BE644866A - - Google Patents

Info

Publication number
BE644866A
BE644866A BE644866DA BE644866A BE 644866 A BE644866 A BE 644866A BE 644866D A BE644866D A BE 644866DA BE 644866 A BE644866 A BE 644866A
Authority
BE
Belgium
Prior art keywords
sep
tube
fuel
pressure
water
Prior art date
Application number
Other languages
English (en)
French (fr)
Publication date
Publication of BE644866A publication Critical patent/BE644866A/fr

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
    • G21C1/14—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
    • 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)
BE644866D BE644866A (it)

Publications (1)

Publication Number Publication Date
BE644866A true BE644866A (it) 1900-01-01

Family

ID=205334

Family Applications (1)

Application Number Title Priority Date Filing Date
BE644866D BE644866A (it)

Country Status (1)

Country Link
BE (1) BE644866A (it)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1517990B1 (de) * 1965-12-03 1971-10-07 Atomic Energy Of Canada Ltd Brennelementkanal fuer einen mit einer unter druck stehenden wasserstoffverbindung gekuehlten atomkernreaktor
US4675154A (en) * 1985-12-20 1987-06-23 General Electric Company Nuclear fuel assembly with large coolant conducting tube

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1517990B1 (de) * 1965-12-03 1971-10-07 Atomic Energy Of Canada Ltd Brennelementkanal fuer einen mit einer unter druck stehenden wasserstoffverbindung gekuehlten atomkernreaktor
US4675154A (en) * 1985-12-20 1987-06-23 General Electric Company Nuclear fuel assembly with large coolant conducting tube

Similar Documents

Publication Publication Date Title
US3070537A (en) Fuel subassembly construction for radial flow in a nuclear reactor
CN102822902B (zh) 带有一体的蒸汽发生器的紧凑型核反应堆
FR2763167A1 (fr) Coeur de reacteur
JPH03118497A (ja) 燃料集合体における異物フィルタ下部ノズル
US3400049A (en) Steam cooled nuclear reactor power system
JPH02232591A (ja) 原子炉燃料集合体用の燃料棒
FR2496317A1 (fr) Barre de commande de deplacement utilisable dans un reacteur a derive spectrale nucleaire constituee par des tubes metalliques ceux reunis par des sections de barre intermediaires
KR102200640B1 (ko) 가압 수로형 원자로를 위한 중하중 방사상 중성자 반사체
FR2807563A1 (fr) Assemblage de combustible nucleaire pour un reacteur refroidi par de l'eau legere comportant un materiau combustible nucleaire sous forme de particules
EP0234566A2 (en) Emergency nuclearreactor core cooling structure
BE644866A (it)
FR2646954A1 (fr) Reacteurs nucleaires refroidis a l'eau
ES2586677T3 (es) Amortiguación de flujo en una vía de tubos de un generador de vapor
FR2715760A1 (fr) Assemblage de combustible incluant des ailettes déflectrices pour dévier une composante d'un courant de fluide s'y écoulant.
FR2962842A1 (fr) Coeur de reacteur a eau legere et assemblage combustible.
KR0139646B1 (ko) 증기발생기 급수관에 열성층 방지장치
FR2566511A1 (fr) Generateur de vapeur hybride a prechauffage et recirculation
JPH06201890A (ja) モジュール型乾燥器一体化蒸気分離器
FR3029677A1 (fr) Grille de maintien d'assemblage combustible nucleaire
FR2519462A1 (fr) Dispositif d'evacuation de secours de la chaleur dissipee par un reacteur nucleaire a neutrons rapides a l'arret
JP3086709B2 (ja) 原子炉炉心
JPH05215877A (ja) 沸騰水型原子炉の炉心
FR3020494A1 (fr) Element combustible nucleaire
EP0047698B1 (fr) Réacteur nucléaire à circulation du fluide primaire de refroidissement par convection mixte
FR2679062A1 (fr) Cóoeur de reacteur surgenerateur rapide et assemblage combustible utilise dans un tel cóoeur.