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GB1427620A - Nuclear reactors - Google Patents

Nuclear reactors

Info

Publication number
GB1427620A
GB1427620A GB2623373A GB2623373A GB1427620A GB 1427620 A GB1427620 A GB 1427620A GB 2623373 A GB2623373 A GB 2623373A GB 2623373 A GB2623373 A GB 2623373A GB 1427620 A GB1427620 A GB 1427620A
Authority
GB
United Kingdom
Prior art keywords
columns
refuelling
probe
column
standpipe
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
GB2623373A
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.)
Nuclear Power Co Whetstone Ltd
Original Assignee
Nuclear Power Co Whetstone Ltd
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 Nuclear Power Co Whetstone Ltd filed Critical Nuclear Power Co Whetstone Ltd
Priority to GB2623373A priority Critical patent/GB1427620A/en
Priority to FR7417803A priority patent/FR2234635B1/fr
Priority to DE19742426498 priority patent/DE2426498A1/en
Priority to JP49061457A priority patent/JPS5031292A/ja
Publication of GB1427620A publication Critical patent/GB1427620A/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
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/20—Arrangements for introducing objects into the pressure vessel; Arrangements for handling objects within the pressure vessel; Arrangements for removing objects from the pressure vessel
    • 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)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

1427620 Fuelling reactors NUCLEAR POWER CO (WHETSTONE) Ltd 21 May 1974 [1 June 1973] 26233/73 Heading G6C In a nuclear reactor, especially a high temperature reactor, having a core 20 of parallel columns 21 of moderator blocks of hexagonal cross-section within a pressure envelope 37, the envelope is provided with refuelling standpipes 23 each having its axis coincident with the common vertex of three adjacent columns of an associated group of twelve columns, consisting of three columns and the nine columns which immediately surround them, and the associated refuelling machine comprises a probe arrangeged to be introduced into the pressure envelope through the standpipe and carries a radially displaceable coupling means capable of engaging and removing any selected column in the group. For peripheral columns, not accommodatable in symmetrical groups of twelve, a uniform standpipe spacing is maintained. If the columns in a group are numbered 1 to 12 as in Fig. 2, satellite standpipes 25 are disposed as shown and contain shut-down rods 28. A trim rod 26 is associated with column 1 and secondary shutdown rods 27 with columns 5 and 9; rods 26, 27 are within standpipe 23. Refuelling-. Fig. 3 illustrates the method of refuelling applied to columns 1 to 4: a sleeve 29 with a fixed absorber at I and J is positioned before refuelling, the refuelling probe is centred on B and, after introduction through standpipe 23, is rotated to carry a cranked end to position C. A column is lifted clear and withdrawn along locus DC by inward movement of displaceable coupling means until at point C. The probe is then rotated through 180 degrees about its axis to locate the column at A and the probe is then raised. For removing blocks of column 4 the cranked end of the probe is rotated to C 1 . An alternative arrangement uses a radius of 2r. A refuelling tool may incorporate a grab Fig. 4 (not shown), or a pick-up inserted through the blocks, Figs. 5, 6 (neither shown). Refuelling can be rotated to suit irradiation and burn-up requirements in specific parts of the core.
GB2623373A 1973-06-01 1973-06-01 Nuclear reactors Expired GB1427620A (en)

Priority Applications (4)

Application Number Priority Date Filing Date Title
GB2623373A GB1427620A (en) 1973-06-01 1973-06-01 Nuclear reactors
FR7417803A FR2234635B1 (en) 1973-06-01 1974-05-22
DE19742426498 DE2426498A1 (en) 1973-06-01 1974-05-31 NUCLEAR REACTOR
JP49061457A JPS5031292A (en) 1973-06-01 1974-06-01

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB2623373A GB1427620A (en) 1973-06-01 1973-06-01 Nuclear reactors

Publications (1)

Publication Number Publication Date
GB1427620A true GB1427620A (en) 1976-03-10

Family

ID=10240433

Family Applications (1)

Application Number Title Priority Date Filing Date
GB2623373A Expired GB1427620A (en) 1973-06-01 1973-06-01 Nuclear reactors

Country Status (4)

Country Link
JP (1) JPS5031292A (en)
DE (1) DE2426498A1 (en)
FR (1) FR2234635B1 (en)
GB (1) GB1427620A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP2518733A4 (en) * 2009-12-23 2015-07-08 Univ Tsinghua STEAM GENERATION SYSTEM WITH GAS-COOLED HIGH-TEMPERATURE REACTOR AND METHOD

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH0782110B2 (en) * 1991-08-07 1995-09-06 動力炉・核燃料開発事業団 Refueling method in reactor

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP2518733A4 (en) * 2009-12-23 2015-07-08 Univ Tsinghua STEAM GENERATION SYSTEM WITH GAS-COOLED HIGH-TEMPERATURE REACTOR AND METHOD

Also Published As

Publication number Publication date
DE2426498A1 (en) 1974-12-19
FR2234635B1 (en) 1978-04-21
FR2234635A1 (en) 1975-01-17
JPS5031292A (en) 1975-03-27

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Legal Events

Date Code Title Description
PS Patent sealed [section 19, patents act 1949]
PCNP Patent ceased through non-payment of renewal fee