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 formerInfo
- 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- Withdrawn
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
Landscapes
- Engineering & Computer Science (AREA)
- Chemical & Material Sciences (AREA)
- Ceramic Engineering (AREA)
- Physics & Mathematics (AREA)
- High Energy & Nuclear Physics (AREA)
- General Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- Chemical Kinetics & Catalysis (AREA)
- General Chemical & Material Sciences (AREA)
- Materials Engineering (AREA)
- Structural Engineering (AREA)
- Organic Chemistry (AREA)
- Inorganic Compounds Of Heavy Metals (AREA)
- Powder Metallurgy (AREA)
- Porous Artificial Stone Or Porous Ceramic Products (AREA)
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.
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)
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)
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 |
-
1976
- 1976-05-20 IL IL49613A patent/IL49613A0/en unknown
- 1976-07-15 DE DE19762631757 patent/DE2631757A1/en active Pending
- 1976-07-23 CA CA257,625A patent/CA1083336A/en not_active Expired
- 1976-07-23 FR FR7622478A patent/FR2318837A1/en not_active Withdrawn
- 1976-07-23 SE SE7608416A patent/SE7608416L/en unknown
- 1976-07-23 JP JP51087367A patent/JPS5221598A/en active Pending
- 1976-07-23 ES ES450106A patent/ES450106A1/en not_active Expired
- 1976-07-23 BE BE169218A patent/BE844494A/en unknown
Cited By (3)
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 |
ES450106A1 (en) | 1977-12-01 |
BE844494A (en) | 1976-11-16 |
DE2631757A1 (en) | 1977-02-10 |
SE7608416L (en) | 1977-01-25 |
IL49613A0 (en) | 1976-07-30 |
JPS5221598A (en) | 1977-02-18 |
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Legal Events
Date | Code | Title | Description |
---|---|---|---|
ST | Notification of lapse |