GB962428A - Improvements in or relating to methods of manufacturing elements of fissile or breeding substances for use in nuclear reactors - Google Patents
Improvements in or relating to methods of manufacturing elements of fissile or breeding substances for use in nuclear reactorsInfo
- Publication number
- GB962428A GB962428A GB32116/60A GB3211660A GB962428A GB 962428 A GB962428 A GB 962428A GB 32116/60 A GB32116/60 A GB 32116/60A GB 3211660 A GB3211660 A GB 3211660A GB 962428 A GB962428 A GB 962428A
- Authority
- GB
- United Kingdom
- Prior art keywords
- fissile
- fertile
- relating
- methods
- sept
- 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
Links
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C21/00—Apparatus or processes specially adapted to the manufacture of reactors or parts thereof
- G21C21/02—Manufacture of fuel elements or breeder elements contained in non-active casings
-
- 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
-
- 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)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Chemical & Material Sciences (AREA)
- Ceramic Engineering (AREA)
- Manufacturing & Machinery (AREA)
- Inorganic Compounds Of Heavy Metals (AREA)
- Dental Preparations (AREA)
Abstract
962,428. Nuclear fueL STITCHING REACTOR CENTRUM NEDERLAND. Sept. 19, 1960 [Sept. 18, 1959], No. 32116/60. Heading G6C. A fissile or fertile nuclear fuel element is made by mixing a fissile or fertile substance with a gel of a fluoride of beryllium, magnesium, calcium, strontium, or barium, moulding the mixture under pressure, and drying at 50‹-400‹C. The fissile or fertile material may be U<SP>233</SP>, U<SP>235</SP>, Pu<SP>239</SP>, Th<SP>232</SP>, or U<SP>238</SP> in metallic form or as oxides, nitrides, carbides, or silicides. The gel may be prepared by grinding a mixture of the fluoride, water, and a volatile salt (ammonium nitrate or chloride) or a decomposable salt (uranium or thorium nitrate). In examples, gels of MgF 2 , CaF 2 , and BeF 2 are mixed with uranium dioxide powder, which may contain plutonium dioxide, and pressed into pellets; after drying the pellets may be heated at 500‹-1200‹C. in vacuo, or in hydrogen or nitrogen.
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
NL243513 | 1959-09-18 |
Publications (1)
Publication Number | Publication Date |
---|---|
GB962428A true GB962428A (en) | 1964-07-01 |
Family
ID=19751932
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB32116/60A Expired GB962428A (en) | 1959-09-18 | 1960-09-19 | Improvements in or relating to methods of manufacturing elements of fissile or breeding substances for use in nuclear reactors |
Country Status (5)
Country | Link |
---|---|
BE (1) | BE595132A (en) |
DE (1) | DE1124611B (en) |
GB (1) | GB962428A (en) |
LU (1) | LU39194A1 (en) |
NL (1) | NL243513A (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
GB2527140A (en) * | 2014-06-15 | 2015-12-16 | Ian Richard Scott | Improved fuel salt chemistry and fission rate control in a molten salt nuclear reactor |
-
0
- NL NL243513D patent/NL243513A/xx unknown
- BE BE595132D patent/BE595132A/xx unknown
-
1960
- 1960-09-17 DE DEST16915A patent/DE1124611B/en active Pending
- 1960-09-19 GB GB32116/60A patent/GB962428A/en not_active Expired
- 1960-09-19 LU LU39194D patent/LU39194A1/xx unknown
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
GB2527140A (en) * | 2014-06-15 | 2015-12-16 | Ian Richard Scott | Improved fuel salt chemistry and fission rate control in a molten salt nuclear reactor |
Also Published As
Publication number | Publication date |
---|---|
LU39194A1 (en) | 1960-11-24 |
NL243513A (en) | |
BE595132A (en) | |
DE1124611B (en) | 1962-03-01 |
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