ES467218A1 - Perfeccionamientos introducidos en las instalaciones de pasode agua a presion por un reactor nuclear - Google Patents

Perfeccionamientos introducidos en las instalaciones de pasode agua a presion por un reactor nuclear

Info

Publication number
ES467218A1
ES467218A1 ES467218A ES467218A ES467218A1 ES 467218 A1 ES467218 A1 ES 467218A1 ES 467218 A ES467218 A ES 467218A ES 467218 A ES467218 A ES 467218A ES 467218 A1 ES467218 A1 ES 467218A1
Authority
ES
Spain
Prior art keywords
flow
fission chamber
cooling
thimbles
control
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
ES467218A
Other languages
English (en)
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.)
Combustion Engineering Inc
Original Assignee
Combustion Engineering Inc
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 Combustion Engineering Inc filed Critical Combustion Engineering Inc
Publication of ES467218A1 publication Critical patent/ES467218A1/es
Expired legal-status Critical Current

Links

Classifications

    • 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
    • G21C1/08—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor
    • G21C1/086—Pressurised water reactors
    • 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
    • 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)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

Perfeccionamientos introducidos en las instalaciones de paso de agua a presión por un reactor nuclear; en el que el agua de refrigeración pasa, en sentido ascendente, a través de este núcleo reactor; equipado con unos tubos de guía verticales dentro del referido núcleo, y con unas varillas de control de desplazamiento vertical dentro de los mencionados tubos de guías caracterizado porque la mencionada agua de refrigeración es dividida en una primera cantidad de agua, que es introducida por el extremo inferior del mencionado núcleo reactor y que por el mismo pasa hacia arriba y en una segunda cantidad de agua que es introducida por el extremo superior de los referidos tubos de guía para pasar por los mismo en sentido descendente.
ES467218A 1977-03-02 1978-02-22 Perfeccionamientos introducidos en las instalaciones de pasode agua a presion por un reactor nuclear Expired ES467218A1 (es)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US77346577A 1977-03-02 1977-03-02

Publications (1)

Publication Number Publication Date
ES467218A1 true ES467218A1 (es) 1979-02-01

Family

ID=25098369

Family Applications (1)

Application Number Title Priority Date Filing Date
ES467218A Expired ES467218A1 (es) 1977-03-02 1978-02-22 Perfeccionamientos introducidos en las instalaciones de pasode agua a presion por un reactor nuclear

Country Status (14)

Country Link
JP (1) JPS591995B2 (es)
AU (1) AU514977B2 (es)
BE (1) BE864438A (es)
BR (1) BR7801231A (es)
CA (1) CA1091827A (es)
CH (1) CH629328A5 (es)
DE (1) DE2804937C3 (es)
ES (1) ES467218A1 (es)
FR (1) FR2382747A1 (es)
GB (1) GB1582107A (es)
IT (1) IT1092993B (es)
NL (1) NL7802250A (es)
PT (1) PT67726A (es)
SE (1) SE430108B (es)

Families Citing this family (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2529705A1 (fr) * 1982-07-01 1984-01-06 Framatome Sa Dispositif de verification de la deconnexion des grappes de controle d'un reacteur nucleaire
DE3373586D1 (en) * 1983-05-13 1987-10-15 Westinghouse Electric Corp Nuclear reactor
FR2595501B1 (fr) * 1986-03-07 1988-06-10 Framatome Sa Equipements internes de reacteurs nucleaires a cuve allongee
JPH067180B2 (ja) * 1987-10-19 1994-01-26 動力炉・核燃料開発事業団 一体型圧力容器構造の原子炉
FR2627321B1 (fr) * 1988-02-11 1992-08-14 Framatome Sa Equipements internes superieurs de reacteur nucleaire muni d'un dispositif de separation des debits
CN111370148B (zh) * 2018-12-25 2024-05-14 国家电投集团科学技术研究院有限公司 反应堆的二套停堆机构和反应堆

Family Cites Families (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
BE586969A (es) * 1959-01-29
GB883717A (en) * 1959-04-03 1961-12-06 Babcock & Wilcox Ltd Improvements in nuclear reactors
US3481832A (en) * 1967-04-14 1969-12-02 Combustion Eng Nuclear reactor core and control element arrangement
US3770583A (en) * 1971-05-20 1973-11-06 Combustion Eng Fuel assembly hold-down device
UST911015I4 (en) * 1971-12-21 1973-06-26 Nuclear core positioning system
BE793195A (fr) * 1971-12-23 1973-04-16 Combustion Eng Reacteur nucleaire equipe d'un dispositif hydraulique individuel pour actionner chaque barre de commande
US3853703A (en) * 1972-07-03 1974-12-10 Combustion Eng Fuel assembly hold-up device
DE2237208A1 (de) * 1972-07-28 1974-02-07 Siemens Ag Kernreaktor

Also Published As

Publication number Publication date
FR2382747B1 (es) 1982-01-29
JPS591995B2 (ja) 1984-01-14
PT67726A (en) 1978-04-01
SE7802267L (sv) 1978-09-03
JPS53107595A (en) 1978-09-19
DE2804937C3 (de) 1980-12-04
IT7820830A0 (it) 1978-03-03
BR7801231A (pt) 1978-09-26
DE2804937A1 (de) 1978-09-07
DE2804937B2 (de) 1980-04-03
CH629328A5 (en) 1982-04-15
IT1092993B (it) 1985-07-12
AU3369278A (en) 1979-09-06
FR2382747A1 (fr) 1978-09-29
SE430108B (sv) 1983-10-17
BE864438A (fr) 1978-07-03
GB1582107A (en) 1980-12-31
AU514977B2 (en) 1981-03-12
CA1091827A (en) 1980-12-16
NL7802250A (nl) 1978-09-05

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Legal Events

Date Code Title Description
FD1A Patent lapsed

Effective date: 19970612