GB1370689A - Nuclear fuel - Google Patents

Nuclear fuel

Info

Publication number
GB1370689A
GB1370689A GB4503971A GB4503971A GB1370689A GB 1370689 A GB1370689 A GB 1370689A GB 4503971 A GB4503971 A GB 4503971A GB 4503971 A GB4503971 A GB 4503971A GB 1370689 A GB1370689 A GB 1370689A
Authority
GB
United Kingdom
Prior art keywords
nitride
nuclear fuel
carbide
fuel
uranium
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
GB4503971A
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.)
Nukem GmbH
Original Assignee
Nukem GmbH
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 Nukem GmbH filed Critical Nukem GmbH
Publication of GB1370689A publication Critical patent/GB1370689A/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
    • G21C3/42—Selection of substances for use as reactor fuel
    • G21C3/58—Solid reactor fuel Pellets made of fissile material
    • G21C3/62—Ceramic 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

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • Chemical & Material Sciences (AREA)
  • Ceramic Engineering (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Inorganic Compounds Of Heavy Metals (AREA)

Abstract

1370689 Nuclear fuel NUKEM GmbH 28 Sept 1971 [9 Oct 1970] 45039/71 Heading G6C Nuclear fuel based on uranium-plutonium monocarbide or mononitride is prepared by mixing pure uranium carbide or nitride powder with plutonium oxide and carbon, compressing the mixture and sintering, for example at 1600- 1700‹ C., in vacuum or in argon to form the carbide, or in nitrogen to form the nitride. The plutonium oxide and carbon may be pre-reacted before mixing with the other component. The uranium carbide or nitride may be used in granulated form and may be inactivated by coating with stearic acid. Grains of the fuel may be stabilized against water and oxygen by nitriding, sulphiding, or phosphiding. In one example, excess metal becomes concentrated at the surface of the fuel particles and is converted to a layer of nitride by heating in nitrogen. Specification 1,370,690 is referred to.
GB4503971A 1970-10-09 1971-09-28 Nuclear fuel Expired GB1370689A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
DE2049566A DE2049566C3 (en) 1970-10-09 1970-10-09 Process for the production of a nuclear fuel from uranium-plutonium-monocarbide or uranium-plutonium-mononitride

Publications (1)

Publication Number Publication Date
GB1370689A true GB1370689A (en) 1974-10-16

Family

ID=5784589

Family Applications (1)

Application Number Title Priority Date Filing Date
GB4503971A Expired GB1370689A (en) 1970-10-09 1971-09-28 Nuclear fuel

Country Status (4)

Country Link
BE (1) BE773730A (en)
DE (1) DE2049566C3 (en)
FR (1) FR2112276B1 (en)
GB (1) GB1370689A (en)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE2616632C3 (en) * 1976-04-15 1979-02-08 Gesellschaft Fuer Kernforschung Mbh, 7500 Karlsruhe Process for reducing plutonium losses in uranium-plutonium mixed carbide production

Also Published As

Publication number Publication date
DE2049566C3 (en) 1978-05-03
DE2049566B2 (en) 1977-09-08
FR2112276B1 (en) 1975-07-11
BE773730A (en) 1972-01-31
DE2049566A1 (en) 1972-04-13
FR2112276A1 (en) 1972-06-16

Similar Documents

Publication Publication Date Title
US3953556A (en) Method of preparing uranium nitride or uranium carbonitride bodies
ES419677A1 (en) Process for controlling end-point density of sintered uranium dioxide nuclear fuel bodies and product
GB1285190A (en) Improvements in ceramic fissile materials
GB1370690A (en) Nuclear fuel
GB1370689A (en) Nuclear fuel
GB1034505A (en) Improvements in or relating to sintered uranium-plutonium compounds
GB1053786A (en)
GB1188011A (en) Production of Nitrides of Actinide Metals.
ES336340A1 (en) Nuclear fuel element
GB1471811A (en) Nuclear fuel pellets
GB1352972A (en) Ceramic sintering process
GB1116663A (en) Sintered uranium dioxide
GB1274112A (en) Improvements in or relating to the production of refractory material
GB1334391A (en) Nuclear fuels
US3044946A (en) High density nuclear fuel composition
GB949727A (en) Improvements in or relating to nuclear fuel
GB1420630A (en) Production of nuclear fuel
GB934254A (en) Production of high density sintered uranium oxide
GB817918A (en) Improvements in or relating to methods of manufacturing radiation-sensitive sinteredbodies containing cadmium sulphide
GB1371595A (en) Manufacturing process for mixed nuclear fuel pellets
GB1256283A (en) Improvements in the preparation of sintered uranium dioxide grains
GB1024765A (en) Improvements in or relating to the production of fuel elements for nuclear reactors
GB1241976A (en) Process for preparing sintered pellets of ceramic materials to be used as nuclear fuels and products obtained by the process
GB1271924A (en) Process for producing full density urania particles
GB1371699A (en) Fission product retaining nuclear reactor fuel

Legal Events

Date Code Title Description
PS Patent sealed
PCNP Patent ceased through non-payment of renewal fee