GB869451A - Fuel composition for aqueous homogeneous nuclear reactors - Google Patents
Fuel composition for aqueous homogeneous nuclear reactorsInfo
- Publication number
- GB869451A GB869451A GB35450/59A GB3545059A GB869451A GB 869451 A GB869451 A GB 869451A GB 35450/59 A GB35450/59 A GB 35450/59A GB 3545059 A GB3545059 A GB 3545059A GB 869451 A GB869451 A GB 869451A
- Authority
- GB
- United Kingdom
- Prior art keywords
- nuclear reactors
- aqueous homogeneous
- fertile
- fuel composition
- oct
- 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
- 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
- G21C3/44—Fluid or fluent reactor fuel
- G21C3/46—Aqueous compositions
-
- 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
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Solid-Sorbent Or Filter-Aiding Compositions (AREA)
- Treatment Of Liquids With Adsorbents In General (AREA)
Abstract
869,451. Nuclear reactors. ALLMANNA SVENSKA ELECTRISKA A. B. Oct. 20, 1959 [Oct. 25, 1958], No. 35450/59. Class 39(4). In an aqueous homogeneous reactor adsorption of dissolved fissile material on suspended fertile material is prevented by salts of Al, Be or Mg in solution. The fuel is preferably uranyl sulphate with 90% U<SP>235</SP> or U<SP>233</SP> enrichment dissolved with D 2 SO 4 in D 2 O, and the fertile material is Th or U oxides as suspended particles. Salts of Cu or Fe, or Mo trioxide, are added to catalytically decompose D 3 O 2 and to recombine D 2 and O 2 . The reactor may have two zones, for fission and for breeding, separated by cyclone action or by a wall which is not fluid-tight, and a system for separating fissile and fertile materials. The fission zone contains 0.5-50 gm/litre of U, 0.1-10 gm/l. of D 2 SO 4 , 0.1-10 gm/l. of catalysts, and 0.01-50 gm/l. of Be, A1 or Mg as sulphate, nitrate or fluoride; the breeding zone contains 20- 2000 gm/l. of Th or U and 0.1-100 gm/l. of Be, Al or Mg ions.
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
SE869451X | 1958-10-25 |
Publications (1)
Publication Number | Publication Date |
---|---|
GB869451A true GB869451A (en) | 1961-05-31 |
Family
ID=20367059
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB35450/59A Expired GB869451A (en) | 1958-10-25 | 1959-10-20 | Fuel composition for aqueous homogeneous nuclear reactors |
Country Status (3)
Country | Link |
---|---|
DE (1) | DE1099097B (en) |
FR (1) | FR1244546A (en) |
GB (1) | GB869451A (en) |
Cited By (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US11361873B2 (en) * | 2012-04-05 | 2022-06-14 | Shine Technologies, Llc | Aqueous assembly and control method |
US11830637B2 (en) | 2008-05-02 | 2023-11-28 | Shine Technologies, Llc | Device and method for producing medical isotopes |
US11894157B2 (en) | 2010-01-28 | 2024-02-06 | Shine Technologies, Llc | Segmented reaction chamber for radioisotope production |
-
1959
- 1959-10-20 GB GB35450/59A patent/GB869451A/en not_active Expired
- 1959-10-22 DE DEA33092A patent/DE1099097B/en active Pending
- 1959-10-23 FR FR808295A patent/FR1244546A/en not_active Expired
Cited By (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US11830637B2 (en) | 2008-05-02 | 2023-11-28 | Shine Technologies, Llc | Device and method for producing medical isotopes |
US11894157B2 (en) | 2010-01-28 | 2024-02-06 | Shine Technologies, Llc | Segmented reaction chamber for radioisotope production |
US11361873B2 (en) * | 2012-04-05 | 2022-06-14 | Shine Technologies, Llc | Aqueous assembly and control method |
Also Published As
Publication number | Publication date |
---|---|
DE1099097B (en) | 1961-02-09 |
FR1244546A (en) | 1960-10-28 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
FR1214246A (en) | New binding mode of the solid moderator of a vertical channel atomic reactor with a centered hexagonal lattice | |
GB1430542A (en) | Recovery and separation of technetium palladium rhodium and ruthenium | |
GB1187244A (en) | Improvements in and relating to Nuclear Reactor Fuel Material | |
GB931286A (en) | Improvements in or relating to nuclear reactors | |
GB869451A (en) | Fuel composition for aqueous homogeneous nuclear reactors | |
SE8205802L (en) | PROCEDURE TO INCREASE THE GRAIN SIZE OF URANOXIDE | |
GB1436465A (en) | Methods of operating at least two nuclear reactors | |
GB901330A (en) | Process for effecting a self-sustaining nuclear fission reaction | |
US3023085A (en) | Method of combining hydrogen and oxygen | |
ES306340A1 (en) | Method of separation of uranium from plutonium | |
GB1079427A (en) | Improvements in nuclear reactors | |
GB1193596A (en) | Ion Exchange Process for Recovering Americium and Curium. | |
GB1187243A (en) | Improvements in the preparation of Nuclear Reactor Fuel materials | |
GB889702A (en) | A control and shut-down device for a nuclear reactor | |
GB855859A (en) | Improvements relating to nuclear reactors | |
GB753399A (en) | Process of nuclear fission | |
GB959574A (en) | Improvements in or relating to ion exchangers | |
GB1021413A (en) | Pyrolytic carbon decladding of nuclear fuel | |
GB1164980A (en) | Process for Depleting <283>PuO2 in <17>O and <18>O. | |
GB1473407A (en) | Process for separating plutonium and/or neptunion from aqueous solution | |
GB801288A (en) | Fuel for nuclear reactors and process of making the same | |
GB1039211A (en) | Removal of stainless steel claddings from nuclear fuel elements | |
GB826529A (en) | Improvements relating to neutronic reaction fuels | |
GB1487013A (en) | Calcination process | |
GB903142A (en) | A nuclear reactor |