GB1021452A - Improvements relating to graphite structures in nuclear reactors - Google Patents
Improvements relating to graphite structures in nuclear reactorsInfo
- Publication number
- GB1021452A GB1021452A GB1212/62A GB121262A GB1021452A GB 1021452 A GB1021452 A GB 1021452A GB 1212/62 A GB1212/62 A GB 1212/62A GB 121262 A GB121262 A GB 121262A GB 1021452 A GB1021452 A GB 1021452A
- Authority
- GB
- United Kingdom
- Prior art keywords
- graphite
- irradiation
- temperature
- thermal expansion
- regions
- 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
- G21C1/00—Reactor types
- G21C1/04—Thermal reactors ; Epithermal reactors
- G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
- G21C1/08—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor
- G21C1/10—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor moderator and coolant being different or separated
- G21C1/12—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor moderator and coolant being different or separated moderator being solid, e.g. Magnox reactor or gas-graphite reactor
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C5/00—Moderator or core structure; Selection of materials for use as moderator
- G21C5/02—Details
- G21C5/04—Spatial arrangements allowing for Wigner growth
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C5/00—Moderator or core structure; Selection of materials for use as moderator
- G21C5/02—Details
- G21C5/08—Means for preventing undesired asymmetric expansion of the complete structure ; Stretching devices, pins
-
- 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)
- Carbon And Carbon Compounds (AREA)
- Physical Or Chemical Processes And Apparatus (AREA)
- Crystals, And After-Treatments Of Crystals (AREA)
Abstract
1,021,452. Moderator structures. UNITED KINGDOM ATOMIC ENERGY AUTHORITY. Jan. 2, 1963 [Jan. 12, 1962; Feb. 7, 1962], Nos. 1212/62 and 4806/62. Heading G6C. The graphite moderator structure of a nuclear reactor comprises graphite having different thermal expansion coefficients in regions of different normal operating temperature with the objective of dimensionally stabilizing the graphite under neutron irradiation. The coefficient of thermal expansion in at least one direction in each region is selected by (a) correlating the temperature of normal operation of that region with the irradiation temperature required to produce the same net damaging effect on graphite under the irradiation conditions of chosen available graphite irradiation data; (b) estimating for such irradiation temperature the bulk dimensional changes indicated by said data; and (c) using these dimensional changes to determine the requisite coefficient of thermal expansion. The regions may be layers of uniform thickness but, in general, the structure is divided into regions each defined by isotherms corresponding to the limits of preselected temperature ranges covering the full compass of the temperature distribution. In order that dimensional stability may prevail in all directions, the graphite selected should have a random crystal orientation of high crystallographic perfection and be substantially isotropic at least to the extent of the thermal expansion properties.
Priority Applications (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
DE19631439794 DE1439794C (en) | 1962-01-12 | 1963-01-11 | Gas-cooled nuclear reactor |
US560017A US3378459A (en) | 1962-01-12 | 1966-06-23 | Graphite structures in nuclear reactors |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB14109/65A GB1106432A (en) | 1965-04-02 | 1965-04-02 | Improvements relating to graphite structures in nuclear reactors |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1021452A true GB1021452A (en) | 1966-03-02 |
Family
ID=10035157
Family Applications (2)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB1212/62A Expired GB1021452A (en) | 1962-01-12 | 1962-01-12 | Improvements relating to graphite structures in nuclear reactors |
GB14109/65A Expired GB1106432A (en) | 1962-01-12 | 1965-04-02 | Improvements relating to graphite structures in nuclear reactors |
Family Applications After (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB14109/65A Expired GB1106432A (en) | 1962-01-12 | 1965-04-02 | Improvements relating to graphite structures in nuclear reactors |
Country Status (3)
Country | Link |
---|---|
BE (1) | BE678890A (en) |
DE (1) | DE1564964C3 (en) |
GB (2) | GB1021452A (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4030974A (en) * | 1973-09-08 | 1977-06-21 | Kernforschungsanlage Julich Gesellschaft Mit Beschrankter Haftung | Core reactor |
-
1962
- 1962-01-12 GB GB1212/62A patent/GB1021452A/en not_active Expired
-
1965
- 1965-04-02 GB GB14109/65A patent/GB1106432A/en not_active Expired
-
1966
- 1966-04-01 DE DE1564964A patent/DE1564964C3/en not_active Expired
- 1966-04-01 BE BE678890D patent/BE678890A/xx unknown
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4030974A (en) * | 1973-09-08 | 1977-06-21 | Kernforschungsanlage Julich Gesellschaft Mit Beschrankter Haftung | Core reactor |
Also Published As
Publication number | Publication date |
---|---|
GB1106432A (en) | 1968-03-20 |
DE1564964A1 (en) | 1970-01-22 |
BE678890A (en) | 1966-10-03 |
DE1564964C3 (en) | 1974-10-31 |
DE1564964B2 (en) | 1974-03-28 |
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