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FR2361604A1 - Steam generator, partic. for nuclear reactor - uses mean liq. sodium temp. in controlling operating conditions to minimise thermal shock - Google Patents

Steam generator, partic. for nuclear reactor - uses mean liq. sodium temp. in controlling operating conditions to minimise thermal shock

Info

Publication number
FR2361604A1
FR2361604A1 FR7723920A FR7723920A FR2361604A1 FR 2361604 A1 FR2361604 A1 FR 2361604A1 FR 7723920 A FR7723920 A FR 7723920A FR 7723920 A FR7723920 A FR 7723920A FR 2361604 A1 FR2361604 A1 FR 2361604A1
Authority
FR
France
Prior art keywords
temp
liq
partic
operating conditions
thermal shock
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.)
Granted
Application number
FR7723920A
Other languages
French (fr)
Other versions
FR2361604B1 (en
Inventor
Akira Suzuoki
Tadashi Goto
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.)
Hitachi Ltd
Original Assignee
Hitachi Ltd
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 Hitachi Ltd filed Critical Hitachi Ltd
Publication of FR2361604A1 publication Critical patent/FR2361604A1/en
Application granted granted Critical
Publication of FR2361604B1 publication Critical patent/FR2361604B1/fr
Granted legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D5/00—Arrangements of reactor and engine in which reactor-produced heat is converted into mechanical energy
    • G21D5/04—Reactor and engine not structurally combined
    • G21D5/08—Reactor and engine not structurally combined with engine working medium heated in a heat exchanger by the reactor coolant
    • G21D5/12—Liquid working medium vaporised by reactor coolant
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
    • F01K—STEAM ENGINE PLANTS; STEAM ACCUMULATORS; ENGINE PLANTS NOT OTHERWISE PROVIDED FOR; ENGINES USING SPECIAL WORKING FLUIDS OR CYCLES
    • F01K3/00—Plants characterised by the use of steam or heat accumulators, or intermediate steam heaters, therein
    • F01K3/18—Plants characterised by the use of steam or heat accumulators, or intermediate steam heaters, therein having heaters
    • F01K3/181—Plants characterised by the use of steam or heat accumulators, or intermediate steam heaters, therein having heaters using nuclear heat
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22—STEAM GENERATION
    • F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B35/00—Control systems for steam boilers
    • F22B35/004—Control systems for steam generators of nuclear power plants
    • 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

Landscapes

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Chemical & Material Sciences (AREA)
  • Combustion & Propulsion (AREA)
  • Mechanical Engineering (AREA)
  • Plasma & Fusion (AREA)
  • Thermal Sciences (AREA)
  • Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

A plant for generating steam, partic. one in which the generator is heated by a liq. metal, having a multi tubular calandria, and used with a fast neutron reactor, incorporates instruments for determining the mean temp. of the liq. metal in the calandria. The operating conditions are controlled in terms of the mean temp. measured. Problems associated with thermal shock on the tubes and the calandria are avoided. Such shocks can result in installations in which the feed rate of water is controlled by a signal representing external conditions only, e.g. the temp. of the steam.
FR7723920A 1976-08-11 1977-08-03 Steam generator, partic. for nuclear reactor - uses mean liq. sodium temp. in controlling operating conditions to minimise thermal shock Granted FR2361604A1 (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP9645776A JPS5321302A (en) 1976-08-11 1976-08-11 Steam generator

Publications (2)

Publication Number Publication Date
FR2361604A1 true FR2361604A1 (en) 1978-03-10
FR2361604B1 FR2361604B1 (en) 1982-01-22

Family

ID=14165545

Family Applications (1)

Application Number Title Priority Date Filing Date
FR7723920A Granted FR2361604A1 (en) 1976-08-11 1977-08-03 Steam generator, partic. for nuclear reactor - uses mean liq. sodium temp. in controlling operating conditions to minimise thermal shock

Country Status (2)

Country Link
JP (1) JPS5321302A (en)
FR (1) FR2361604A1 (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2565324A1 (en) * 1984-05-29 1985-12-06 Us Energy CONTROL SYSTEM FOR A FLUID HEATED STEAM GENERATOR

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN114352364B (en) * 2021-07-22 2023-11-21 杭州绿能环保发电有限公司 Main steam temperature control device

Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR1396030A (en) * 1964-04-24 1965-04-16 Sulzer Ag Method and device for regulating a reactor installation
FR1441942A (en) * 1963-10-30 1966-06-10 Sulzer Ag Method for heating a working fluid in the heat exchanger of a nuclear reactor

Patent Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR1441942A (en) * 1963-10-30 1966-06-10 Sulzer Ag Method for heating a working fluid in the heat exchanger of a nuclear reactor
FR1396030A (en) * 1964-04-24 1965-04-16 Sulzer Ag Method and device for regulating a reactor installation

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2565324A1 (en) * 1984-05-29 1985-12-06 Us Energy CONTROL SYSTEM FOR A FLUID HEATED STEAM GENERATOR

Also Published As

Publication number Publication date
JPS5761961B2 (en) 1982-12-27
FR2361604B1 (en) 1982-01-22
JPS5321302A (en) 1978-02-27

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Legal Events

Date Code Title Description
ST Notification of lapse