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MX2017008724A - Control de reaccion de fision en un reactor de sal fundida. - Google Patents

Control de reaccion de fision en un reactor de sal fundida.

Info

Publication number
MX2017008724A
MX2017008724A MX2017008724A MX2017008724A MX2017008724A MX 2017008724 A MX2017008724 A MX 2017008724A MX 2017008724 A MX2017008724 A MX 2017008724A MX 2017008724 A MX2017008724 A MX 2017008724A MX 2017008724 A MX2017008724 A MX 2017008724A
Authority
MX
Mexico
Prior art keywords
molten fuel
fuel salt
reactor core
nuclear reactor
salt
Prior art date
Application number
MX2017008724A
Other languages
English (en)
Other versions
MX387314B (es
Inventor
R Cheatham Jesse Iii
T Cisneros Anselmo Jr
F Latkowski Jeffery
m vollmer James
J Johns Christopher
Original Assignee
Terrapower Llc
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 Terrapower Llc filed Critical Terrapower Llc
Publication of MX2017008724A publication Critical patent/MX2017008724A/es
Publication of MX387314B publication Critical patent/MX387314B/es

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G21C1/02—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders
    • G21C1/03—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders cooled by a coolant not essentially pressurised, e.g. pool-type reactors
    • 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
    • G21C1/22—Heterogeneous reactors, i.e. in which fuel and moderator are separated using liquid or gaseous fuel
    • 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
    • G21C15/28—Selection of specific coolants ; Additions to the reactor coolants, e.g. against moderator corrosion
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/28—Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/28—Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core
    • G21C19/30—Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core with continuous purification of circulating fluent material, e.g. by extraction of fission products deterioration or corrosion products, impurities, e.g. by cold traps
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/28—Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core
    • G21C19/30—Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core with continuous purification of circulating fluent material, e.g. by extraction of fission products deterioration or corrosion products, impurities, e.g. by cold traps
    • G21C19/303—Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core with continuous purification of circulating fluent material, e.g. by extraction of fission products deterioration or corrosion products, impurities, e.g. by cold traps specially adapted for gases
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/42—Reprocessing of irradiated fuel
    • G21C19/50—Reprocessing of irradiated fuel of irradiated fluid fuel, e.g. regeneration of fuels while the reactor is in operation
    • 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
    • G21C3/02—Fuel elements
    • G21C3/24—Fuel elements with fissile or breeder material in fluid form within a non-active casing
    • 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
    • G21C3/42—Selection of substances for use as reactor fuel
    • G21C3/44—Fluid or fluent reactor fuel
    • G21C3/54—Fused salt, oxide or hydroxide compositions
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C7/00—Control of nuclear reaction
    • G21C7/30—Control of nuclear reaction by displacement of the reactor fuel or fuel elements
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
    • G21C17/104—Measuring reactivity
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/20—Arrangements for introducing objects into the pressure vessel; Arrangements for handling objects within the pressure vessel; Arrangements for removing objects from the pressure vessel
    • G21C19/205—Interchanging of fuel elements in the core, i.e. fuel shuffling
    • 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
    • G21C3/02—Fuel elements
    • G21C3/22—Fuel elements with fissile or breeder material in contact with 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
    • 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)
  • Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Inorganic Compounds Of Heavy Metals (AREA)
  • Extraction Or Liquid Replacement (AREA)

Abstract

Un reactor de sal fundida incluye un núcleo de reactor nuclear para mantener una reacción de fisión nuclear alimentada por una sal de combustible fundida. Un sistema de control de sal de combustible fundida elimina un volumen de la sal de combustible fundida desde el núcleo de reactor nuclear para mantener un parámetro de reactividad dentro de un intervalo de reactividad nominal. El sistema de control de sal de combustible fundida incluye un sistema de intercambio de sal de combustible fundida que se acopla por fluidos al núcleo de reactor nuclear e intercambiar un volumen de la sal de combustible fundida con un volumen de un material de alimentación que contiene una mezcla de un material fértil seleccionado y una sal portadora. El sistema de control de sal de combustible fundida puede incluir un sistema de control de desplazamiento volumétrico que tiene uno o más cuerpos de desplazamiento volumétrico insertables en el núcleo de reactor nuclear. Cada cuerpo de desplazamiento volumétrico puede eliminar un volumen de la sal de combustible fundida desde el núcleo de reactor nuclear, como a través de un sistema de desbordamiento.
MX2017008724A 2014-12-29 2015-12-29 Control de reacción de fisión en un reactor de sal fundida. MX387314B (es)

Applications Claiming Priority (4)

Application Number Priority Date Filing Date Title
US201462097235P 2014-12-29 2014-12-29
US201462098984P 2014-12-31 2014-12-31
US201562234889P 2015-09-30 2015-09-30
PCT/US2015/067923 WO2016109579A1 (en) 2014-12-29 2015-12-29 Fission reaction control in a molten salt reactor

Publications (2)

Publication Number Publication Date
MX2017008724A true MX2017008724A (es) 2018-04-10
MX387314B MX387314B (es) 2025-03-18

Family

ID=55405444

Family Applications (2)

Application Number Title Priority Date Filing Date
MX2017008724A MX387314B (es) 2014-12-29 2015-12-29 Control de reacción de fisión en un reactor de sal fundida.
MX2017008725A MX2017008725A (es) 2014-12-29 2015-12-29 Sales de combustible nuclear fundidas y sistemas y metodos relacionados.

Family Applications After (1)

Application Number Title Priority Date Filing Date
MX2017008725A MX2017008725A (es) 2014-12-29 2015-12-29 Sales de combustible nuclear fundidas y sistemas y metodos relacionados.

Country Status (10)

Country Link
US (4) US10438705B2 (es)
EP (3) EP3241218B1 (es)
JP (3) JP2018507396A (es)
KR (2) KR102548067B1 (es)
CN (3) CN107112054A (es)
AU (1) AU2015374124B2 (es)
CA (3) CA2967473A1 (es)
MX (2) MX387314B (es)
RU (2) RU2709966C2 (es)
WO (3) WO2016109442A1 (es)

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