

DE19762612081

DE2612081A1
(en)

1976-03-22
1976-03-22

STEAM GENERATORS FOR PRESSURE WATER NUCLEAR REACTORS

Publications (1)

Publication Number
Publication Date

GB1516624A
true

GB1516624A
(en)

1978-07-05

Family
ID=5973116
Family Applications (1)

Application Number
Title
Priority Date
Filing Date

GB11883/77A
Expired

GB1516624A
(en)

1976-03-22
1977-03-21
Steam generator for a pressurised-water nuclear reactor

Country Status (6)

Country
Link

US
(1)

US4148281A
(en)

BR
(1)

BR7700521A
(en)

DE
(1)

DE2612081A1
(en)

FR
(1)

FR2345665A1
(en)

GB
(1)

GB1516624A
(en)

SE
(1)

SE7701892L
(en)

Families Citing this family (11)

* Cited by examiner, † Cited by third party

Publication number
Priority date
Publication date
Assignee
Title

CH639745A5
(en)

*

1978-08-18
1983-11-30
Bbc Brown Boveri & Cie

Feed water preheater.

DE2846581A1
(en)

*

1978-10-26
1980-05-08
Ght Hochtemperaturreak Tech

HEAT EXCHANGER FOR GASES OF HIGH TEMPERATURE

DE2851197A1
(en)

*

1978-11-27
1980-06-12
Interatom

LIQUID METAL HEATED STEAM GENERATOR WITH INTEGRATED INTERMEDIATE HEATING

AU532945B2
(en)

*

1979-07-23
1983-10-20
British Nuclear Fuels Ltd.
Controlling vapourisation of hydrogen fluoride

FR2477265A1
(en)

*

1980-02-29
1981-09-04
Framatome Sa

PRE-HEATING STEAM GENERATOR

DE3044902A1
(en)

*

1980-11-28
1982-07-08
Basf Ag, 6700 Ludwigshafen

HEAT EXCHANGER

US4352341A
(en)

*

1981-04-06
1982-10-05
The M.W. Kellogg Company
Waste heat boiler and steam superheater system

EP0156798A1
(en)

*

1983-09-19
1985-10-09
CHEN, Thomas Y.C.
Methods and apparatus for transferring liquid against high pressure resistance

FR2700383B1
(en)

*

1993-01-11
1995-02-10
Framatome Sa

Heat exchanger in which the supply of secondary fluid takes place at the top by a supply box open at the bottom.

US7140328B2
(en)

2002-03-11
2006-11-28
Ztek Corporation
Miniature vaporizers for use with chemical converters and energy devices

US11754349B2
(en)

*

2019-03-08
2023-09-12
Hamilton Sundstrand Corporation
Heat exchanger

Family Cites Families (6)

* Cited by examiner, † Cited by third party

Publication number
Priority date
Publication date
Assignee
Title

US3250250A
(en)

*

1962-05-11
1966-05-10
Eric M Woock
Live poultry guard unit for continuous poultry feeding troughs

DE1551050A1
(en)

*

1967-03-25
1970-02-05
Siemens Ag

Steam generator, especially for pressurized water nuclear reactors

US3443548A
(en)

*

1968-01-23
1969-05-13
Vogt & Co Inc Henry
High temperature and high pressure steam generator

US3596638A
(en)

*

1968-10-15
1971-08-03
Siemens Ag
Forced-flow steam generator to be heated by pressurized coolant of a nuclear reactor

US3724532A
(en)

*

1970-03-02
1973-04-03
Babcock & Wilcox Co
Once-through vapor generator

US3850231A
(en)

*

1973-05-24
1974-11-26
Combustion Eng
Lmfbr intermediate heat exchanger

1976

1976-03-22
DE
DE19762612081
patent/DE2612081A1/en
active
Pending

1977

1977-01-28
BR
BR7700521A
patent/BR7700521A/en
unknown

1977-02-21
SE
SE7701892A
patent/SE7701892L/en
unknown

1977-03-17
US
US05/778,592
patent/US4148281A/en
not_active
Expired – Lifetime

1977-03-21
FR
FR7708429A
patent/FR2345665A1/en
not_active
Withdrawn

1977-03-21
GB
GB11883/77A
patent/GB1516624A/en
not_active
Expired

Also Published As

Publication number
Publication date

FR2345665A1
(en)

1977-10-21

SE7701892L
(en)

1977-09-23

BR7700521A
(en)

1977-12-13

US4148281A
(en)

1979-04-10

DE2612081A1
(en)

1977-10-20

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(en)

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(en)

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(en)

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A rotary piston steam engine

Legal Events

Date
Code
Title
Description

1978-11-08
PS
Patent sealed [section 19, patents act 1949]

1981-10-28
PCNP
Patent ceased through non-payment of renewal fee

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