GB1256874A - - Google Patents
Info
- Publication number
- GB1256874A GB1256874A GB903768A GB1256874DA GB1256874A GB 1256874 A GB1256874 A GB 1256874A GB 903768 A GB903768 A GB 903768A GB 1256874D A GB1256874D A GB 1256874DA GB 1256874 A GB1256874 A GB 1256874A
- Authority
- GB
- United Kingdom
- Prior art keywords
- sodium
- fluid
- pipes
- liquid
- lining
- 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
- 239000011734 sodium Substances 0.000 abstract 9
- DGAQECJNVWCQMB-PUAWFVPOSA-M Ilexoside XXIX Chemical compound C[C@@H]1CC[C@@]2(CC[C@@]3(C(=CC[C@H]4[C@]3(CC[C@@H]5[C@@]4(CC[C@@H](C5(C)C)OS(=O)(=O)[O-])C)C)[C@@H]2[C@]1(C)O)C)C(=O)O[C@H]6[C@@H]([C@H]([C@@H]([C@H](O6)CO)O)O)O.[Na+] DGAQECJNVWCQMB-PUAWFVPOSA-M 0.000 abstract 8
- 229910052708 sodium Inorganic materials 0.000 abstract 8
- 239000012530 fluid Substances 0.000 abstract 7
- 238000001816 cooling Methods 0.000 abstract 4
- 239000007788 liquid Substances 0.000 abstract 4
- PQXKHYXIUOZZFA-UHFFFAOYSA-M lithium fluoride Chemical compound [Li+].[F-] PQXKHYXIUOZZFA-UHFFFAOYSA-M 0.000 abstract 2
- XPDWGBQVDMORPB-UHFFFAOYSA-N Fluoroform Chemical compound FC(F)F XPDWGBQVDMORPB-UHFFFAOYSA-N 0.000 abstract 1
- 229910001209 Low-carbon steel Inorganic materials 0.000 abstract 1
- JZKFIPKXQBZXMW-UHFFFAOYSA-L beryllium difluoride Chemical compound F[Be]F JZKFIPKXQBZXMW-UHFFFAOYSA-L 0.000 abstract 1
- 239000002826 coolant Substances 0.000 abstract 1
- 230000005496 eutectics Effects 0.000 abstract 1
- 239000012535 impurity Substances 0.000 abstract 1
- 238000009413 insulation Methods 0.000 abstract 1
- 229910001338 liquidmetal Inorganic materials 0.000 abstract 1
- 239000012528 membrane Substances 0.000 abstract 1
- 239000000203 mixture Substances 0.000 abstract 1
- 150000008442 polyphenolic compounds Chemical class 0.000 abstract 1
- 235000013824 polyphenols Nutrition 0.000 abstract 1
- 150000003839 salts Chemical class 0.000 abstract 1
- 238000007789 sealing Methods 0.000 abstract 1
- 239000007787 solid Substances 0.000 abstract 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 abstract 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/18—Emergency cooling arrangements; Removing shut-down heat
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/02—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C11/00—Shielding structurally associated with the reactor
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
-
- 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)
- Crystals, And After-Treatments Of Crystals (AREA)
- Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
Abstract
1,256,874. Reactors. UNITED KINGDOM ATOMIC ENERGY AUTHORITY. 14 Feb., 1969 [23 Feb., 1968], No. 9037/68. Heading G6C. A nuclear reactor which is cooled by, and whose core is submerged in, a liquid, has this liquid contained by a continuous layer of the liquid frozen into the solid state and supported by a support structure. In one embodiment, as shown in Fig. 1, a sodium-cooled fast breeder reactor has a concrete vault pre-stressed by means of ducted cables 9 to serve as a tank, the wall 1 of which is provided with a membrane lining 2 of mild steel. Pipes 3 for a cooling or refrigerating fluid 4 are embedded in the wall 1, and further pipes 5 are provided on the outer side of the lining 2, the contact positions of the pipes 3, 5 with the lining 2 being in staggered relationship. Cooling or refrigerating fluid 6 flows through the pipes 5, and may be the same fluid as 4, where this is compatible with sodium. The fluid 4 may be water, "Freon" (Trade Mark) or "Arcton" (Trade Mark) but as these are strongly reactive with sodium, the fluid 6 is different and may be the Na/K eutectic or a pressurized gas, e.g. He, A or CO 2 . The fluid 4 may also be one of these. With a mean temperature of about 400 C. of a sodium pool P contained in the lined vault, the cooling is designed to keep the temperature of the lined surface of the concrete wall 1 well within the limit prescribed for concrete, and to keep the temperature gradient across the wall 1 to about 50 C. It may be necessary to augment the cooling effect produced by the pipes 5 and fluid 6 by the provision of thermal insulation 7 over the pipes 5. The molten sodium of the pool P freezes in contact with the lining 2, the frozen volume being indicated by the shaded area 8 and the boundary of the volume by the broken line 9. The advantages of this frozen sodium volume which contain the molten sodium are compatibility, self-sealing property, and ability to act as cold trap for impurities. A large (600 M.W.(E.)) power generating fast breeder reactor cooled by liquid sodium and incorporating a concrete vault of the above type is described (Figs. 2 and 3, not shown). The invention is applicable to other coolants such as liquid metals other than sodium, polyphenols, and fused salts. An example of the last-named is a mixture of lithium fluoride and beryllium difluoride.
