GB824829A - Nuclear reactors - Google Patents

Nuclear reactors

Info

Publication number
GB824829A
GB824829A GB4330/58A GB433058A GB824829A GB 824829 A GB824829 A GB 824829A GB 4330/58 A GB4330/58 A GB 4330/58A GB 433058 A GB433058 A GB 433058A GB 824829 A GB824829 A GB 824829A
Authority
GB
United Kingdom
Prior art keywords
nuclear reactors
silicon
zirconium
uranium
alloy
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
GB4330/58A
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.)
Sulzer AG
Original Assignee
Sulzer AG
Gebrueder Sulzer AG
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 Sulzer AG, Gebrueder Sulzer AG filed Critical Sulzer AG
Publication of GB824829A publication Critical patent/GB824829A/en
Expired legal-status Critical Current

Links

Classifications

    • 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
    • G21C1/14Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor
    • G21C1/16Heterogeneous 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
    • G21C1/18Heterogeneous 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
    • G21C1/20Heterogeneous 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
    • 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
    • G21C15/06Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from fissile or breeder material in fuel elements
    • 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
    • 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
    • G21C3/16Details of the construction within the casing
    • 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

Abstract

An alloy of uranium for use in a nuclear reactor contains up to 1.5% of silicon and 5% if zirconium alternatively up to 1.5% of silicon and 1.5% of iron. A further alloy described comprises uranium with up to 7% of zirconium and up to 3% of niobium.
GB4330/58A 1957-04-17 1958-02-10 Nuclear reactors Expired GB824829A (en)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
CH348212T 1957-04-17
CH350724T 1957-05-28

Publications (1)

Publication Number Publication Date
GB824829A true GB824829A (en) 1959-12-02

Family

ID=4539817

Family Applications (1)

Application Number Title Priority Date Filing Date
GB4330/58A Expired GB824829A (en) 1957-04-17 1958-02-10 Nuclear reactors

Country Status (5)

Country Link
BE (1) BE566754A (en)
CH (2) CH348212A (en)
DE (1) DE1080236B (en)
FR (1) FR1203515A (en)
GB (1) GB824829A (en)

Families Citing this family (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
NL281496A (en) * 1962-06-13 1900-01-01
BE637885A (en) * 1962-10-22
US3156625A (en) * 1962-10-22 1964-11-10 Harty Harold Core for a supercritical pressure power reactor
GB1169714A (en) * 1966-08-08 1969-11-05 Atomic Energy Authority Uk Nuclear Reactor Fuel Elements

Family Cites Families (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
BE626837A (en) * 1955-02-16 1900-01-01

Also Published As

Publication number Publication date
DE1080236B (en) 1960-04-21
CH350724A (en) 1960-12-15
CH348212A (en) 1960-08-15
FR1203515A (en) 1960-01-19
BE566754A (en) 1958-10-14

Similar Documents

Publication Publication Date Title
GB807817A (en) Fuel-breeder fuel element for nuclear reactor
GB837769A (en) A nuclear reactor
GB824829A (en) Nuclear reactors
AU235753B2 (en) Improvements in and relating tothe fabrication of reactive or neutron-absorbing nuclear reactor elements
GB838324A (en) Process for enclosing a body containing fissionable material in a jacket
AU217374B2 (en) Improvements relating to nuclear reactors and fuel elements therefor
AU223047B2 (en) Improvements in nuclear reactors andin or relating to nuclear reactor fuel elements
AU2149856A (en) Improvements relating to nuclear reactors and fuel elements therefor
AU214958B2 (en) Improvements in and relating to nuclear reactors
AU228280B2 (en) Improvements in or relating to graphite moderator structures for nuclear reactors
AU3070057A (en) Improvements in nuclear reactors andin or relating to nuclear reactor fuel elements
AU229519B2 (en) Improvements in or relating to a nuclear reactor and to a method of operating same
AU219754B2 (en) Improvements relating to fuel elements for nuclear reactors and to nuclear reactors using such elements
AU2336956A (en) Improvements in and relating to nuclear reactors
AU4256158A (en) Improvements in or relating to graphite moderator structures for nuclear reactors
AU222809B2 (en) Improvements in and relating to nuclear reactors
AU223903B2 (en) Improvements in and relating to nuclear reactors
AU226675B2 (en) Improvements in and relating to nuclear reactors
AU227281B2 (en) Improvements in and relating to nuclear reactors
AU221126B2 (en) Improvements in or relating to moderator and reflector structures for nuclear reactors
AU220648B2 (en) Improvements in and relating to fuel elements for nuclear reactors
AU226454B2 (en) Improvements in and relating to fuel elements for nuclear reactors
AU222172B2 (en) Improvements in and relating to fuel elements for nuclear reactors
AU223770B2 (en) Improvements in and relating to fuel elements for nuclear reactors
AU225637B2 (en) Improvements in or'relating to fuel for nuclear reactors