FR2297483A1 - Nuclear power plant with superheating reheater cooler than evaporator - gives high efficiency without adversely affecting reactor characteristics - Google Patents

Nuclear power plant with superheating reheater cooler than evaporator - gives high efficiency without adversely affecting reactor characteristics

Info

Publication number
FR2297483A1
FR2297483A1 FR7500731A FR7500731A FR2297483A1 FR 2297483 A1 FR2297483 A1 FR 2297483A1 FR 7500731 A FR7500731 A FR 7500731A FR 7500731 A FR7500731 A FR 7500731A FR 2297483 A1 FR2297483 A1 FR 2297483A1
Authority
FR
France
Prior art keywords
circuit
evaporator
steam
reheater
primary
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
FR7500731A
Other languages
French (fr)
Other versions
FR2297483B1 (en
Inventor
Viktor Vladimirovich Orlov
Anatoly Antonovich Rineisky
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.)
Individual
Original Assignee
Individual
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 Individual filed Critical Individual
Priority to FR7500731A priority Critical patent/FR2297483A1/en
Publication of FR2297483A1 publication Critical patent/FR2297483A1/en
Application granted granted Critical
Publication of FR2297483B1 publication Critical patent/FR2297483B1/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
    • 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

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Engine Equipment That Uses Special Cycles (AREA)

Abstract

A nuclear power plant comprises a reactor, a primary circuit, opt. also a secondary heat transfer circuit, and a steam generating circuit contg. an economiser, evaporator and super-heater and also an intermediate superheater (reheater) for steam drawn from an intermediate tapping point in the turbine. The heat supply to this intermediate superheater is provided by a tapping from the secondary heat transfer circuit (in the case of a three-circuit system as shown) or from the primary circuit (in the case of a two-circuit system) at the outlet from the evaporator; the heat supply fluid is returned to the same circuit (secondary or primary) at the low temp. side. Used for three-circuit systems esp. sodium-sodium-steam or two-circuit systems esp. gas-steam or water-steam. As compared with an earlier system where the heat supply fluid in the (secondary or primary) heat supply circuit was subdivided into two parallel flows, one for the main superheater and the other for the intermediate reheater, and then recombined before passing through the evaporator and economiser, the present arrangement permits a high thermal efficiency to be obtained without the need to increase the reactor core/diameter ratio with a consequent reduction in the regeneration of secondary fuel. Also, the situation of the intermediate superheater in a zone of lower temp. means that austenitic steel is not required for its construction.
FR7500731A 1975-01-10 1975-01-10 Nuclear power plant with superheating reheater cooler than evaporator - gives high efficiency without adversely affecting reactor characteristics Granted FR2297483A1 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
FR7500731A FR2297483A1 (en) 1975-01-10 1975-01-10 Nuclear power plant with superheating reheater cooler than evaporator - gives high efficiency without adversely affecting reactor characteristics

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR7500731A FR2297483A1 (en) 1975-01-10 1975-01-10 Nuclear power plant with superheating reheater cooler than evaporator - gives high efficiency without adversely affecting reactor characteristics

Publications (2)

Publication Number Publication Date
FR2297483A1 true FR2297483A1 (en) 1976-08-06
FR2297483B1 FR2297483B1 (en) 1977-07-08

Family

ID=9149641

Family Applications (1)

Application Number Title Priority Date Filing Date
FR7500731A Granted FR2297483A1 (en) 1975-01-10 1975-01-10 Nuclear power plant with superheating reheater cooler than evaporator - gives high efficiency without adversely affecting reactor characteristics

Country Status (1)

Country Link
FR (1) FR2297483A1 (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0121416A2 (en) * 1983-03-30 1984-10-10 The Babcock & Wilcox Company Steam generation and reheat apparatus and methods
FR3141795A1 (en) * 2022-11-07 2024-05-10 Commissariat A L'energie Atomique Et Aux Energies Alternatives Nuclear power cogeneration installation with light water reactor (LWR) and heat exploitation system(s), in particular atmospheric CO2 capture system, or seawater desalination without withdrawal or discharge of liquid water into the environment.

Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1564628A1 (en) * 1966-06-11 1970-02-12 Siemens Ag Nuclear reactor plant, consisting of a reactor that works preferably as a fast Brueter

Patent Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1564628A1 (en) * 1966-06-11 1970-02-12 Siemens Ag Nuclear reactor plant, consisting of a reactor that works preferably as a fast Brueter

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0121416A2 (en) * 1983-03-30 1984-10-10 The Babcock & Wilcox Company Steam generation and reheat apparatus and methods
EP0121416A3 (en) * 1983-03-30 1986-07-09 The Babcock & Wilcox Company Steam generation and reheat apparatus and method
FR3141795A1 (en) * 2022-11-07 2024-05-10 Commissariat A L'energie Atomique Et Aux Energies Alternatives Nuclear power cogeneration installation with light water reactor (LWR) and heat exploitation system(s), in particular atmospheric CO2 capture system, or seawater desalination without withdrawal or discharge of liquid water into the environment.
WO2024100030A1 (en) * 2022-11-07 2024-05-16 Commissariat A L'energie Atomique Et Aux Energies Alternatives Electronuclear cogeneration plant with light water reactor and system for capturing atmospheric co2 or for desalinating sea water without withdrawing liquid water therefrom or releasing same into the environment

Also Published As

Publication number Publication date
FR2297483B1 (en) 1977-07-08

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Legal Events

Date Code Title Description
ST Notification of lapse