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| GB903768 | 1968-02-23 |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| GB1256874A true GB1256874A (en) | 1971-12-15 |
Family
ID=9864181
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| GB903768A Expired GB1256874A (en) | 1968-02-23 | 1968-02-23 |
Country Status (7)
| Country | Link |
|---|---|
| JP (1) | JPS4929558B1 (en) |
| BE (1) | BE728799A (en) |
| DE (1) | DE1908908A1 (en) |
| FR (1) | FR2002531A1 (en) |
| GB (1) | GB1256874A (en) |
| NL (1) | NL6902777A (en) |
| SE (1) | SE348868B (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| ES2335336A1 (en) * | 2009-06-22 | 2010-03-24 | Universidad Politecnica De Madrid | Heterogeneous nuclear reactor with beryllium compounds as coolants |
Families Citing this family (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2299702A1 (en) * | 1974-10-24 | 1976-08-27 | Electricite De France | Molten fuel salt mixture reactor - with protective structure and cooling for reactor vessel wall |
| FR2296248A1 (en) * | 1974-12-24 | 1976-07-23 | Electricite De France | Nuclear reactor fuelled by eutectic salt mixture - with integral primary cooling system |
| GB1494055A (en) * | 1974-12-24 | 1977-12-07 | Pechiney Ugine Kuhlmann | Molten salt in a nuclear reactor |
| FR2497388A1 (en) * | 1980-12-30 | 1982-07-02 | Commissariat Energie Atomique | NUCLEAR REACTOR COOLED BY A LIQUID METAL AND COMPRISING A COOLED COLD BOTTOM |
| NL2000078C2 (en) * | 2006-05-19 | 2007-11-20 | Gerrit Clemens Van Uitert | Nuclear reactor. |
| FR3104311B1 (en) * | 2019-12-09 | 2021-12-03 | Commissariat A L Energie Atomique Et Aux Energies Alternatives | Liquid metal cooled nuclear reactor incorporating a completely passive residual heat removal system (EPUR) |
-
1968
- 1968-02-23 GB GB903768A patent/GB1256874A/en not_active Expired
-
1969
- 1969-02-21 NL NL6902777A patent/NL6902777A/xx unknown
- 1969-02-21 FR FR6904569A patent/FR2002531A1/en active Granted
- 1969-02-21 BE BE728799D patent/BE728799A/xx unknown
- 1969-02-21 SE SE02449/69A patent/SE348868B/xx unknown
- 1969-02-22 DE DE19691908908 patent/DE1908908A1/en active Pending
- 1969-02-24 JP JP44013274A patent/JPS4929558B1/ja active Pending
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| ES2335336A1 (en) * | 2009-06-22 | 2010-03-24 | Universidad Politecnica De Madrid | Heterogeneous nuclear reactor with beryllium compounds as coolants |
| WO2010149801A1 (en) * | 2009-06-22 | 2010-12-29 | Universidad Politécnica de Madrid | Heterogeneous nuclear reactor with beryllium compounds as coolants |
Also Published As
| Publication number | Publication date |
|---|---|
| FR2002531A1 (en) | 1969-10-17 |
| FR2002531B1 (en) | 1973-08-10 |
| JPS4929558B1 (en) | 1974-08-05 |
| SE348868B (en) | 1972-09-11 |
| DE1908908A1 (en) | 1969-09-18 |
| NL6902777A (en) | 1969-08-26 |
| BE728799A (en) | 1969-08-21 |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PS | Patent sealed [section 19, patents act 1949] | ||
| PCNP | Patent ceased through non-payment of renewal fee |