ES468863A1 - Procedimiento de refrigeracion de la cuba de un reactor nu- clear de neutrones rapidos - Google Patents
Procedimiento de refrigeracion de la cuba de un reactor nu- clear de neutrones rapidosInfo
- Publication number
- ES468863A1 ES468863A1 ES468863A ES468863A ES468863A1 ES 468863 A1 ES468863 A1 ES 468863A1 ES 468863 A ES468863 A ES 468863A ES 468863 A ES468863 A ES 468863A ES 468863 A1 ES468863 A1 ES 468863A1
- Authority
- ES
- Spain
- Prior art keywords
- wall
- vessel
- baffle
- main vessel
- liquid metal
- 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
- 238000001816 cooling Methods 0.000 title abstract 2
- 238000000034 method Methods 0.000 title abstract 2
- 229910001338 liquidmetal Inorganic materials 0.000 abstract 4
- 239000000110 cooling liquid Substances 0.000 abstract 1
Classifications
-
- 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
- G21C1/03—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders cooled by a coolant not essentially pressurised, e.g. pool-type reactors
-
- 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
- G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
- G21C15/12—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from pressure vessel; from containment vessel
-
- 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)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
- Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
Abstract
Procedimiento de refrigeración de la cuba de un reactor nuclear de neutrones rápidos, el cual reactor comporta una cuba denominada principal, que rodea y envuelve una segunda cuba, denominada cuba interna, que contiene el núcleo y que separa un volumen de metal líquido encerrado en la cuba principal, en dos regiones, respectivamente denominadas colector caliente y colector frío; de manera que la circulación forzada del metal líquido aspirado al colector frío e impulsado a través del núcleo hacia el colector caliente, es realizada por una bombas distribuidas alrededor del núcleo; existiendo una pantalla separadora y una contrapantalla, dispuestas concéntricamente a la citada pared de la cuba principal y delimitando respectivamente, un primer espacio anular y un segundo espacio anular que desembocan en el colector frío; siendo el primer espacio anular recorrido por un caudal derivado de metal líquido de refrigeración que circula en sentido ascendente por dentro de este primer espacio y en contacto con la pared de la cuba principal, hasta un nivel superior constante y próximo a la arista superior de la citada pantalla separadora, caracterizado porque se hace verter el metal líquido en el segundo espacio anular hasta un nivel inferior, nivel que corresponde a la superficie libre del colector frío, por el intermedio de unos órganos que están en contacto con la pared de la pantalla separadora que está orientada hacia el interior de la cuba principal.
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| FR7711664A FR2388375A1 (fr) | 1977-04-19 | 1977-04-19 | Procede de refroidissement de la cuve d'un reacteur nucleaire et dispositif pour l'application du procede |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| ES468863A1 true ES468863A1 (es) | 1979-01-16 |
Family
ID=9189557
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| ES468863A Expired ES468863A1 (es) | 1977-04-19 | 1978-04-17 | Procedimiento de refrigeracion de la cuba de un reactor nu- clear de neutrones rapidos |
Country Status (8)
| Country | Link |
|---|---|
| US (1) | US4156629A (es) |
| JP (1) | JPS53129791A (es) |
| BE (1) | BE865946A (es) |
| DE (1) | DE2816348C2 (es) |
| ES (1) | ES468863A1 (es) |
| FR (1) | FR2388375A1 (es) |
| GB (1) | GB1595042A (es) |
| IT (1) | IT7867873A0 (es) |
Families Citing this family (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4298431A (en) * | 1977-06-13 | 1981-11-03 | Commissariat A L'energie Atomique | Device for the thermal protection of an internal structure of a liquid metal cooled fast reactor |
| FR2397046A1 (fr) * | 1977-07-05 | 1979-02-02 | Commissariat Energie Atomique | Reacteur nucleaire a eau legere pour la production d'eau chaude |
| US4613478A (en) * | 1978-08-31 | 1986-09-23 | Westinghouse Electric Corp. | Plenum separator system for pool-type nuclear reactors |
| US4302296A (en) * | 1978-09-28 | 1981-11-24 | Electric Power Research Institute, Inc. | Apparatus for insulating hot sodium in pool-type nuclear reactors |
| FR2508225A1 (fr) * | 1981-06-19 | 1982-12-24 | Novatome | Dispositif de jonction entre le conduit de refoulement d'une pompe primaire et un conduit solidaire du support de coeur d'un reacteur nucleaire a neutrons rapides |
| FR2643189B1 (fr) * | 1989-02-10 | 1991-05-10 | Commissariat Energie Atomique | Dispositif de protection thermique de la virole superieure de supportage d'une cuve suspendue, notamment dans un reacteur nucleaire a neutrons rapides |
Family Cites Families (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB1207036A (en) * | 1968-12-04 | 1970-09-30 | Babcock & Wilcox Ltd | Improvements in and relating to the heat-insulating screening of reactor pressure vessel walls |
| FR2220847B1 (es) * | 1973-03-07 | 1975-10-31 | Commissariat Energie Atomique | |
| US4056438A (en) * | 1973-10-18 | 1977-11-01 | Commissariat A L'energie Atomique | Liquid sodium cooled fast reactor |
| FR2248583B1 (es) * | 1973-10-18 | 1976-10-01 | Commissariat Energie Atomique | |
| FR2291580A1 (fr) * | 1974-11-14 | 1976-06-11 | Commissariat Energie Atomique | Dispositif de protection thermique de la cuve d'un reacteur |
-
1977
- 1977-04-19 FR FR7711664A patent/FR2388375A1/fr active Granted
-
1978
- 1978-04-07 US US05/894,377 patent/US4156629A/en not_active Expired - Lifetime
- 1978-04-07 GB GB13719/78A patent/GB1595042A/en not_active Expired
- 1978-04-11 JP JP4259178A patent/JPS53129791A/ja active Pending
- 1978-04-13 BE BE186763A patent/BE865946A/xx not_active IP Right Cessation
- 1978-04-14 DE DE2816348A patent/DE2816348C2/de not_active Expired
- 1978-04-17 ES ES468863A patent/ES468863A1/es not_active Expired
- 1978-04-18 IT IT7867873A patent/IT7867873A0/it unknown
Also Published As
| Publication number | Publication date |
|---|---|
| BE865946A (fr) | 1978-07-31 |
| JPS53129791A (en) | 1978-11-13 |
| FR2388375B1 (es) | 1980-02-22 |
| DE2816348C2 (de) | 1982-11-18 |
| IT7867873A0 (it) | 1978-04-18 |
| FR2388375A1 (fr) | 1978-11-17 |
| DE2816348A1 (de) | 1978-11-02 |
| GB1595042A (en) | 1981-08-05 |
| US4156629A (en) | 1979-05-29 |
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