FR2318837A1 - Sintering of nuclear fuel oxides - using ammonium oxalate as a pore former - Google Patents

Sintering of nuclear fuel oxides - using ammonium oxalate as a pore former

Info

Publication number
FR2318837A1
FR2318837A1 FR7622478A FR7622478A FR2318837A1 FR 2318837 A1 FR2318837 A1 FR 2318837A1 FR 7622478 A FR7622478 A FR 7622478A FR 7622478 A FR7622478 A FR 7622478A FR 2318837 A1 FR2318837 A1 FR 2318837A1
Authority
FR
France
Prior art keywords
mixt
nuclear fuel
ammonium oxalate
sintering
pore former
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Withdrawn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
FR7622478A
Other languages
French (fr)
Inventor
Henry Clay Brassfield
William Roger Dehollander
Yogesh Nivas
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 FR2318837A1 publication Critical patent/FR2318837A1/en
Withdrawn legal-status Critical Current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
    • G21C3/623—Oxide fuels
    • C—CHEMISTRY; METALLURGY
    • C04—CEMENTS; CONCRETE; ARTIFICIAL STONE; CERAMICS; REFRACTORIES
    • C04B—LIME, MAGNESIA; SLAG; CEMENTS; COMPOSITIONS THEREOF, e.g. MORTARS, CONCRETE OR LIKE BUILDING MATERIALS; ARTIFICIAL STONE; CERAMICS; REFRACTORIES; TREATMENT OF NATURAL STONE
    • C04B38/00—Porous mortars, concrete, artificial stone or ceramic ware; Preparation thereof
    • C04B38/02—Porous mortars, concrete, artificial stone or ceramic ware; Preparation thereof by adding chemical blowing agents
    • 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

Abstract

Method of preparing a piece of nuclear fuel for a nuclear reactor comprises preparing a mixt. contg. the nuclear fuel and ammonium oxalate, the latter being in the form of aggregates of at least 10 pref. 30-60 mu dia., and being present to an amount of 0.1-33.0 wt.% of the mixt., moulding the mixt. into a green body of 30-70% theoretical density, heating to decompose the oxalate and further heating to suiter the body to form discontinuous porosity, the final density of the body being 90-96% theoretical. The process is esp. applicable to a nuclear fuel comprising uranium dioxide, a mixt. of UO2 and PuO2 or a mixt. of UO2 and Gd2O3. The density of the oxide is controlled so as not to reach the maximum possible, without the need for careful control of the sintering conditions so as to produce undersintering.
FR7622478A 1975-07-24 1976-07-23 Sintering of nuclear fuel oxides - using ammonium oxalate as a pore former Withdrawn FR2318837A1 (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US59883975A 1975-07-24 1975-07-24

Publications (1)

Publication Number Publication Date
FR2318837A1 true FR2318837A1 (en) 1977-02-18

Family

ID=24397127

Family Applications (1)

Application Number Title Priority Date Filing Date
FR7622478A Withdrawn FR2318837A1 (en) 1975-07-24 1976-07-23 Sintering of nuclear fuel oxides - using ammonium oxalate as a pore former

Country Status (8)

Country Link
JP (1) JPS5221598A (en)
BE (1) BE844494A (en)
CA (1) CA1083336A (en)
DE (1) DE2631757A1 (en)
ES (1) ES450106A1 (en)
FR (1) FR2318837A1 (en)
IL (1) IL49613A0 (en)
SE (1) SE7608416L (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2474021A1 (en) * 1980-01-21 1981-07-24 Gen Electric PROCESS FOR MANUFACTURING NUCLEAR FUEL PELLETS AND PELLETS OBTAINED
EP0377077A1 (en) * 1988-12-27 1990-07-11 Mitsubishi Materials Corporation UO2 pellet fabrication process
EP0635846A1 (en) * 1993-07-23 1995-01-25 Doryokuro Kakunenryo Kaihatsu Jigyodan Method for manufacturing nuclear fuel pellet

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE2833054C2 (en) * 1978-07-27 1982-07-01 Alkem Gmbh, 6450 Hanau Process for the production of PuO ↓ 2 ↓ / UO ↓ 2 ↓ nuclear fuel
US9721679B2 (en) 2008-04-08 2017-08-01 Terrapower, Llc Nuclear fission reactor fuel assembly adapted to permit expansion of the nuclear fuel contained therein

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2474021A1 (en) * 1980-01-21 1981-07-24 Gen Electric PROCESS FOR MANUFACTURING NUCLEAR FUEL PELLETS AND PELLETS OBTAINED
EP0377077A1 (en) * 1988-12-27 1990-07-11 Mitsubishi Materials Corporation UO2 pellet fabrication process
EP0635846A1 (en) * 1993-07-23 1995-01-25 Doryokuro Kakunenryo Kaihatsu Jigyodan Method for manufacturing nuclear fuel pellet

Also Published As

Publication number Publication date
CA1083336A (en) 1980-08-12
JPS5221598A (en) 1977-02-18
BE844494A (en) 1976-11-16
DE2631757A1 (en) 1977-02-10
SE7608416L (en) 1977-01-25
IL49613A0 (en) 1976-07-30
ES450106A1 (en) 1977-12-01

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Legal Events

Date Code Title Description
ST Notification of lapse