FR2191704A5 - Steam raising heat exchanger - for nuclear power station with secondary fluid preheater - Google Patents

Steam raising heat exchanger - for nuclear power station with secondary fluid preheater

Info

Publication number
FR2191704A5
FR2191704A5 FR7323162A FR7323162A FR2191704A5 FR 2191704 A5 FR2191704 A5 FR 2191704A5 FR 7323162 A FR7323162 A FR 7323162A FR 7323162 A FR7323162 A FR 7323162A FR 2191704 A5 FR2191704 A5 FR 2191704A5
Authority
FR
France
Prior art keywords
heat exchanger
preheater
secondary fluid
nuclear power
power station
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
FR7323162A
Other languages
French (fr)
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.)
Siemens AG
Original Assignee
Siemens 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.)
Filing date
Publication date
Application filed by Siemens AG filed Critical Siemens AG
Application granted granted Critical
Publication of FR2191704A5 publication Critical patent/FR2191704A5/en
Expired legal-status Critical Current

Links

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

Abstract

The preheater consists of a chamber enclosing the lower part of the outflow ends of the bundle of inverted U-tubes through which the primary coolant flows. To reduce chemical stresses due to thermal shock, the secondary fluid is fed in at a front on the side of the preheater section such that all or part of the inlet flow to the main chamber of the heat exchanger is in the same general direction as that of the primary fluid in the U-tubes where they pass through the preheater. A number of baffle plates deflect the flow so that it crosses the tubes several times.
FR7323162A 1972-06-26 1973-06-25 Steam raising heat exchanger - for nuclear power station with secondary fluid preheater Expired FR2191704A5 (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
DE19722231181 DE2231181A1 (en) 1972-06-26 1972-06-26 STEAM GENERATOR

Publications (1)

Publication Number Publication Date
FR2191704A5 true FR2191704A5 (en) 1974-02-01

Family

ID=5848800

Family Applications (1)

Application Number Title Priority Date Filing Date
FR7323162A Expired FR2191704A5 (en) 1972-06-26 1973-06-25 Steam raising heat exchanger - for nuclear power station with secondary fluid preheater

Country Status (6)

Country Link
AT (1) AT354473B (en)
BE (1) BE801383A (en)
DE (1) DE2231181A1 (en)
ES (1) ES416241A1 (en)
FR (1) FR2191704A5 (en)
IT (1) IT989377B (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0035450B1 (en) * 1980-02-29 1983-10-05 Framatome Preheating steam generator

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0035450B1 (en) * 1980-02-29 1983-10-05 Framatome Preheating steam generator

Also Published As

Publication number Publication date
AT354473B (en) 1979-01-10
IT989377B (en) 1975-05-20
BE801383A (en) 1973-10-15
ATA524573A (en) 1979-06-15
ES416241A1 (en) 1976-08-01
DE2231181A1 (en) 1974-01-10

Similar Documents

Publication Publication Date Title
ES413428A1 (en) Industrial technique
GB1358442A (en) Heat exchangers
ES409674A1 (en) Heat exchanger for two vapor media
ES417163A1 (en) Steam generator with split flow preheater
IL43700A (en) Nuclear steam generator
GB1210185A (en) Cross-current heat exchanger
GB980413A (en) Multi-pressure boiler construction
GB1175157A (en) Improvements in or relating to Steam Condensers
FR2191704A5 (en) Steam raising heat exchanger - for nuclear power station with secondary fluid preheater
GB1066775A (en) Improvements in or relating to heat exchangers
FR2106620B1 (en)
GB969036A (en) Improvements in or relating to tubular heat exchange apparatus
GB1462537A (en) Tubular heat exchangers
CU34685A (en) HEAT EXCHANGER FOR INDIRECT COOLING OF A THERMAL TRANSMITTER FLUID
GB997280A (en) Heat exchanger
GB1389904A (en) Nuclear power generating systems
GB1158322A (en) Improvements in or relating to Heat Exchangers.
ES420608A1 (en) Steam generator
GB1312457A (en) Nuclear reactor power plant
GB1032740A (en) Improved convector heater
ES422584A1 (en) Steam generator feed-water preheater improvement
FR2049022A1 (en) U-tube heat exchanger
GB1360239A (en) Tube-in-shell heat exchangers
GB879200A (en) Improvements in or relating to tubular heat exchangers
GB971902A (en) Improvements in or relating to nuclear reactors

Legal Events

Date Code Title Description
ST Notification of lapse