CH496500A - Procédé de fabrication de pièces frittées en oxyde d'uranium ou d'élément transuranien - Google Patents
Procédé de fabrication de pièces frittées en oxyde d'uranium ou d'élément transuranienInfo
- Publication number
- CH496500A CH496500A CH1161068A CH1161068A CH496500A CH 496500 A CH496500 A CH 496500A CH 1161068 A CH1161068 A CH 1161068A CH 1161068 A CH1161068 A CH 1161068A CH 496500 A CH496500 A CH 496500A
- Authority
- CH
- Switzerland
- Prior art keywords
- sintering
- uranium
- parts
- naphthalene
- transuranien
- Prior art date
Links
Classifications
-
- B—PERFORMING OPERATIONS; TRANSPORTING
- B65—CONVEYING; PACKING; STORING; HANDLING THIN OR FILAMENTARY MATERIAL
- B65G—TRANSPORT OR STORAGE DEVICES, e.g. CONVEYORS FOR LOADING OR TIPPING, SHOP CONVEYOR SYSTEMS OR PNEUMATIC TUBE CONVEYORS
- B65G69/00—Auxiliary measures taken, or devices used, in connection with loading or unloading
- B65G69/20—Auxiliary treatments, e.g. aerating, heating, humidifying, deaerating, cooling, de-watering or drying, during loading or unloading; Loading or unloading in a fluid medium other than air
-
- 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
-
- 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)
- Mechanical Engineering (AREA)
- Inorganic Compounds Of Heavy Metals (AREA)
- Glass Compositions (AREA)
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| FR116667 | 1967-08-02 |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CH496500A true CH496500A (de) | 1970-09-30 |
Family
ID=8636295
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CH1161068A CH496500A (de) | 1967-08-02 | 1968-08-02 | Procédé de fabrication de pièces frittées en oxyde d'uranium ou d'élément transuranien |
Country Status (5)
| Country | Link |
|---|---|
| BE (1) | BE718476A (cs) |
| CH (1) | CH496500A (cs) |
| ES (1) | ES356814A1 (cs) |
| FR (1) | FR1550150A (cs) |
| LU (1) | LU56563A1 (cs) |
-
1967
- 1967-08-02 FR FR116667A patent/FR1550150A/fr not_active Expired
-
1968
- 1968-07-23 LU LU56563D patent/LU56563A1/xx unknown
- 1968-07-24 BE BE718476D patent/BE718476A/xx unknown
- 1968-08-02 CH CH1161068A patent/CH496500A/fr not_active IP Right Cessation
- 1968-08-02 ES ES356814A patent/ES356814A1/es not_active Expired
Also Published As
| Publication number | Publication date |
|---|---|
| ES356814A1 (es) | 1970-02-16 |
| BE718476A (cs) | 1968-12-31 |
| LU56563A1 (cs) | 1968-10-30 |
| FR1550150A (cs) | 1968-12-20 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| JP3106113B2 (ja) | 酸化物核燃料のペレットスクラップのリサイクル方法 | |
| Radford et al. | UO2 fuel pellet microstructure modification through impurity additions | |
| EP2474000A1 (fr) | Procede de preparation d'un combustible nucleaire poreux a base d'au moins un actinide mineur | |
| JP2020534530A (ja) | 軽水炉および鉛高速炉向け高温セラミック原子燃料システム | |
| EP0432065B1 (fr) | Procédé d'obtention de pastilles combustibles d'UO2 à partir d'U métal, sans production d'effluent | |
| US3306957A (en) | Production of nuclear fuel materials | |
| FR2555566A1 (fr) | Procede de preparation d'oxydes metalliques pulverulents a partir de solutions aqueuses ou de melanges solides de nitrates metalliques | |
| FR2706066A1 (fr) | Combustible nucléaire ayant des propriétés améliorées de rétention des produits de fission. | |
| FR2573094A1 (fr) | Alliage de molybdene et son procede de fabrication | |
| FR2969661A1 (fr) | Poudre d'un alliage a base d'uranium et de molybdene utile pour la fabrication de combustibles nucleaires | |
| FR3030500A1 (fr) | Procede de fabrication d'une pastille d'au moins un oxyde metallique, son utilisation comme combustible nucleaire | |
| CH496500A (de) | Procédé de fabrication de pièces frittées en oxyde d'uranium ou d'élément transuranien | |
| KR20180027390A (ko) | 이중결정립 조직을 갖는 핵연료 소결체의 제조방법 | |
| US20130223582A1 (en) | Fabrication method of burnable absorber nuclear fuel pellets and burnable absorber nuclear fuel pellets fabricated by the same | |
| EP2991932B1 (fr) | Nouveau materiau a base d'uranium, de gadolinium et d'oxygene et son utilisation comme poison neutronique consommable | |
| JPH0774833B2 (ja) | 二酸化ウラン焼結体の製造方法及び核燃料体 | |
| EP1071830B1 (fr) | Alliage de zirconium et de niobium comprenant de l'erbium, procede de preparation et piece comprenant ledit alliage | |
| US3409504A (en) | Nuclear fuel element | |
| US20220084700A1 (en) | Control method for volume fraction of multistructural isotropic fuel particles in fully ceramic microencapsulated nuclear fuels, compositions for coating and sintered body of the same | |
| RU2701542C1 (ru) | Способ изготовления таблетированного топлива для тепловыделяющих элементов ядерных реакторов | |
| RU2690492C1 (ru) | Способ получения таблетированного пористого диоксида урана | |
| CN115058268B (zh) | 复合结构燃料及其制备方法 | |
| JP4614540B2 (ja) | 酸化物基材の核燃料要素の製造方法および酸化物基材の核燃料要素に焼結されるように適合された物質 | |
| CN113683422B (zh) | 一种大晶粒uo2陶瓷燃料及其制备方法和应用 | |
| FR2998288A1 (fr) | Procede de preparation d'une composition a base d'au moins un oxyde comprenant de l'uranium autre que u3o8 et utilisation de cette composition pour la fabrication d'un combustible nucleaire dense |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PL | Patent ceased |