FR2036822A1 - Gas cooled, graphite moderated nuclear - reactor - Google Patents

Gas cooled, graphite moderated nuclear - reactor

Info

Publication number
FR2036822A1
FR2036822A1 FR6910490A FR6910490A FR2036822A1 FR 2036822 A1 FR2036822 A1 FR 2036822A1 FR 6910490 A FR6910490 A FR 6910490A FR 6910490 A FR6910490 A FR 6910490A FR 2036822 A1 FR2036822 A1 FR 2036822A1
Authority
FR
France
Prior art keywords
reactor
guide
gas cooled
core
moderated nuclear
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.)
Withdrawn
Application number
FR6910490A
Other languages
French (fr)
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.)
Atomic Power Constructions Ltd
Original Assignee
Atomic Power Constructions 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 Atomic Power Constructions Ltd filed Critical Atomic Power Constructions Ltd
Priority to FR6910490A priority Critical patent/FR2036822A1/en
Publication of FR2036822A1 publication Critical patent/FR2036822A1/en
Withdrawn legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C13/00Pressure vessels; Containment vessels; Containment in general
    • G21C13/02Details
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C19/00Arrangements 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
    • G21C19/02Details of handling arrangements
    • G21C19/04Means for controlling flow of coolant over objects being handled; Means for controlling flow of coolant through channel being serviced, e.g. for preventing "blow-out"
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/30Assemblies of a number of fuel elements in the form of a rigid unit
    • G21C3/32Bundles of parallel pin-, rod-, or tube-shaped fuel elements
    • 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)
  • Production Of Liquid Hydrocarbon Mixture For Refining Petroleum (AREA)

Abstract

Each of a number of loading channels through which fuel elements or units are introduced to, and withdrawn from, the core to the reactor has a constriction which serves as a guide for the movement of the element into and out of the core but which does not reduce the effective cross sectional area of the passage for coolant flow. This guide construction is formed by a tubular insert spaced away from the walls of the main coolant channel. At least one part of this guide has a truncated conical section and has perforated walls.
FR6910490A 1969-04-04 1969-04-04 Gas cooled, graphite moderated nuclear - reactor Withdrawn FR2036822A1 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
FR6910490A FR2036822A1 (en) 1969-04-04 1969-04-04 Gas cooled, graphite moderated nuclear - reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR6910490A FR2036822A1 (en) 1969-04-04 1969-04-04 Gas cooled, graphite moderated nuclear - reactor

Publications (1)

Publication Number Publication Date
FR2036822A1 true FR2036822A1 (en) 1970-12-31

Family

ID=9031957

Family Applications (1)

Application Number Title Priority Date Filing Date
FR6910490A Withdrawn FR2036822A1 (en) 1969-04-04 1969-04-04 Gas cooled, graphite moderated nuclear - reactor

Country Status (1)

Country Link
FR (1) FR2036822A1 (en)

Similar Documents

Publication Publication Date Title
GB1256198A (en) Nuclear fuel assembly
ES408794A1 (en) Nuclear fuel assembly with bypass coolant control
GB1197461A (en) Improvements in or relating to Nuclear Reactors
FR2036822A1 (en) Gas cooled, graphite moderated nuclear - reactor
ES317805A1 (en) A caperuza to receive and drive the gases from a basic oxygen oven. (Machine-translation by Google Translate, not legally binding)
US3133000A (en) Fuel elements for nuclear reactors
GB1502427A (en) Nuclear reactor coolant channels
US3206370A (en) Nuclear reactor core
GB933510A (en) Pressure tube reactor
ES238326A1 (en) Improvements relating to nuclear reactors
GB1023133A (en) Improvements in or relating to fuel elements for nuclear reactors
FR2058306A1 (en) Nuclear reactor fuel rod assembly with sep - arate nose-piece intercepting a coolant
GB1252519A (en)
SE8301495L (en) KERNBRENSLEANORDNING
GB942411A (en) Heterogenous nuclear reactor
CH379008A (en) Method for obtaining a matrix network for detecting sheath breaks in the channels of a nuclear reactor, and matrix network obtained by this method
ES286481A1 (en) A nucleus structure for nuclear reactor (Machine-translation by Google Translate, not legally binding)
GB1117315A (en) Nuclear reactors
GB974129A (en) Improvements relating to nuclear reactors
BE606903A (en) Process for refining metallic elements belonging to groups II to VI of the periodic system.
FR2409578A1 (en) MODERATE GRAPHITE NUCLEAR REACTOR COOLED BY GAS
ES237980A1 (en) Improvements relating to moderator structures for nuclear reactors
US3379243A (en) Device for the heat insulation of reactor channels
GB1336968A (en) Fuel assembly for nuclear reactors
GB1500436A (en) Nuclear reactor coolant channels

Legal Events

Date Code Title Description
ST Notification of lapse