ES253177A1 - Improvements in and relating to nuclear reactors - Google Patents

Improvements in and relating to nuclear reactors

Info

Publication number
ES253177A1
ES253177A1 ES0253177A ES253177A ES253177A1 ES 253177 A1 ES253177 A1 ES 253177A1 ES 0253177 A ES0253177 A ES 0253177A ES 253177 A ES253177 A ES 253177A ES 253177 A1 ES253177 A1 ES 253177A1
Authority
ES
Spain
Prior art keywords
steam
reactor
superheaters
source
successive
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
ES0253177A
Other languages
Spanish (es)
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.)
CA Parsons and Co Ltd
Original Assignee
CA Parsons and Co 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 CA Parsons and Co Ltd filed Critical CA Parsons and Co Ltd
Publication of ES253177A1 publication Critical patent/ES253177A1/en
Expired 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
    • G21D5/06—Reactor and engine not structurally combined with engine working medium circulating through reactor core
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G21C1/04—Thermal reactors ; Epithermal reactors
    • G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
    • G21C1/14—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor
    • G21C1/16—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor
    • G21C1/18—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor coolant being pressurised
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G21C1/04—Thermal reactors ; Epithermal reactors
    • G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
    • G21C1/14—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor
    • G21C1/16—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor
    • G21C1/18—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor coolant being pressurised
    • G21C1/20—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor coolant being pressurised moderator being liquid, e.g. pressure-tube reactor
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
    • G21C15/08—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from moderating material
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
    • G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
    • 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
    • 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
    • Y02E30/30—Nuclear fission reactors

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
  • Engine Equipment That Uses Special Cycles (AREA)

Abstract

Improvements in nuclear reactors, characterized in that the nuclear fuel is housed in closed containers, which are located in a nucleus of the reactor of neutron moderating material, the reactor being associated with a source that uses the heat extracted from the reactor by a refrigerant, in which reactor the refrigerant is a steam that is passed through successive sections of its core, overheating, the sections being connected in series with each other, arranging a variety of de-superheaters in such a way that the steam that circulates from one section to the The next one passes through one of them, the arrangement being such that the condemned steam that returns to the reactor from the source that uses the heat content of the steam is divided into a series of separate streams, raising the current that goes to the first section of the reactor core at least to saturated steam outside the reactor, the remaining currents being transported of condensed steam to the superheaters for mixing with steam that passes through them between successive sections of the reactor, cooling the aforementioned steam and turning into steam as well, increasing amounts of condensate being added in successive de-superheaters until that the steam that returns to the reactor from the final de-superheater is equivalent to the totality of the current of mass of steam in circulation towards the referred source. (Machine-translation by Google Translate, not legally binding)
ES0253177A 1958-11-07 1959-11-05 Improvements in and relating to nuclear reactors Expired ES253177A1 (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB35857/58A GB880697A (en) 1958-11-07 1958-11-07 Improvements in and relating to nuclear reactors

Publications (1)

Publication Number Publication Date
ES253177A1 true ES253177A1 (en) 1960-02-01

Family

ID=10382298

Family Applications (1)

Application Number Title Priority Date Filing Date
ES0253177A Expired ES253177A1 (en) 1958-11-07 1959-11-05 Improvements in and relating to nuclear reactors

Country Status (5)

Country Link
BE (1) BE584390A (en)
ES (1) ES253177A1 (en)
FR (1) FR1240821A (en)
GB (1) GB880697A (en)
NL (1) NL245052A (en)

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CH378431A (en) * 1960-05-17 1964-06-15 Sulzer Ag Nuclear reactor plant
US3164527A (en) * 1961-04-28 1965-01-05 Sulzer Ag Nuclear reactor vapor generating plant

Also Published As

Publication number Publication date
NL245052A (en) 1900-01-01
FR1240821A (en) 1960-09-09
BE584390A (en) 1960-03-01
GB880697A (en) 1961-10-25

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