GB1066264A - Nuclear reactor - Google Patents

Nuclear reactor

Info

Publication number
GB1066264A
GB1066264A GB38494/64A GB3849464A GB1066264A GB 1066264 A GB1066264 A GB 1066264A GB 38494/64 A GB38494/64 A GB 38494/64A GB 3849464 A GB3849464 A GB 3849464A GB 1066264 A GB1066264 A GB 1066264A
Authority
GB
United Kingdom
Prior art keywords
core
fertile
reactor
rods
fissile
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
GB38494/64A
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.)
US Atomic Energy Commission (AEC)
Original Assignee
US Atomic Energy Commission (AEC)
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 US Atomic Energy Commission (AEC) filed Critical US Atomic Energy Commission (AEC)
Publication of GB1066264A publication Critical patent/GB1066264A/en
Expired legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C7/00Control of nuclear reaction
    • G21C7/30Control of nuclear reaction by displacement of the reactor fuel or fuel elements
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C1/00Reactor types
    • 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
    • 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)
  • Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

1,066,264. Reactors. UNITED STATES ATOMIC ENERGY COMMISSION. Sept. 21. 1964 [Nov. 15, 1963], No. 38494/64. Heading G6C. In a large pressurized-water power breeder reactor there are no neutron absorbers in the core apart from safety rods, and control is effected by moving fuel to vary the ratio of neutrons used for fission and breeding. The core is formed of a number of core assemblies, each being independently critical, and containing both fissile and fertile material, U 235 or U 233 , and U 238 or Th 232 respectively, and all being in dioxide form. It is envisaged that the reactor will operate at its full power of 1720 MW(th) for 10 years without refuelling. Reactor.-Coolant enters the spherical pressure vessel 20 through a pipe 35 which leads to an inlet plenum chamber 31. 40% of the coolant enters ports 36 and passes upwards within the movable centres of the core assemblies, out through the ends of these parts to the stationary part of the core assemblies, and finally through outlets 49. Tile remainder of the coolant enters the core assemblies through ports 53B and makes three passes through each before leaving. The core weight is transmitted to the pressure vessel by the inlet plenum chamber. Core assemblies (Figs. 1, 3).-The core of the reactor is assembled basically from a number of circular section units 42 each surrounded by three chevron section units 38. These units are arranged on a triangular lattice. The innermost section, 41, is the movable portion of the assembly and is surrounded by the fixed annular portion 42. Both sections comprise a plurality of rods 44 containing fertile and/or fuel material. An annular neutron absorbing safety element 43 is insertable between the sections 41 and 42. Each blanket segment 38 contains fertile rods 55 and has an internal baffle 58 forming two of the coolant passes referred to earlier, the third pass being through the fixed annular section 42. Thus the critical units of the reactor core each comprise a group formed by members 41, 42. and three members 38. Each rod in the central region of section 41 is entirely of fertile material, and the remaining rods of section 41 have upper portions of fertile material and lower portions of fissile material. The relative lengths of fissile and fertile material in the rods are so arranged that, referring to Fig. 10, the central rod 41 has fertile material 45 and fissile material 46. A similar arrangement of the rods in the annular section 42 results in that part of the assembly having a fissile region 46 and a fertile region 45. Reactor operation.-All reactivity control, other than emergency shut-down, is achieved by moving the centre core assembly sections 41. Initially, all power is generated by the fissile material, but towards the end of the reactor lifetime about 65% of the power will be derived from the originally fertile loading. At start-up, the movable sections are set at positions of maximum reactivity, are moved to minimum positions after about 30,000 hours and gradually returned to their original positions in about 70.000 hours.
GB38494/64A 1963-11-15 1964-09-21 Nuclear reactor Expired GB1066264A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US32414563A 1963-11-15 1963-11-15

Publications (1)

Publication Number Publication Date
GB1066264A true GB1066264A (en) 1967-04-26

Family

ID=23262291

Family Applications (1)

Application Number Title Priority Date Filing Date
GB38494/64A Expired GB1066264A (en) 1963-11-15 1964-09-21 Nuclear reactor

Country Status (5)

Country Link
BE (1) BE655683A (en)
DE (1) DE1439845A1 (en)
GB (1) GB1066264A (en)
NL (1) NL6413282A (en)
SE (1) SE306377B (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1922593A1 (en) * 1968-05-02 1970-07-30 Gen Electric Nuclear reactor with fuel element containing plutonium, which are arranged on the edge of the reactor core
CN114171214A (en) * 2021-12-03 2022-03-11 中国原子能科学研究院 Control rod system for critical apparatus

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1922593A1 (en) * 1968-05-02 1970-07-30 Gen Electric Nuclear reactor with fuel element containing plutonium, which are arranged on the edge of the reactor core
CN114171214A (en) * 2021-12-03 2022-03-11 中国原子能科学研究院 Control rod system for critical apparatus
CN114171214B (en) * 2021-12-03 2024-02-20 中国原子能科学研究院 Control rod system for critical device

Also Published As

Publication number Publication date
BE655683A (en) 1965-03-01
SE306377B (en) 1968-11-25
DE1439845A1 (en) 1969-10-23
NL6413282A (en) 1965-05-17

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