GB1499092A - Nuclear reactor coolant transport system - Google Patents
Nuclear reactor coolant transport systemInfo
- Publication number
- GB1499092A GB1499092A GB24044/76A GB2404476A GB1499092A GB 1499092 A GB1499092 A GB 1499092A GB 24044/76 A GB24044/76 A GB 24044/76A GB 2404476 A GB2404476 A GB 2404476A GB 1499092 A GB1499092 A GB 1499092A
- Authority
- GB
- United Kingdom
- Prior art keywords
- pump
- coolant
- nuclear reactor
- reactor vessel
- inlet
- 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
- G21D—NUCLEAR POWER PLANT
- G21D1/00—Details of nuclear power plant
- G21D1/04—Pumping arrangements
-
- 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
-
- 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
Abstract
1499092 Nuclear reactor cooling systems WESTINGHOUSE ELECTRIC COKP 10 June 1976 [10 June 1975] 24044/76 Heading G6C In a nuclear reactor (e.g. sodium-cooled, fast breeder) coolant system (Fig. 1), an outlet 32 from a circulating pump 24 is connected by a line 52 to the drive nozzle of a jet pump 50 disposed in a main coolant line 48 between a reactor vessel coolant outlet 16 and the circulating pump inlet 30. The major proportion of coolant leaving the pump 24 passes to a heat exchanger 44 or, if the pump 24 is in the "cold leg", passes back to a reactor vessel coolant inlet 14. The jet pump 50, which may be of conventional form (Fig. 2, not shown) or be modified (Fig. 3) to include several drive nozzles 70, operates to reduce and eliminate any pressure differential (in the main coolant line 48 between the reactor vessel coolant outlet 16 and pump inlet 30) occasioned by operation of the pump 24.
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
US05585727 UST945008I4 (en) | 1975-06-10 | 1975-06-10 |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1499092A true GB1499092A (en) | 1978-01-25 |
Family
ID=24342701
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB24044/76A Expired GB1499092A (en) | 1975-06-10 | 1976-06-10 | Nuclear reactor coolant transport system |
Country Status (5)
Country | Link |
---|---|
US (1) | UST945008I4 (en) |
JP (1) | JPS5922200B2 (en) |
DE (1) | DE2620151A1 (en) |
FR (1) | FR2314561A1 (en) |
GB (1) | GB1499092A (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
EP0377494A1 (en) * | 1989-01-03 | 1990-07-11 | Westinghouse Electric Corporation | Pressurized water nuclear reactor system with hot let vortex mitigator |
Families Citing this family (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US6808047B2 (en) | 2001-11-05 | 2004-10-26 | Maki Takeshima | Escape device |
-
1975
- 1975-06-10 US US05585727 patent/UST945008I4/en active Pending
-
1976
- 1976-05-07 DE DE19762620151 patent/DE2620151A1/en not_active Withdrawn
- 1976-06-09 JP JP51066669A patent/JPS5922200B2/en not_active Expired
- 1976-06-09 FR FR7617382A patent/FR2314561A1/en active Granted
- 1976-06-10 GB GB24044/76A patent/GB1499092A/en not_active Expired
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
EP0377494A1 (en) * | 1989-01-03 | 1990-07-11 | Westinghouse Electric Corporation | Pressurized water nuclear reactor system with hot let vortex mitigator |
Also Published As
Publication number | Publication date |
---|---|
UST945008I4 (en) | 1976-04-06 |
DE2620151A1 (en) | 1976-12-30 |
FR2314561A1 (en) | 1977-01-07 |
FR2314561B1 (en) | 1978-11-17 |
JPS5922200B2 (en) | 1984-05-24 |
JPS51151499A (en) | 1976-12-25 |
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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 |