GB924748A - Improvements in or relating to nuclear reactors - Google Patents

Improvements in or relating to nuclear reactors

Info

Publication number
GB924748A
GB924748A GB2158/60A GB215860A GB924748A GB 924748 A GB924748 A GB 924748A GB 2158/60 A GB2158/60 A GB 2158/60A GB 215860 A GB215860 A GB 215860A GB 924748 A GB924748 A GB 924748A
Authority
GB
United Kingdom
Prior art keywords
shield
reactor
graphite
fuel
pressure vessel
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
GB2158/60A
Inventor
John Ewart Richards
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.)
UK Atomic Energy Authority
Original Assignee
UK Atomic Energy Authority
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 UK Atomic Energy Authority filed Critical UK Atomic Energy Authority
Priority to GB2158/60A priority Critical patent/GB924748A/en
Publication of GB924748A publication Critical patent/GB924748A/en
Expired legal-status Critical Current

Links

Classifications

    • 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
    • G21C1/10Heterogeneous 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 moderator and coolant being different or separated
    • G21C1/12Heterogeneous 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 moderator and coolant being different or separated moderator being solid, e.g. Magnox reactor or gas-graphite reactor
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C7/00Control of nuclear reaction
    • G21C7/06Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
    • 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)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

924,748. Nuclear reactors. UNITED KING- DOM ATOMIC ENERGY AUTHORITY. April 14, 1961 [Jan. 20, 1960], No. 2158/60. Class 39 (4). A plutonium - fuelled nuclear reactor has the fuel in clad sheet form arranged for fluid cooling on one face, the other face being in close proximity with a neutron moderating material. A fuel, the temperature of which can be allowed to rise several hundred degrees above the normal working temperature so that, in the event of coolant failure, the reactor will shut itself down due to its own negative temperature coefficient, comprises a cement of plutonium oxide and stainless steel particles clad in stainless steel sheet. Carbon dioxide is the preferred coolant and in the core arrangement shown in Fig. 4, flows in the spaces between hexagonal graphite cylinders 1 which are encased in the steel clad cermet sheet fuel 2 and so protected from the carbon dioxide which would otherwise oxidize the graphite at high temperatures. A preferred core arrangement is shown in Fig. 10 and comprises hexagonal graphite cylinders 5, each drilled to accommodate a plurality of steel clad cermet fuel tubes 6. The cylinders 5 are mounted between plates 14, 20, each plate 20 being attached by rods 25 to a shield plug 24 to which spring loading is applied, e.g. by Belleville washers 26, and each plate 14 having a conical collector 16 secured to it. This spring loading allows for swelling of the graphite cylinders under irradiation (Wigner effect). The conical collectors 16 are supported by a grid plate 17 mounted within the reactor pressure vessel 7 and integral with a thermal shield 29 inside which are further thermal shields 27, 28 spaced from each other and the shield 29. The upper end of the shielding is closed by a biological shield 30 of laminated steel and graphite which is bolted down to the thermal shield 29 compressing the core-loading springs. Lateral biological shielding (not shown) is outside the pressure vessel. The cooling gas enters the reactor through ducts 31 flowing up between the pressure vessel 7 and thermal shield 29 or between the graphite cylinders 5. These two coolant flows meet through ports 34 in the thermal shields 27, 28 and 29 and descend together through the fuel tubes 6 into the conical collectors 16 and thence through pipes 35, corrugated to allow for expansion, to a collector pan 36, leaving the reactor through ducts 37. A small bleed-in point 38 in the summit of the cover 39 of the reactor avoids stagnation of the gas in the upper part of the pressure vessel 7. On raising the shield 30 after the cover 39 has been removed, rollers mounted on a flange 41 of the pressure vessel 7 may be inserted into a track 40 cut into the shield which can then be rotated to provide access to any graphite cylinder 5 or fuel tube 6 through access holes 42 which are normally plugged with stepped plugs 43.
GB2158/60A 1960-01-20 1960-01-20 Improvements in or relating to nuclear reactors Expired GB924748A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
GB2158/60A GB924748A (en) 1960-01-20 1960-01-20 Improvements in or relating to nuclear reactors

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB2158/60A GB924748A (en) 1960-01-20 1960-01-20 Improvements in or relating to nuclear reactors

Publications (1)

Publication Number Publication Date
GB924748A true GB924748A (en) 1963-05-01

Family

ID=9734615

Family Applications (1)

Application Number Title Priority Date Filing Date
GB2158/60A Expired GB924748A (en) 1960-01-20 1960-01-20 Improvements in or relating to nuclear reactors

Country Status (1)

Country Link
GB (1) GB924748A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2059744A1 (en) * 1969-08-29 1971-06-04 British Nuclear Design Constr
WO2020223604A1 (en) * 2019-05-02 2020-11-05 BWXT Advanced Technologies LLC Small modular mobile fission reactor

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2059744A1 (en) * 1969-08-29 1971-06-04 British Nuclear Design Constr
WO2020223604A1 (en) * 2019-05-02 2020-11-05 BWXT Advanced Technologies LLC Small modular mobile fission reactor
US11495363B2 (en) 2019-05-02 2022-11-08 BWXT Advanced Technologies LLC Small modular mobile fission reactor

Similar Documents

Publication Publication Date Title
CN106653107B (en) A kind of liquid metal cooling passive accident afterheat discharge system of pool reactor
US3235463A (en) Nuclear reactor
ES478385A1 (en) Fast nuclear reactor with at least one auxiliary heat exchanger.
DE3518968C2 (en)
GB850015A (en) Improvements in or relating to fuel elements for nuclear reactors
GB1169714A (en) Nuclear Reactor Fuel Elements
US3127325A (en) Reactor with prompt negative temperature
Zhipeng et al. Discussion on the accident behavior and accident management of the HTGR
GB897446A (en) Improvements in or relating to nuclear reactors
DE3141892A1 (en) CORE REACTOR INSTALLED IN A CYLINDRICAL STEEL PRESSURE TANK WITH A GAS-COOLED HIGH TEMPERATURE REACTOR
GB1128826A (en) Fuel assembly for a nuclear reactor cooled by a liquid metal
US3271260A (en) Liquid metal fast breeder reactor
GB924748A (en) Improvements in or relating to nuclear reactors
GB862624A (en) Improvements in or relating to nuclear reactor installations
GB847636A (en) Improvements in or relating to nuclear reactor refuelling devices
US3211623A (en) Neutronic reactor and fuel element therefor
US3378457A (en) Cermet and ceramic fuel element
GB1241441A (en) Improvements in or relating to nuclear reactors
Foster et al. Effects of Temperature Changes on the Swelling Behavior of 20% Cold-Worked AISI Type 316 Stainless Steel
Zhu et al. Neutronic design and fuel cycle analysis of a fluoride salt-cooled High Temperature Reactor (FHR)
Ohashi et al. Conceptual Plant System Design Study of an Experimental HTGR upgraded from HTTR
Appleby Compilation of data and descriptions for United States and foreign liquid metal fast breeder reactors
Abuqudaira et al. Perspective Chapter: Assessment of Nuclear Sensors and Instrumentation Maturity in Advanced Nuclear Reactors
Petersen et al. The Fission Product Retention of Pebble-Bed Reactors in Ultimate Accidents
Mitchell et al. THE HIGH TEMPERATURE ZERO ENERGY REACTOR" ZENITH"