GB1271347A - Nuclear reactor installations - Google Patents
Nuclear reactor installationsInfo
- Publication number
- GB1271347A GB1271347A GB42320/70A GB4232070A GB1271347A GB 1271347 A GB1271347 A GB 1271347A GB 42320/70 A GB42320/70 A GB 42320/70A GB 4232070 A GB4232070 A GB 4232070A GB 1271347 A GB1271347 A GB 1271347A
- Authority
- GB
- United Kingdom
- Prior art keywords
- bank
- control rods
- power output
- drive means
- move
- 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
- 238000009434 installation Methods 0.000 title 1
- 230000009467 reduction Effects 0.000 abstract 3
- 230000037431 insertion Effects 0.000 abstract 2
- 238000003780 insertion Methods 0.000 abstract 2
- 239000002826 coolant Substances 0.000 abstract 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/04—Safety arrangements
-
- 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
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
- G21C9/02—Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; Control elements having arrangements activated in an emergency
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
- G21C9/02—Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; Control elements having arrangements activated in an emergency
- G21C9/027—Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; Control elements having arrangements activated in an emergency by fast movement of a solid, e.g. pebbles
-
- 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
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Business, Economics & Management (AREA)
- Emergency Management (AREA)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
1,271,347. Controlling reactors. SIEMENS A.G. 3 Sept., 1970 [5 Sept., 1969], No. 42320/70. Heading G6C. The power output of a reactor is controlled by common drive means coupled to a bank of control rods to move them axially so as to change their degree of insertion in the reactor core, but rapid reduction of the power output is achieved, when required, by causing a control rod of the bank to be moved axially, at a rate which is high in comparison with that at which the common drive means move the control rods of the bank, from a withdrawn position of the bank to a fully-inserted position, whilst other control rods of the bank remain in the withdrawn position. The reduction in power output may be required because of a failure of a main coolant pump, or because of load shedding or sudden reductions in load. More than one of the control rods of a bank may be rapidly inserted, and this insertion may take place by automatic actions or manually. A control rod which has been rapidly inserted is withdrawn, shortly after having been inserted, at a selectively variable speed, and the common drive means are used to move the other control rods of the bank to bring the power output of the reactor to a desired level.
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
DE19691945044 DE1945044A1 (en) | 1969-09-05 | 1969-09-05 | Method for the accelerated power reduction of a pressurized water nuclear reactor |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1271347A true GB1271347A (en) | 1972-04-19 |
Family
ID=5744684
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB42320/70A Expired GB1271347A (en) | 1969-09-05 | 1970-09-03 | Nuclear reactor installations |
Country Status (10)
Country | Link |
---|---|
JP (1) | JPS5114673B1 (en) |
AT (1) | AT311504B (en) |
BE (1) | BE755198A (en) |
CH (1) | CH515587A (en) |
DE (1) | DE1945044A1 (en) |
ES (1) | ES383388A1 (en) |
FR (1) | FR2060424B1 (en) |
GB (1) | GB1271347A (en) |
NL (1) | NL7012030A (en) |
SE (1) | SE359954B (en) |
Families Citing this family (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4129475A (en) * | 1975-07-31 | 1978-12-12 | Westinghouse Electric Corp. | Method of operating a nuclear reactor |
JP7026034B2 (en) * | 2018-11-26 | 2022-02-25 | 三菱重工業株式会社 | Reactor output control device, nuclear plant and reactor output control method |
-
0
- BE BE755198D patent/BE755198A/en unknown
-
1969
- 1969-09-05 DE DE19691945044 patent/DE1945044A1/en active Pending
-
1970
- 1970-08-14 NL NL7012030A patent/NL7012030A/xx unknown
- 1970-08-17 AT AT744270A patent/AT311504B/en not_active IP Right Cessation
- 1970-08-24 CH CH1259970A patent/CH515587A/en not_active IP Right Cessation
- 1970-09-02 SE SE11927/70A patent/SE359954B/xx unknown
- 1970-09-03 GB GB42320/70A patent/GB1271347A/en not_active Expired
- 1970-09-04 ES ES383388A patent/ES383388A1/en not_active Expired
- 1970-09-04 FR FR707032330A patent/FR2060424B1/fr not_active Expired
- 1970-09-05 JP JP45077540A patent/JPS5114673B1/ja active Pending
Also Published As
Publication number | Publication date |
---|---|
JPS5114673B1 (en) | 1976-05-11 |
DE1945044A1 (en) | 1971-04-08 |
BE755198A (en) | 1971-02-01 |
ES383388A1 (en) | 1974-06-16 |
NL7012030A (en) | 1971-03-09 |
FR2060424A1 (en) | 1971-06-18 |
AT311504B (en) | 1973-11-26 |
SE359954B (en) | 1973-09-10 |
FR2060424B1 (en) | 1974-07-12 |
CH515587A (en) | 1971-11-15 |
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