BE903946A - Barre grise amelioree pour reacteur nucleaire. - Google Patents
Barre grise amelioree pour reacteur nucleaire.Info
- Publication number
- BE903946A BE903946A BE0/216068A BE216068A BE903946A BE 903946 A BE903946 A BE 903946A BE 0/216068 A BE0/216068 A BE 0/216068A BE 216068 A BE216068 A BE 216068A BE 903946 A BE903946 A BE 903946A
- Authority
- BE
- Belgium
- Prior art keywords
- longitudinal section
- gray bar
- tube
- nuclear reactor
- stack
- Prior art date
Links
- 239000000446 fuel Substances 0.000 abstract 2
- 239000008188 pellet Substances 0.000 abstract 2
- 238000005253 cladding Methods 0.000 abstract 1
- 230000009977 dual effect Effects 0.000 abstract 1
- 239000011796 hollow space material Substances 0.000 abstract 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/02—Details of handling arrangements
- G21C19/08—Means for heating fuel elements before introduction into the core; Means for heating or cooling fuel elements after removal from the core
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
- G21C7/08—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
- G21C7/10—Construction of control elements
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
- G21C7/08—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
- G21C7/10—Construction of control elements
- G21C7/117—Clusters of control rods; Spider construction
-
- 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)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Vibration Dampers (AREA)
- Devices And Processes Conducted In The Presence Of Fluids And Solid Particles (AREA)
Abstract
La barre grise comprend un tube de gainage à paroi mince (46) dont une première section longitudinale est disposée à l'intérieur du réseau des barres de combustible, tandis qu'une section longitudinale de ce tube se situe essentiellement à l'extérieur de ce réseau, lorsque la barre grise est introduite dans l'assemblage combustible, la première section formant un espace récepteur de pastilles (52),contenant une pile de pastilles annulaires (48), tandis que la seconde section longitudinale forme un espace creux (54) ne comportant pas de pastille et ne contenant qu'un ressort à boudin partiellement comprimé (50) qui assure la double fonction de retenir la pile des pastilles (48) dans l'espace (52) et d'assurer un support radial à la paroi de la seconde section longitudinale du tube.
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| US68677184A | 1984-12-27 | 1984-12-27 |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| BE903946A true BE903946A (fr) | 1986-06-24 |
Family
ID=24757677
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| BE0/216068A BE903946A (fr) | 1984-12-27 | 1985-12-24 | Barre grise amelioree pour reacteur nucleaire. |
Country Status (8)
| Country | Link |
|---|---|
| JP (2) | JPS61161488A (fr) |
| KR (1) | KR930011014B1 (fr) |
| CN (1) | CN85109308A (fr) |
| BE (1) | BE903946A (fr) |
| ES (1) | ES8705676A1 (fr) |
| FR (1) | FR2575580B1 (fr) |
| GB (1) | GB2169127B (fr) |
| IT (1) | IT1200904B (fr) |
Families Citing this family (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US7412021B2 (en) * | 2005-07-26 | 2008-08-12 | Westinghouse Electric Co Llc | Advanced gray rod control assembly |
| CN109036591B (zh) * | 2017-06-08 | 2021-10-15 | 中广核工程有限公司 | 核反应堆堆芯 |
Family Cites Families (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB926133A (en) * | 1958-10-28 | 1963-05-15 | Atomic Energy Authority Uk | Improvements in or relating to nuclear reactors |
| JPS5419089A (en) * | 1977-07-12 | 1979-02-13 | Toshiba Corp | Method to make a reactor control rod |
