GB788284A - Improvements in or relating to nuclear reactors - Google Patents

Improvements in or relating to nuclear reactors

Info

Publication number
GB788284A
GB788284A GB21932/56A GB2193256A GB788284A GB 788284 A GB788284 A GB 788284A GB 21932/56 A GB21932/56 A GB 21932/56A GB 2193256 A GB2193256 A GB 2193256A GB 788284 A GB788284 A GB 788284A
Authority
GB
United Kingdom
Prior art keywords
oxalate
fissile
heat distributing
sintered
adhesive
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
GB21932/56A
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.)
STICHTING REACTOR CENTRUM
Original Assignee
STICHTING REACTOR CENTRUM
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 STICHTING REACTOR CENTRUM filed Critical STICHTING REACTOR CENTRUM
Publication of GB788284A publication Critical patent/GB788284A/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
    • G21C3/04—Constructional details
    • G21C3/044—Fuel elements with porous or capillary structure
    • 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
    • G21C3/42—Selection of substances for use as reactor fuel
    • G21C3/58—Solid reactor fuel Pellets made of fissile material
    • G21C3/62—Ceramic fuel
    • G21C3/64—Ceramic dispersion fuel, e.g. cermet
    • 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

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Chemical & Material Sciences (AREA)
  • Ceramic Engineering (AREA)
  • Dispersion Chemistry (AREA)
  • Physical Or Chemical Processes And Apparatus (AREA)
  • Particle Accelerators (AREA)

Abstract

788,284. Nuclear reactors. STICHTING REACTOR CENTRUM NEDERLAND. July 16, 1956 [July 18, 1955], No. 21932/56. Class 39(4). In a reactor, the fuel and a heat distributing material, which may be a moderator, are sintered or heated together with an adhesive to form a porous material, which may be formed into granules, Berl saddles, Rashig rings, hollow spheres, blocks, plates, rods or tubes. The cooling fluid may be a gas, oxygen, carbon monoxide, helium, hydrogen or deuterium; a liquid sodium hydroxide or bismuth; or a dispersion of liquid in gas such as heavy water in water vapour. The fuel may be uranium 235, uranium 233 or plutonium, while heat distributing moderating material may be beryllium oxide, beryllium carbide or carbon. Thorium oxalate may be added as a treating material and the concentration of fissile material may decrease from the surface to the inside. Where the heat distributing material is not a moderator it may consist of compounds of bismuth, magnesium, lead, phosphorus, silicon, zirconium, and aluminium and the moderating material may be arranged separately in the form of blocks or plates. A fine control of the reactor may be effected by regulating the pressure of the cooling fluid where the latter has moderating properties. The sintering process may take place under pressure, but for small bodies, an aggregate of heat distributing material is formed by mixing with an adhesive and applying pressure. This is then soaked in a solution of the fissile material for example uranium oxalate and heated, to decompose the oxalate, and then sintered without pressure. The formation of the entectic mixture is facilitated by the addition of bervllium oxalate to the fissile solution. Alternatively, aggregate of carbon particles with an adhesive are formed, soaked in fissile solution, heated in vacuo or in carbon monoxide and then sintered.
GB21932/56A 1955-07-18 1956-07-16 Improvements in or relating to nuclear reactors Expired GB788284A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
NL788284X 1955-07-18

Publications (1)

Publication Number Publication Date
GB788284A true GB788284A (en) 1957-12-23

Family

ID=19832334

Family Applications (1)

Application Number Title Priority Date Filing Date
GB21932/56A Expired GB788284A (en) 1955-07-18 1956-07-16 Improvements in or relating to nuclear reactors

Country Status (4)

Country Link
BE (2) BE549567A (en)
DE (1) DE1033810B (en)
FR (1) FR1156379A (en)
GB (1) GB788284A (en)

Cited By (9)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2984613A (en) * 1959-04-09 1961-05-16 Charles H Bassett Fuel element for nuclear reactors
DE1117786B (en) * 1959-02-10 1961-11-23 Hartwig Benzler Dr Ing Nuclear reactor whose core contains little or no moderator
US3028330A (en) * 1959-04-07 1962-04-03 Rnb Corp Nuclear fuel elements having an autogenous matrix and method of making the same
US3047487A (en) * 1958-12-15 1962-07-31 Dow Chemical Co Solid fuel and heating element for gas-cooled nuclear reactors
US3102848A (en) * 1959-11-23 1963-09-03 Curtiss Wright Corp Nuclear fuel compositions and method of making the same
US3129141A (en) * 1958-11-03 1964-04-14 Gen Motors Corp Nuclear reactor fuel element and process for making same
US3166614A (en) * 1959-11-30 1965-01-19 Carborundum Co Process of making nuclear fuel element
US3205174A (en) * 1958-05-30 1965-09-07 Atomic Energy Authority Uk Nuclear fuel materials including vitreous phase
US3238108A (en) * 1959-04-17 1966-03-01 Babcock & Wilcox Co Bundle-type nuclear fuel element having novel arrangement of fissionable and fertile material

Families Citing this family (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1182362B (en) * 1958-07-12 1964-11-26 Siemens Ag Fuel element for preferably gas or metal-cooled nuclear reactors
US3087877A (en) * 1958-12-31 1963-04-30 Walter V Goeddel Method of making fuel bodies
BE586884A (en) * 1959-01-27
NL126623C (en) * 1960-10-28
DE1276230B (en) * 1960-12-19 1968-08-29 Kernkraftwerksbau Veb Device for controlling nuclear reactors
NL269759A (en) * 1961-03-04
DE1238122B (en) * 1963-12-18 1967-04-06 Atomic Energy Authority Uk Nuclear reactor
FR2989815A1 (en) * 2012-04-18 2013-10-25 Commissariat Energie Atomique Method for preparing porous fuel, involves performing heat treatment of mixture comprising oxide precursor blowing agent, which is complex coordination comprising of uranium, plutonium and/or minor actinide

Cited By (9)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3205174A (en) * 1958-05-30 1965-09-07 Atomic Energy Authority Uk Nuclear fuel materials including vitreous phase
US3129141A (en) * 1958-11-03 1964-04-14 Gen Motors Corp Nuclear reactor fuel element and process for making same
US3047487A (en) * 1958-12-15 1962-07-31 Dow Chemical Co Solid fuel and heating element for gas-cooled nuclear reactors
DE1117786B (en) * 1959-02-10 1961-11-23 Hartwig Benzler Dr Ing Nuclear reactor whose core contains little or no moderator
US3028330A (en) * 1959-04-07 1962-04-03 Rnb Corp Nuclear fuel elements having an autogenous matrix and method of making the same
US2984613A (en) * 1959-04-09 1961-05-16 Charles H Bassett Fuel element for nuclear reactors
US3238108A (en) * 1959-04-17 1966-03-01 Babcock & Wilcox Co Bundle-type nuclear fuel element having novel arrangement of fissionable and fertile material
US3102848A (en) * 1959-11-23 1963-09-03 Curtiss Wright Corp Nuclear fuel compositions and method of making the same
US3166614A (en) * 1959-11-30 1965-01-19 Carborundum Co Process of making nuclear fuel element

Also Published As

Publication number Publication date
BE549567A (en)
FR1156379A (en) 1958-05-14
DE1033810B (en) 1958-07-10
BE549566A (en)

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