GB938446A - Compact mobile nuclear power plant - Google Patents

Compact mobile nuclear power plant

Info

Publication number
GB938446A
GB938446A GB40651/61A GB4065161A GB938446A GB 938446 A GB938446 A GB 938446A GB 40651/61 A GB40651/61 A GB 40651/61A GB 4065161 A GB4065161 A GB 4065161A GB 938446 A GB938446 A GB 938446A
Authority
GB
United Kingdom
Prior art keywords
fuel
zirconium
alpha
hydrogen
delta
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
GB40651/61A
Inventor
Joseph Ronald Wetch
Herman Maier Dieckamp
Monte Vincent Davis
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.)
North American Aviation Corp
Original Assignee
North American Aviation Corp
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 North American Aviation Corp filed Critical North American Aviation Corp
Publication of GB938446A publication Critical patent/GB938446A/en
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
    • G21C1/10—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 moderator and coolant being different or separated
    • G21C1/12—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 moderator and coolant being different or separated moderator being solid, e.g. Magnox reactor or gas-graphite reactor
    • 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
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G21C1/04—Thermal reactors ; Epithermal reactors
    • G21C1/24—Homogeneous reactors, i.e. in which the fuel and moderator present an effectively homogeneous medium to the neutrons
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C11/00—Shielding structurally associated with the reactor
    • G21C11/06—Reflecting shields, i.e. for minimising loss of neutrons
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C13/00—Pressure vessels; Containment vessels; Containment in general
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C13/00—Pressure vessels; Containment vessels; Containment in general
    • G21C13/02—Details
    • G21C13/06—Sealing-plugs
    • G21C13/073—Closures for reactor-vessels, e.g. rotatable
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C13/00—Pressure vessels; Containment vessels; Containment in general
    • G21C13/08—Vessels characterised by the material; Selection of materials for pressure vessels
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02—Fuel elements
    • G21C3/04—Constructional details
    • G21C3/06—Casings; Jackets
    • G21C3/14—Means forming part of the element for inserting it into, or removing it from, the core; Means for coupling adjacent elements, e.g. to form a stringer
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/42—Selection of substances for use as reactor fuel
    • G21C3/58—Solid reactor fuel Pellets made of fissile material
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C5/00—Moderator or core structure; Selection of materials for use as moderator
    • G21C5/12—Moderator or core structure; Selection of materials for use as moderator characterised by composition, e.g. the moderator containing additional substances which ensure improved heat resistance of the moderator
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C7/00—Control of nuclear reaction
    • G21C7/005—Flux flattening
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C7/00—Control of nuclear reaction
    • G21C7/28—Control of nuclear reaction by displacement of the reflector or parts thereof
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D5/00—Arrangements of reactor and engine in which reactor-produced heat is converted into mechanical energy
    • G21D5/02—Reactor and engine structurally combined, e.g. portable
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D5/00—Arrangements of reactor and engine in which reactor-produced heat is converted into mechanical energy
    • G21D5/04—Reactor and engine not structurally combined
    • G21D5/06—Reactor and engine not structurally combined with engine working medium circulating through reactor core
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D3/00—Control of nuclear power plant
    • G21D3/02—Manual control
    • 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
    • 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)
  • Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Inorganic Compounds Of Heavy Metals (AREA)

Abstract

938,446. Alloys. NORTH AMERICAN AVIATION Inc. Nov. 14, 1961, No. 40651/61. Class 82. [Also in Group XL (a)] A uranium-zirconium hydride alloy is used as the fuel in a nuclear reactor core and behaves as a mechanical mixture of zirconium hydride and uranium metal. The fuel operates between 300‹ C. and 550‹ C. and has a H/Zr ratio of about 0.6 to about 1.4. This places it on the hatched area of the Zr-H phase diagram where the dissociation pressure is less than 11 microns at the fuel centre temperature and about 0.01 microns at the surface temperature, and is independent of composition since it is in a twophase region (alpha and delta). Structurally the mixture is about 80 a/o ZrH 1À5 dispersed in 20 a/o alpha zirconium. In this region the disadvantages of the brittle delta phase are reduced. Further, the proposed fuel contains the same mixed phases in the same proportion from room temperature up to about 575‹ C. The lower limit of hydrogen concentration, i.e. about 40 a/o, is dictated by the extremely low limit of hydrogen solubility in alpha zirconium (ZrH x , where x is less than 0.1). Therefore, sufficient delta phase must be present so that sufficient hydrogen can be present in the zirconium hydride system.
GB40651/61A 1961-12-04 1961-11-14 Compact mobile nuclear power plant Expired GB938446A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
DEN0020925 1961-12-04

Publications (1)

Publication Number Publication Date
GB938446A true GB938446A (en) 1963-10-02

Family

ID=7341502

Family Applications (1)

Application Number Title Priority Date Filing Date
GB40651/61A Expired GB938446A (en) 1961-12-04 1961-11-14 Compact mobile nuclear power plant

Country Status (4)

Country Link
CH (1) CH415879A (en)
DE (1) DE1414964B1 (en)
GB (1) GB938446A (en)
NL (1) NL271842A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US9230696B2 (en) 2010-05-07 2016-01-05 Westinghouse Electric Sweden Ab Control rod for a nuclear power light water reactor
EP4042449A4 (en) * 2019-10-04 2023-11-29 Ultra Safe Nuclear Corporation Automatic shutdown controller for nuclear reactor system with control drums

Family Cites Families (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3019176A (en) * 1957-11-21 1962-01-30 Gen Dynamics Corp Fuel element
GB879282A (en) * 1959-07-03 1961-10-11 North American Aviation Inc Steam superheat boiling water nuclear reactor

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US9230696B2 (en) 2010-05-07 2016-01-05 Westinghouse Electric Sweden Ab Control rod for a nuclear power light water reactor
EP4042449A4 (en) * 2019-10-04 2023-11-29 Ultra Safe Nuclear Corporation Automatic shutdown controller for nuclear reactor system with control drums

Also Published As

Publication number Publication date
CH415879A (en) 1966-06-30
NL271842A (en) 1900-01-01
DE1414964B1 (en) 1970-06-18

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