GB918907A - Method of obtaining a uniform output density in gas-cooled high-temperature nuclear reactors - Google Patents

Method of obtaining a uniform output density in gas-cooled high-temperature nuclear reactors

Info

Publication number
GB918907A
GB918907A GB35946/61A GB3594661A GB918907A GB 918907 A GB918907 A GB 918907A GB 35946/61 A GB35946/61 A GB 35946/61A GB 3594661 A GB3594661 A GB 3594661A GB 918907 A GB918907 A GB 918907A
Authority
GB
United Kingdom
Prior art keywords
cone
bodies
determined
fissile
reactor
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
GB35946/61A
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.)
Beteiligungs und Patentverwaltungs GmbH
BBC Brown Boveri AG Germany
BBC Brown Boveri France SA
Original Assignee
Beteiligungs und Patentverwaltungs GmbH
Brown Boveri und Cie AG Germany
BBC Brown Boveri France SA
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 Beteiligungs und Patentverwaltungs GmbH, Brown Boveri und Cie AG Germany, BBC Brown Boveri France SA filed Critical Beteiligungs und Patentverwaltungs GmbH
Publication of GB918907A publication Critical patent/GB918907A/en
Expired legal-status Critical Current

Links

Classifications

    • 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
    • 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
    • G21C1/07—Pebble-bed reactors; Reactors with granular fuel
    • 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
    • G21C19/202—Arrangements for handling ball-form, i.e. pebble fuel
    • 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

918,907. Nuclear reactors. BROWN, BOVERI & CIE A.G., and BETEILIGUNGSUND PATENTVERWALTUNGSGESELLSCHAFT. Oct. 5, 1961 [March 4, 1961], No. 35946/61. Class 39 (4). In a gas-cooled nuclear reactor shaped bodies, preferably balls, containing fissile, breeder, inert or moderating material are fed downwardly into the core of the reactor and form a mound or cone, the bodies being introduced into the reactor in dependence upon the size of the angle of slope of the cone. The object of the invention is to obtain a uniform neutron density in the cone and is done by a distribution of the different types of material, so that on building the cone bodies of a lower fission cross-section are placed close to the axis of the cone, and fissile material is placed around the periphery. The bodies are discharged through a tapered part of the core bottom and after discharge the upper sloping part of the cone collapses. The bodies of small fission cross-section build up the upper part of the cone and when this is completed fissile bodies fall on to the cone and roll into the peripheral zone. The building-up of the cone may be determined by electroconduction, several level gauges and by measuring the neutron distribution, but the simplest method is that from a determined amount of bodies the cone has a determined slope and reaches a maximum of about 22 degrees. The quantity of discharged spheres is determined by counting, weighing or the like, and from this result the number to be fed to the core is known, which is counted by a manual or automatic control device or a programme register.
GB35946/61A 1961-03-04 1961-10-05 Method of obtaining a uniform output density in gas-cooled high-temperature nuclear reactors Expired GB918907A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
DEB61520A DE1191049B (en) 1961-03-04 1961-03-04 Process for achieving a uniform power density in gas-cooled pebble bed high-temperature nuclear reactors

Publications (1)

Publication Number Publication Date
GB918907A true GB918907A (en) 1963-02-20

Family

ID=6973222

Family Applications (1)

Application Number Title Priority Date Filing Date
GB35946/61A Expired GB918907A (en) 1961-03-04 1961-10-05 Method of obtaining a uniform output density in gas-cooled high-temperature nuclear reactors

Country Status (4)

Country Link
BE (1) BE614603A (en)
DE (1) DE1191049B (en)
GB (1) GB918907A (en)
NL (1) NL269759A (en)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN111128419B (en) * 2019-12-30 2023-01-24 福建福清核电有限公司 Nuclear power plant fuel assembly integrity judgment method

Family Cites Families (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
BE549566A (en) * 1955-07-18
DE1034784B (en) * 1956-03-16 1958-07-24 Dr Rudolf Schulten Nuclear reactor with gas cooling
NL269758A (en) * 1956-05-17
DE1025535B (en) * 1956-08-24 1958-03-06 Steinmueller Gmbh L & C Method for achieving a neutron flux that is equalized in the normal planes to the direction of coolant flow in thermal reactors cooled by liquid or gaseous media
BE568348A (en) * 1957-06-07
DE1053682B (en) * 1957-11-16 1959-03-26 Bbc Brown Boveri & Cie Process for carrying out nuclear reactions in a breeder reactor
DE1095959B (en) * 1958-12-03 1960-12-29 Babcock & Wilcox Dampfkessel High pressure reactor

Also Published As

Publication number Publication date
NL269759A (en)
BE614603A (en) 1962-09-03
DE1191049B (en) 1965-04-15

Similar Documents

Publication Publication Date Title
ES8103444A1 (en) Determining fissile content of nuclear fuel elements
GB1240235A (en) Method for the non-destructive assay of bulk nuclear reactor fuel and apparatus
GB915190A (en) Improvements in nuclear reactors
US4325785A (en) Method and apparatus for measuring the reactivity of a spent fuel assembly
GB918907A (en) Method of obtaining a uniform output density in gas-cooled high-temperature nuclear reactors
ES8608717A1 (en) Apparatus for detecting and measuring nuclear flux density within a nuclear reactor.
GB1446086A (en) Method for the passive protection of a nuclear reactor
GB839392A (en) "process for carrying out a nuclear reaction in a breeding reactor"
US3650894A (en) Method of measuring the nuclear physical behavior of bodies
JPS53123795A (en) Device for making spherical particle from drop of aqueous solution of nitrate of uranium* plutonium*thorium or mixture of them for nuclear reactor fuel element or breeding material
GB818685A (en) Improvements in fission product detection systems
GB912222A (en) Apparatus for the generation of short-time neutron impulses
Burtscher Experience with the standard neutron irradiation facility in the ASTRA reactor
GB974314A (en) Improvements in or relating to the testing of fuel elements for nuclear reactors
Level FIGURE I. PRTR Moderator Level Coeffi-cient of Reactivity
JPS5493795A (en) Concentration mesearing method and device of neutron strong absorbent in fuel rod
GB917776A (en) Method of measuring the amount of material fissile by thermal neutrons and present in any arbitrary substance, particularly for controlling the state of exhaustion of fuel elements in nuclear reactors
GB861602A (en) Improvements in or relating to nuclear reactor fuel compositions
AT338385B (en) METHOD OF MEASURING THE POWER DISTRIBUTION IN THERMAL REACTOR CORES
Bramblett Fuel rod scanner for quality control and safeguards
GB946901A (en) Nuclear reactor with fixed bed fuel elements
DE3166316D1 (en) Energy production installation comprising several fast neutron breeder nuclear reactors and an apparatus for charging and discharging fuel elements
GB818776A (en) Improvements relating to thermal apparatus
Lillegraven et al. Fallout in Norwegian milk in 1960
Brandon et al. Intercomparison of the D sub (2) O-moderated super (252) Cf sources at the N. B. S. and at the SEFOR calibration center.