GB1126323A - Improvements in or relating to high temperature gas cooled reactors - Google Patents

Improvements in or relating to high temperature gas cooled reactors

Info

Publication number
GB1126323A
GB1126323A GB921/65A GB92165A GB1126323A GB 1126323 A GB1126323 A GB 1126323A GB 921/65 A GB921/65 A GB 921/65A GB 92165 A GB92165 A GB 92165A GB 1126323 A GB1126323 A GB 1126323A
Authority
GB
United Kingdom
Prior art keywords
fuel
holes
coolant
coated
channels
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
GB921/65A
Inventor
Pierre Jean Camille Alb Marien
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 GB921/65A priority Critical patent/GB1126323A/en
Priority to BE674751D priority patent/BE674751A/xx
Priority to AT11366A priority patent/AT265450B/en
Priority to FR45250A priority patent/FR1463313A/en
Priority to CH33966A priority patent/CH429966A/en
Priority to DEE22755U priority patent/DE1935094U/en
Publication of GB1126323A publication Critical patent/GB1126323A/en
Expired legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C5/00Moderator or core structure; Selection of materials for use as moderator
    • G21C5/14Moderator or core structure; Selection of materials for use as moderator characterised by shape
    • G21C5/16Shape of its constituent parts
    • 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
    • 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
    • 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)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Devices And Processes Conducted In The Presence Of Fluids And Solid Particles (AREA)

Abstract

1,126,323. Fuel elements. UNITED KING- DOM ATOMIC ENERGY AUTHORITY. 7 Jan., 1966 [8 Jan., 1965], No. 921/65. Heading G6C. A nuclear reactor fuel assembly comprises a number of columnar blocks of moderating material, each of the blocks containing axially extending channels, at least some of which contain nuclear fuel particles having fission product retaining outer layers. In one embodiment, as shown in Fig. 1, a graphite block 1 of hexagonal cross-section is penetrated by a number of holes 2 which receive fuelled bodies formed with a series of holes, at least one of these holes serving as a coolant flowpath and others containing fission product retaining fuel, e.g. coated nuclear fuel particles dispersed in moderator material. A first form of fuelled body 3a comprises an open ended graphite cylinder 11 providing a central coolant channel 12 and frirmed with an annular row of holes 13 containing nuclear fuel 14. A second similar form of fuelled body 3b comprises an open ended cylinder 15 which is, however, centralized with respect to, and spaced from, the wall of a hole 16 by extension ribs 15a. Several outer coolant channels 17 are thus provided as well as an inner coolant channel 18. In a second embodi- ment, as shown in Fig. 2A, an hexagonal graphite block 30 is formed with an array of holes 31, 32 of four different diameters: the holes 31 of the largest diameter serving as coolant channels C penetrate the block completely, whilst the holes 32 of smaller diameters are blind and retain nuclear fuel bodies 33. The latter are cylindrical regions of loose or consolidated fuel particles coated with fission product retaining material. A coolant channel C is located at the centre of each group of holes 32. In both embodiments, the fuel may be placed in the holes by firstly filling these with coated fuel particles and then depositing carbon in the interstices between the particles, e.g. from the gas phase. In an alternative arrangement (Fig. 28, not shown), the graphite block 30 is of circular cross-section and is enclosed by a tubular sleeve of hexagonal cross-section. In any of the described fuel arrangements, the bores of the coolant channels may be coated with pyrolytic carbon or SiC to reduce the rate at which the hot coolant gas passing through the channels corrodes the matrix material. By distributing the fuel in lumped segregated zones spaced apart in a block of moderator, a low enriched fuel (about 5% by wt. U-235) can be substituted for the more highly enriched fuel normally associated with reactors employing fuel in a coated particle form.
GB921/65A 1965-01-08 1965-01-08 Improvements in or relating to high temperature gas cooled reactors Expired GB1126323A (en)

Priority Applications (6)

Application Number Priority Date Filing Date Title
GB921/65A GB1126323A (en) 1965-01-08 1965-01-08 Improvements in or relating to high temperature gas cooled reactors
BE674751D BE674751A (en) 1965-01-08 1966-01-05
AT11366A AT265450B (en) 1965-01-08 1966-01-05 Fuel element for a nuclear reactor
FR45250A FR1463313A (en) 1965-01-08 1966-01-07 Improvement in nuclear reactors cooled by gases at high temperature
CH33966A CH429966A (en) 1965-01-08 1966-01-07 Body containing fuel for use in nuclear reactors
DEE22755U DE1935094U (en) 1965-01-08 1966-01-07 FUEL ELEMENT FOR THE CORE OF A NUCLEAR REACTOR.

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB921/65A GB1126323A (en) 1965-01-08 1965-01-08 Improvements in or relating to high temperature gas cooled reactors

Publications (1)

Publication Number Publication Date
GB1126323A true GB1126323A (en) 1968-09-05

Family

ID=9712858

Family Applications (1)

Application Number Title Priority Date Filing Date
GB921/65A Expired GB1126323A (en) 1965-01-08 1965-01-08 Improvements in or relating to high temperature gas cooled reactors

Country Status (6)

Country Link
AT (1) AT265450B (en)
BE (1) BE674751A (en)
CH (1) CH429966A (en)
DE (1) DE1935094U (en)
FR (1) FR1463313A (en)
GB (1) GB1126323A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN104183279A (en) * 2014-08-26 2014-12-03 南华大学 Inner-cooling pressurized-water reactor core
US20210304909A1 (en) * 2019-08-29 2021-09-30 BWXT Advanced Technologies LLC Robust nuclear propulsion fission reactor with tri-pitch patterned core and drum absorbers

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN117038128B (en) * 2023-07-07 2024-06-04 华能核能技术研究院有限公司 Ball bed type reactor fuel element counting instrument mounting device

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN104183279A (en) * 2014-08-26 2014-12-03 南华大学 Inner-cooling pressurized-water reactor core
US20210304909A1 (en) * 2019-08-29 2021-09-30 BWXT Advanced Technologies LLC Robust nuclear propulsion fission reactor with tri-pitch patterned core and drum absorbers
US11990248B2 (en) * 2019-08-29 2024-05-21 BWXT Advanced Technologies LLC Robust nuclear propulsion fission reactor with tri-pitch patterned core and drum absorbers

Also Published As

Publication number Publication date
FR1463313A (en) 1966-12-23
AT265450B (en) 1968-10-10
DE1935094U (en) 1966-03-24
BE674751A (en) 1966-07-05
CH429966A (en) 1967-02-15

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