| US4432934A (en) * | 1980-12-16 | 1984-02-21 | Westinghouse Electric Corp. | Displacer rod for use in a mechanical spectral shift reactor |
| FR2518300B1 (fr) * | 1981-12-11 | 1987-10-16 | Framatome Sa | Crayon contenant un materiau consommable pour le pilotage d'un reacteur nucleaire |
| ES291691Y (es) * | 1983-11-30 | 1987-01-16 | Westinghouse Electric Corporation | Varilla de control auxiliar para ajuste fino de la reactividad de un reactor nuclear |
| DE3534902A1 (de) * | 1985-09-30 | 1987-04-02 | Kraftwerk Union Ag | Wasserverdraengungskoerper |
-
1985
- 1985-12-11 GB GB08530483A patent/GB2169127B/en not_active Expired
- 1985-12-18 IT IT23264/85A patent/IT1200904B/it active
- 1985-12-20 ES ES550274A patent/ES8705676A1/es not_active Expired
- 1985-12-24 BE BE0/216068A patent/BE903946A/fr not_active IP Right Cessation
- 1985-12-24 JP JP60299761A patent/JPS61161488A/ja active Pending
- 1985-12-26 CN CN198585109308A patent/CN85109308A/zh active Pending
- 1985-12-26 FR FR858519243A patent/FR2575580B1/fr not_active Expired
- 1985-12-27 KR KR1019850009868A patent/KR930011014B1/ko not_active Expired - Lifetime
-
1994
- 1994-01-14 JP JP1994000540U patent/JPH079118Y2/ja not_active Expired - Lifetime
Also Published As
| Publication number | Publication date |
|---|---|
| JPH0674998U (ja) | 1994-10-21 |
| GB8530483D0 (en) | 1986-01-22 |
| JPS61161488A (ja) | 1986-07-22 |
| FR2575580B1 (fr) | 1989-12-08 |
| IT1200904B (it) | 1989-01-27 |
| GB2169127A (en) | 1986-07-02 |
| JPH079118Y2 (ja) | 1995-03-06 |
| ES550274A0 (es) | 1987-05-01 |
| GB2169127B (en) | 1988-06-22 |
| FR2575580A1 (fr) | 1986-07-04 |
| KR860005394A (ko) | 1986-07-21 |
| CN85109308A (zh) | 1986-08-06 |
| IT8523264A0 (it) | 1985-12-18 |
| ES8705676A1 (es) | 1987-05-01 |
| KR930011014B1 (ko) | 1993-11-19 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| ZA9867B (en) | Process for producing a guide tube of nuclear reactor fuel assembly mandrel for forming the guide tube and the guide tube obtained | |
| GB1578443A (en) | Apparatus for producing a gaseous fuel from finely divided solid or liquid fuels | |
| CA2088104A1 (fr) | Radiateur de vehicule et sa methode de fabrication | |
| NO931898L (no) | Reformeringsroerenhet | |
| BE903946A (fr) | Barre grise amelioree pour reacteur nucleaire. | |
| CA2114509A1 (fr) | Systeme d'injection | |
| FR2864322B1 (fr) | Crayon de combustible pour un reacteur nucleaire | |
| US3291870A (en) | Method of fabricating a multichannel nuclear fuel element | |
| BE895156A (fr) | Recipient pour le stockage de longue duree, d'elements combustible epuises de reacteurs nucleaires | |
| GB9421179D0 (en) | Agitating apparatus for digestion tank | |
| EP0514121B1 (fr) | Assemblage de combustible ayant des barreaux de combustible avec deux diamètres | |
| FR2458131A1 (fr) | Echangeur intermediaire de chaleur pour reacteur nucleaire | |
| KR930005573B1 (ko) | 핵 연료봉 | |
| SE9501936D0 (sv) | Bränslepatron för kokarvattenreaktor | |
| FR2363867A1 (fr) | Procede pour ravitailler en combustible un coeur de reacteur nucleaire | |
| KR940002988B1 (ko) | 중공환상 지지 펠릿을 구비한 변위봉 | |
| FR2589615A1 (fr) | Installation de reacteur nucleaire avec cuve de reacteur supportee par le bas | |
| JPH06324169A (ja) | 高速増殖炉用金属燃料被覆管 | |
| JPS57153794A (en) | Methane fermenting vat | |
| EP0094732A3 (fr) | Générateur de vapeur pour réacteur surrégénérateur rapide à refroidissement par métal liquide | |
| JPS5818190A (ja) | 圧力管型原子炉 | |
| SU1346928A1 (ru) | Способ засыпки змеевиковых регенераторов | |
| JPH05126976A (ja) | 燃料集合体 | |
| JPS58110052U (ja) | 溶鋼精錬容器用底吹ガス吹込みノズル | |
| JPH0421091B2 (fr) |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| RE | Patent lapsed |
Owner name: WESTINGHOUSE ELECTRIC CORP. Effective date: 19911231 |