GB1131480A - Improvements in or relating to nuclear reactor fuel elements - Google Patents

Improvements in or relating to nuclear reactor fuel elements

Info

Publication number
GB1131480A
GB1131480A GB50760/66A GB5076066A GB1131480A GB 1131480 A GB1131480 A GB 1131480A GB 50760/66 A GB50760/66 A GB 50760/66A GB 5076066 A GB5076066 A GB 5076066A GB 1131480 A GB1131480 A GB 1131480A
Authority
GB
United Kingdom
Prior art keywords
fuel
trap
fuel element
bao
sheath
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
GB50760/66A
Inventor
Robert Dorrell Collins
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 GB50760/66A priority Critical patent/GB1131480A/en
Priority to DE19671614942 priority patent/DE1614942A1/en
Priority to FR126373A priority patent/FR1543628A/en
Priority to BE706377D priority patent/BE706377A/xx
Priority to JP42072546A priority patent/JPS4823238B1/ja
Publication of GB1131480A publication Critical patent/GB1131480A/en
Expired legal-status Critical Current

Links

Classifications

    • 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
    • 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
    • G21C3/16—Details of the construction within the casing
    • 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
    • G21C3/16—Details of the construction within the casing
    • G21C3/17—Means for storage or immobilisation of gases in fuel elements
    • 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)
  • Solid-Sorbent Or Filter-Aiding Compositions (AREA)
  • Treating Waste Gases (AREA)

Abstract

1,131,480. Fuel elements. UNITED KING- DOM ATOMIC ENERGY AUTHORITY. 11 Oct., 1967 [11 Nov., 1966], No. 50760/66. Heading G6C. In a fuel element in which UO 2 is encased in a protective sheath, BaO is included within the sheath to form a trap for the I-131 fission product. Preferably the BaO is dispersed in a matrix, e.g. compressed stainless steel mesh or activated alumina, to provide a relatively large surface area. When used with a fuel element in which the sheath is completely sealed about the fuel, the trap is preferably positioned at the cooler end of the fuel element as fission products with their low vapour pressure will tend to collect there. Intermediate traps may, however, also be desirable, particularly if the fuel element is more than a few feet in length. The use of hollow fuel pellets is an advantage since the fission products then have a readier access to the trap. In the case of a vented fuel element, the trap may conveniently be provided in the vent path. The invention may also be applied to fuel elements which are connected internally to a He source and continuously purged, traps being provided to clean up the He which is recirculated. In vented fuel elements for a CO 2 -cooled reactor, an activated charcoal bed for trapping Cs and Te fission products may be used in addition to the BaO trap.
GB50760/66A 1966-11-11 1966-11-11 Improvements in or relating to nuclear reactor fuel elements Expired GB1131480A (en)

Priority Applications (5)

Application Number Priority Date Filing Date Title
GB50760/66A GB1131480A (en) 1966-11-11 1966-11-11 Improvements in or relating to nuclear reactor fuel elements
DE19671614942 DE1614942A1 (en) 1966-11-11 1967-10-27 Nuclear reactor fuel element
FR126373A FR1543628A (en) 1966-11-11 1967-10-30 Fuel cartridges for nuclear reactors
BE706377D BE706377A (en) 1966-11-11 1967-11-10
JP42072546A JPS4823238B1 (en) 1966-11-11 1967-11-11

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB50760/66A GB1131480A (en) 1966-11-11 1966-11-11 Improvements in or relating to nuclear reactor fuel elements

Publications (1)

Publication Number Publication Date
GB1131480A true GB1131480A (en) 1968-10-23

Family

ID=10457248

Family Applications (1)

Application Number Title Priority Date Filing Date
GB50760/66A Expired GB1131480A (en) 1966-11-11 1966-11-11 Improvements in or relating to nuclear reactor fuel elements

Country Status (4)

Country Link
JP (1) JPS4823238B1 (en)
BE (1) BE706377A (en)
DE (1) DE1614942A1 (en)
GB (1) GB1131480A (en)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3804709A (en) * 1972-05-15 1974-04-16 Gen Electric Nuclear fuel element

Also Published As

Publication number Publication date
DE1614942A1 (en) 1970-06-25
JPS4823238B1 (en) 1973-07-12
BE706377A (en) 1968-05-10

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