GB960678A - Nuclear power reactor with rod-shaped fuel elements - Google Patents

Nuclear power reactor with rod-shaped fuel elements

Info

Publication number
GB960678A
GB960678A GB39943/62A GB3994362A GB960678A GB 960678 A GB960678 A GB 960678A GB 39943/62 A GB39943/62 A GB 39943/62A GB 3994362 A GB3994362 A GB 3994362A GB 960678 A GB960678 A GB 960678A
Authority
GB
United Kingdom
Prior art keywords
reactor
fuel
ladder
steam
water
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
GB39943/62A
Inventor
Friedrich Schmiedel
Heinrich Gunter Schafstall
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.)
Beteiligungs und Patentverwaltungs GmbH
Original Assignee
Beteiligungs und Patentverwaltungs GmbH
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
Priority to BE624265D priority Critical patent/BE624265A/xx
Application filed by Beteiligungs und Patentverwaltungs GmbH filed Critical Beteiligungs und Patentverwaltungs GmbH
Priority to GB39943/62A priority patent/GB960678A/en
Priority to FR912979A priority patent/FR1336626A/en
Publication of GB960678A publication Critical patent/GB960678A/en
Expired legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/30Assemblies of a number of fuel elements in the form of a rigid unit
    • G21C3/32Bundles of parallel pin-, rod-, or tube-shaped fuel elements
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C1/00Reactor types
    • G21C1/04Thermal reactors ; Epithermal reactors
    • G21C1/06Heterogeneous reactors, i.e. in which fuel and moderator are separated
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C1/00Reactor types
    • G21C1/04Thermal reactors ; Epithermal reactors
    • G21C1/06Heterogeneous reactors, i.e. in which fuel and moderator are separated
    • G21C1/08Heterogeneous 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
    • G21C1/082Reactors where the coolant is overheated
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C15/00Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/02Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
    • G21C15/04Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from fissile or breeder material
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02Fuel elements
    • G21C3/04Constructional details
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Devices And Processes Conducted In The Presence Of Fluids And Solid Particles (AREA)

Abstract

960,678. Reactors. BETEILIGUNGS-UND PATENTVERWALTUNGSGESELLSCHAFT. Oct. 22, 1962, No. 39943/62. Heading G6C. A nuclear reactor with no bottom grid has horizontally rod shaped fuel elements the ends of which are connected to longitudinal members to form a number of ladder-like groups in which the fuel elements form the rungs of the ladders. The invention is applicable to boiling water and gas cooled reactors and provides a single zone within the reactor in which superheating takes place. The fuel may be metallic or ceramic compounds of circular or elliptical cross-section. A further feature of all the embodiments described is that one of the longitudinal members of each "ladder" is movable in a direction parallel to the fuel element axes in order to accommodate thermal expansion. The water cooled reactor shown in Fig. 7 comprises two heating zones, the first heating the water, which may be heavy water acting as coolant, moderator and shield, and the second superheating the resultant steam. Each ladder-like fuel assembly is immersed in the liquid coolant, and the steam thereby generated accumulates above the water level in the reactor before passing into the first hollow longitudinal member 6 of the fuel assemblies From the member 6 the steam passes through the interiors of the hollow fuel elements 5, out through the second longitudinal member 7 and into a steam accumulator 8. Superheated steam passes from the accumulator either to a heat exchanger or direct to a turbine. The superheating coolant circuit may be modified by placing a divider at approximately the mid point of the longitudinal member 6, such that the entire steam flow passes from left to right in the upper half of the "ladder", and from right to left in the lower half. The upper end of the longitudinal member 7 is closed, and the steam accumulator is connected to the lower end of the member 6. In a modified form of boiling water reactor, solid fuel elements are used, there being no circulation of coolant within the "ladder". In this case, the superheating takes place in a zone above the water level into which the "ladder" ends project. The gas cooled reactor shown in Fig. 11 utilizes a solid fuel element surrounded by two spaced apart concentric graphite tubes (Figs. 8, 9, not shown). Provision is made for circulating a scavenging gas (entirely independent of the coolant circuit) through the graphite annulus surrounding each fuel element via inlet and outlet connections made to the two longitudinal members 24, 25. Gas . enters the reactor through an annulus 29 and passes dpward, cooling the reflector 28. The thus preheated gas then passes down through the core and out through a pipe 32. An advantageous feature of both the boiling water and gas cooled reactors described is that the "ladder" construction of the fuel assemblies obviates the need for a bottom grid plate. The weight of fuel is supported through the longitudinal members on an annular ring positioned in the bottom of the reactor.
GB39943/62A 1962-10-22 1962-10-22 Nuclear power reactor with rod-shaped fuel elements Expired GB960678A (en)

Priority Applications (3)

Application Number Priority Date Filing Date Title
BE624265D BE624265A (en) 1962-10-22
GB39943/62A GB960678A (en) 1962-10-22 1962-10-22 Nuclear power reactor with rod-shaped fuel elements
FR912979A FR1336626A (en) 1962-10-22 1962-10-22 Rod-shaped fuel element nuclear power reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB39943/62A GB960678A (en) 1962-10-22 1962-10-22 Nuclear power reactor with rod-shaped fuel elements

Publications (1)

Publication Number Publication Date
GB960678A true GB960678A (en) 1964-06-10

Family

ID=10412338

Family Applications (1)

Application Number Title Priority Date Filing Date
GB39943/62A Expired GB960678A (en) 1962-10-22 1962-10-22 Nuclear power reactor with rod-shaped fuel elements

Country Status (2)

Country Link
BE (1) BE624265A (en)
GB (1) GB960678A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4343760A (en) * 1979-11-14 1982-08-10 The United States Of America As Represented By The United States Department Of Energy Divertor target for magnetic containment device

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4343760A (en) * 1979-11-14 1982-08-10 The United States Of America As Represented By The United States Department Of Energy Divertor target for magnetic containment device

Also Published As

Publication number Publication date
BE624265A (en)

Similar Documents

Publication Publication Date Title
US3213833A (en) Unitized vapor generation system
US2865827A (en) Power generation from liquid metal nuclear fuel
US2994657A (en) Chimney for boiling water reactor
US3105030A (en) Fuel element for a neutronic reactor
CN108140433B (en) Nuclear reactor
ES350798A1 (en) Steam cooled nuclear reactor power system
US3296085A (en) Calandria core for sodium graphite reactor
US3049487A (en) Direct-cycle, boiling-water nuclear reactor
US3240678A (en) Pressure tube neutronic reactor and coolant control means therefor
GB983742A (en) Improvements in or relating to nuclear reactor systems
US3226300A (en) Unified modular reactor plant
US3276914A (en) Reactor-thermoelectric generator
US3085056A (en) Method and apparatus for generating and superheating steam from nuclear energy
US3700552A (en) Nuclear reactor with means for adjusting coolant temperature
US3205139A (en) High temperature reactor with specific distribution of non-1/v. absorber and fertilematerial
GB960678A (en) Nuclear power reactor with rod-shaped fuel elements
US3178354A (en) Steam cooled nuclear reactor system with improved fuel element assembly
US3149046A (en) Nuclear steam generator for a thermoelectric power plant
US3185630A (en) Boiling coolant reactor with integral vapor separation and nuclear superheat
US3180801A (en) Heavy water moderated organic cooled nuclear fission reactor
US3189524A (en) Fuel element assembly
US3069341A (en) Neutronic reactor
US3068159A (en) Process for cooling a nuclear reactor
US3322643A (en) Heat transfer apparatus arrangement
Ju et al. Research method and two-phase flow stability of the steam generator of HTR-10