FR2019325A1 - Manufacturing nuclear fuel from sintered uranium - dioxide - Google Patents

Manufacturing nuclear fuel from sintered uranium - dioxide

Info

Publication number
FR2019325A1
FR2019325A1 FR6926904A FR6926904A FR2019325A1 FR 2019325 A1 FR2019325 A1 FR 2019325A1 FR 6926904 A FR6926904 A FR 6926904A FR 6926904 A FR6926904 A FR 6926904A FR 2019325 A1 FR2019325 A1 FR 2019325A1
Authority
FR
France
Prior art keywords
nuclear fuel
dioxide
uranium
prior
sintered product
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.)
Granted
Application number
FR6926904A
Other languages
French (fr)
Other versions
FR2019325B1 (en
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.)
General Electric Co
Original Assignee
General Electric Co
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 General Electric Co filed Critical General Electric Co
Publication of FR2019325A1 publication Critical patent/FR2019325A1/en
Application granted granted Critical
Publication of FR2019325B1 publication Critical patent/FR2019325B1/fr
Granted legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/42Selection of substances for use as reactor fuel
    • G21C3/58Solid reactor fuel Pellets made of fissile material
    • G21C3/62Ceramic fuel
    • G21C3/623Oxide fuels
    • 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

  • 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)
  • Furnace Details (AREA)

Abstract

Nuclear fuel is produced by pressing UO2 powder to green bodies and then sintering them at a temp. below approx. 1500 degrees C. to the desired density, while the oxygen-uranium ratio of the bodies is maintained at least approx. 2.005. A uranium dioxide sintered product is manufactured in an oven at a relatively low temp. and without the necessity of an additional combustion step which is required with prior art sintering processes with vapour atmosphere. This results in the drawbacks of prior art process being avoided. The uranium dioxide sintered product complies with the requirements for nuclear reactors.
FR6926904A 1968-08-05 1969-08-05 Manufacturing nuclear fuel from sintered uranium - dioxide Granted FR2019325A1 (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US74999468A 1968-08-05 1968-08-05

Publications (2)

Publication Number Publication Date
FR2019325A1 true FR2019325A1 (en) 1970-07-03
FR2019325B1 FR2019325B1 (en) 1973-11-16

Family

ID=25016083

Family Applications (1)

Application Number Title Priority Date Filing Date
FR6926904A Granted FR2019325A1 (en) 1968-08-05 1969-08-05 Manufacturing nuclear fuel from sintered uranium - dioxide

Country Status (3)

Country Link
JP (1) JPS5434880B1 (en)
DE (1) DE1939610A1 (en)
FR (1) FR2019325A1 (en)

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE3142447C1 (en) * 1981-10-26 1983-04-14 Kraftwerk Union AG, 4330 Mülheim Process for the production of oxidic nuclear fuel sintered bodies
SE447610B (en) * 1985-04-02 1986-11-24 Asea Atom Ab SET TO MANUFACTURE SINTERED NUCLEAR FUEL BODIES

Also Published As

Publication number Publication date
JPS5434880B1 (en) 1979-10-30
FR2019325B1 (en) 1973-11-16
DE1939610A1 (en) 1970-02-19

Similar Documents

Publication Publication Date Title
US3087877A (en) Method of making fuel bodies
ES419677A1 (en) Process for controlling end-point density of sintered uranium dioxide nuclear fuel bodies and product
FR2060242A1 (en) Sinterable uranium oxides from uraniumhexafluoride
ES8207648A1 (en) Process for preparing high-density oxidic nuclear-fuel bodies.
FR2019325A1 (en) Manufacturing nuclear fuel from sintered uranium - dioxide
GB1208433A (en) Manufacture of ceramic artefacts having pores
US3342562A (en) High density urania fuel elements
GB1424389A (en) Process for the production of fuel inserts fuel elements and absorber elements for high-temperature nuclear reactors
US3168601A (en) Process for the production of plutonium oxide-containing nuclear fuel compacts
ES286348A1 (en) Method of manufacture of a sinterized body of ferrous ferrous manganese cinc (Machine-translation by Google Translate, not legally binding)
US3168479A (en) Process for producing high density nuclear fuel particles
GB832317A (en) Process for the production of fine-pore metal filters, membranes and diaphragms
GB1128742A (en) Nuclear fuel element and method of fabricating of said element
US3168371A (en) Process for producing high density urania fuel elements
ES299210A1 (en) Method of preparation of nuclear combustible elements (Machine-translation by Google Translate, not legally binding)
US3761546A (en) Method of making uranium dioxide bodies
US3230278A (en) Method of manufacture of uranium dioxide having a high density
US3404201A (en) Method of making sintered nuclear fuel pellets, in particular consisting of uranium dioxide
US3766082A (en) Sintering of compacts of un,(u,pu)n, and pun
GB1420630A (en) Production of nuclear fuel
US3291869A (en) Nuclear fuel
GB1182080A (en) Nuclear Fuel
FR2318837A1 (en) Sintering of nuclear fuel oxides - using ammonium oxalate as a pore former
US3327027A (en) Process for the production of plutonium oxide-containing nuclear fuel powders
ES410552A1 (en) Production of porous ceramic nuclear fuel employing dextrin as a volatile pore former

Legal Events

Date Code Title Description
ST Notification of lapse