GB991424A - Improvements in or relating to fuel elements for nuclear reactors - Google Patents
Improvements in or relating to fuel elements for nuclear reactorsInfo
- Publication number
- GB991424A GB991424A GB20926/62A GB2092662A GB991424A GB 991424 A GB991424 A GB 991424A GB 20926/62 A GB20926/62 A GB 20926/62A GB 2092662 A GB2092662 A GB 2092662A GB 991424 A GB991424 A GB 991424A
- Authority
- GB
- United Kingdom
- Prior art keywords
- tube
- pellets
- fissile
- sheath
- wave
- 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
- G21C21/12—Manufacture of fuel elements or breeder elements contained in non-active casings by hydrostatic or thermo-pneumatic canning in general by pressing without lengthening, e.g. explosive coating
-
- 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)
- Manufacturing & Machinery (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Fuel-Injection Apparatus (AREA)
Abstract
991,424. Stamping. UNITED KINGDOM ATOMIC ENERGY AUTHORITY. March 11, 1963 [May 30, 1962], No. 20926/62. Drawings to Specification. Heading B3Q. [Also in Division G6] As a step in the manufacture of a nuclear reactor fuel element, the protective sheath of the element is deformed into intimate contact with the fuel member by external pressurization brought about by a high-energy shock-wave or waves. The shock-wave or waves may be generated by a rod of explosive placed parallel with the assembled fuel element in a water-filled vessel and fired electrically. Alternatively electromagnetic means may be used, the element together with a copper tube in which it is coaxially disposed being positioned within a coil through which a bank of high capacity condensers is repeatedly discharged, thus setting up an intense variable magnetic field. A current is thereby induced in the tube which generates a magnetic field opposed to that set up by the condenser discharges and thereby subjects the tube to a physical force, which force effects deformation of both the tube and the protective sheath of the element. A similar device uses a spark-gap in place of the coil, a tungsten or titanium wire being connected across the gap which is immersed in a cylinder of water close to the element. On discharging the bank of condensers the wire vaporizes to create a high-energy wave front. In the embodiments described, the fuel element comprises a stack of pellets of ceramic fissile material enclosed withing a stainless steel sheath, one or more non- fissile pellets which divide up the stack of fissile pellets being each formed with a circumferential groove into which the sheath is deformed in order to provide a degree of keying. Specification 958,697, and U.S.A. Specification 2,976,907 are referred to.
Priority Applications (5)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
BE629449D BE629449A (en) | 1962-05-30 | ||
GB20926/62A GB991424A (en) | 1962-05-30 | 1962-05-30 | Improvements in or relating to fuel elements for nuclear reactors |
FR927551A FR1354379A (en) | 1962-05-30 | 1963-03-11 | Improvements to fuel cartridges for nuclear reactors |
DEU9637A DE1248178B (en) | 1962-05-30 | 1963-03-11 | Process for producing a nuclear reactor fuel assembly and device for carrying out the process |
ES285967A ES285967A1 (en) | 1962-05-30 | 1963-03-12 | Improvements in the manufacture of fuel elements for nuclear reactors (Machine-translation by Google Translate, not legally binding) |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB20926/62A GB991424A (en) | 1962-05-30 | 1962-05-30 | Improvements in or relating to fuel elements for nuclear reactors |
Publications (1)
Publication Number | Publication Date |
---|---|
GB991424A true GB991424A (en) | 1965-05-05 |
Family
ID=10154143
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB20926/62A Expired GB991424A (en) | 1962-05-30 | 1962-05-30 | Improvements in or relating to fuel elements for nuclear reactors |
Country Status (4)
Country | Link |
---|---|
BE (1) | BE629449A (en) |
DE (1) | DE1248178B (en) |
ES (1) | ES285967A1 (en) |
GB (1) | GB991424A (en) |
Families Citing this family (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE1303528B (en) * | 1964-06-10 | 1972-05-31 | Siemens Ag |
-
0
- BE BE629449D patent/BE629449A/xx unknown
-
1962
- 1962-05-30 GB GB20926/62A patent/GB991424A/en not_active Expired
-
1963
- 1963-03-11 DE DEU9637A patent/DE1248178B/en active Pending
- 1963-03-12 ES ES285967A patent/ES285967A1/en not_active Expired
Also Published As
Publication number | Publication date |
---|---|
BE629449A (en) | |
DE1248178B (en) | 1967-08-24 |
ES285967A1 (en) | 1963-11-16 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
US3035995A (en) | Electronic reactor safety control device | |
GB917938A (en) | Method and apparatus for injecting and trapping electrons in the magnetic field of athermonuclear reactor | |
GB1110657A (en) | Nuclear fuel elements | |
US5835545A (en) | Compact intense radiation system | |
GB1531666A (en) | Packed rod neutron shield for fast nuclear reactors | |
GB991424A (en) | Improvements in or relating to fuel elements for nuclear reactors | |
GB913656A (en) | Improvements in or relating to nuclear reactor fuel elements | |
US4121123A (en) | Explosively driven plasma current generator | |
WO1991013531A2 (en) | Amplification or generation of shock fronts | |
US3325375A (en) | Fuel element for a water-cooled nuclear reactor | |
GB1069277A (en) | Improvements in or relating to nuclear fuel element fabrication | |
GB919986A (en) | Improvements in or relating to spacing arrangements for nuclear fuel elements | |
GB942667A (en) | Improvements in or relating to neutron generators | |
Balthesen et al. | Magnetic After Effects in Nickel after Low Temperature Irradiation with Neutrons | |
SU529673A1 (en) | Impulsive nuclear reactor | |
ES449946A1 (en) | Control rod and reactor | |
FR2181885A1 (en) | Prismatic core configuration - for heterogeneous reactor using polygonal block fuel elements | |
RU95113294A (en) | NUCLEAR REACTOR CONTROL ROD | |
GB902786A (en) | Nuclear reactor control element | |
DAGBJARTSSON et al. | Results of studies on various fast and thermal thermionic reactor systems(Fast and thermal thermionic reactor systems characteristics including fissile material, components mass, power output and flattening and design features) | |
SU490187A1 (en) | Fast neutron reactor | |
GB904438A (en) | Improvements in or relating to nuclear reactor fuel elements | |
Thomsen et al. | Simulation of nuclear underwater shock waves using planar sources: an investigation of feasibility. Final report 23 July 79-30 April 80 | |
DICKERMAN et al. | Capsules and sodium loops used in Argonne National Laboratory reactor safety experiments in the TREAT reactor(Subjecting fuel capsules and sodium loops to power bursts in reactor safety experiments in Transient Reactor Test facility) | |
CAPO et al. | Heating rate calculations(for KIWI B-1 reactor core) |