GB1204375A - Nuclear reactors - Google Patents
Nuclear reactorsInfo
- Publication number
- GB1204375A GB1204375A GB35472/67A GB3547267A GB1204375A GB 1204375 A GB1204375 A GB 1204375A GB 35472/67 A GB35472/67 A GB 35472/67A GB 3547267 A GB3547267 A GB 3547267A GB 1204375 A GB1204375 A GB 1204375A
- Authority
- GB
- United Kingdom
- Prior art keywords
- fuel
- section
- cluster
- cross
- fuel elements
- 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
- 239000000446 fuel Substances 0.000 abstract 10
- 229910052770 Uranium Inorganic materials 0.000 abstract 3
- 239000002826 coolant Substances 0.000 abstract 3
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 abstract 3
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 abstract 2
- 229910001093 Zr alloy Inorganic materials 0.000 abstract 2
- 238000010276 construction Methods 0.000 abstract 2
- 229910002804 graphite Inorganic materials 0.000 abstract 2
- 239000010439 graphite Substances 0.000 abstract 2
- 239000011343 solid material Substances 0.000 abstract 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 abstract 2
- FYYHWMGAXLPEAU-UHFFFAOYSA-N Magnesium Chemical compound [Mg] FYYHWMGAXLPEAU-UHFFFAOYSA-N 0.000 abstract 1
- 229910052790 beryllium Inorganic materials 0.000 abstract 1
- ATBAMAFKBVZNFJ-UHFFFAOYSA-N beryllium atom Chemical compound [Be] ATBAMAFKBVZNFJ-UHFFFAOYSA-N 0.000 abstract 1
- 229910052749 magnesium Inorganic materials 0.000 abstract 1
- 239000011777 magnesium Substances 0.000 abstract 1
- 229910052751 metal Inorganic materials 0.000 abstract 1
- 239000002184 metal Substances 0.000 abstract 1
- OOAWCECZEHPMBX-UHFFFAOYSA-N oxygen(2-);uranium(4+) Chemical compound [O-2].[O-2].[U+4] OOAWCECZEHPMBX-UHFFFAOYSA-N 0.000 abstract 1
- 239000008188 pellet Substances 0.000 abstract 1
- FCTBKIHDJGHPPO-UHFFFAOYSA-N uranium dioxide Inorganic materials O=[U]=O FCTBKIHDJGHPPO-UHFFFAOYSA-N 0.000 abstract 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/04—Thermal reactors ; Epithermal reactors
- G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
- G21C1/14—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor
- G21C1/16—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor
- G21C1/18—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor coolant being pressurised
- G21C1/20—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor coolant being pressurised moderator being liquid, e.g. pressure-tube reactor
-
- 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
- G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
- G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
- G21C3/326—Bundles of parallel pin-, rod-, or tube-shaped fuel elements comprising fuel elements of different composition; comprising, in addition to the fuel elements, other pin-, rod-, or tube-shaped elements, e.g. control rods, grid support rods, fertile rods, poison rods or dummy rods
-
- 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)
- Inorganic Compounds Of Heavy Metals (AREA)
Abstract
1,204,375. Reactors. UNITED KINGDOM ATOMIC ENERGY AUTHORITY. 23 July, 1968 [2 Aug., 1967], No. 35472/67. Heading G6C. In a nuclear reactor having natural uranium fuel contained in pressure tubes of circular cross-section through which light water coolant is conducted, the fuel in each tube 1 comprises closely spaced, parallel fuel elements 2 arranged on a lattice to form a cluster of generally rectilinear cross-section, and the voids 3 bounded by the sides of the fuel element cluster and the internal wall surface of the tube 1 contain solid material of low neutron absorbing cross-section, e.g. graphite, beryllium or magnesium. The uranium fuel may be in the form of uranium metal or oxide. In a preferred construction, the fuel elements 2 are arranged in triangular lattice pitch to form a cluster of hexagonal cross-section, as shown, and graphite bars 4 of generally segmental cross-section are contained within the voids 3. The bars 4 may be clamped to sides of the cluster. In this construction, the fuel elements 2 comprise stacks of uranium dioxide pellets sheathed in zirconium alloy and the pressure tube 1 is of zirconium alloy. The lattice arrangement of fuel elements enables small, uniform interspacing of the fuel elements to be achieved, and the solid material serves to replace coolant water which would normally occupy the voids within the pressure tubes and thereby increases the fuel/coolant ratio.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| GB35472/67A GB1204375A (en) | 1967-08-02 | 1967-08-02 | Nuclear reactors |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| GB35472/67A GB1204375A (en) | 1967-08-02 | 1967-08-02 | Nuclear reactors |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| GB1204375A true GB1204375A (en) | 1970-09-09 |
Family
ID=10378106
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| GB35472/67A Expired GB1204375A (en) | 1967-08-02 | 1967-08-02 | Nuclear reactors |
Country Status (1)
| Country | Link |
|---|---|
| GB (1) | GB1204375A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2130384A1 (en) * | 1971-03-19 | 1972-11-03 | Ca Atomic Energy Ltd |
-
1967
- 1967-08-02 GB GB35472/67A patent/GB1204375A/en not_active Expired
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2130384A1 (en) * | 1971-03-19 | 1972-11-03 | Ca Atomic Energy Ltd |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PS | Patent sealed [section 19, patents act 1949] | ||
| PLNP | Patent lapsed through nonpayment of renewal fees |