GB1341131A - Methods of operating nuclear reactors - Google Patents
Methods of operating nuclear reactorsInfo
- Publication number
- GB1341131A GB1341131A GB2186771A GB2186771A GB1341131A GB 1341131 A GB1341131 A GB 1341131A GB 2186771 A GB2186771 A GB 2186771A GB 2186771 A GB2186771 A GB 2186771A GB 1341131 A GB1341131 A GB 1341131A
- Authority
- GB
- United Kingdom
- Prior art keywords
- bank
- doppler
- power
- rods
- load
- 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
- 230000000694 effects Effects 0.000 abstract 3
- 239000002826 coolant Substances 0.000 abstract 2
- 239000000446 fuel Substances 0.000 abstract 2
- 239000003795 chemical substances by application Substances 0.000 abstract 1
- 230000007774 longterm Effects 0.000 abstract 1
- 230000000630 rising effect Effects 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
- G21C7/00—Control of nuclear reaction
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F15—FLUID-PRESSURE ACTUATORS; HYDRAULICS OR PNEUMATICS IN GENERAL
- F15B—SYSTEMS ACTING BY MEANS OF FLUIDS IN GENERAL; FLUID-PRESSURE ACTUATORS, e.g. SERVOMOTORS; DETAILS OF FLUID-PRESSURE SYSTEMS, NOT OTHERWISE PROVIDED FOR
- F15B11/00—Servomotor systems without provision for follow-up action; Circuits therefor
- F15B11/06—Servomotor systems without provision for follow-up action; Circuits therefor involving features specific to the use of a compressible medium, e.g. air, steam
- F15B11/064—Servomotor systems without provision for follow-up action; Circuits therefor involving features specific to the use of a compressible medium, e.g. air, steam with devices for saving the compressible medium
-
- 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
-
- 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
- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- General Engineering & Computer Science (AREA)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Plasma & Fusion (AREA)
- High Energy & Nuclear Physics (AREA)
- Fluid Mechanics (AREA)
- Mechanical Engineering (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
1341131 Controlling reactors SIEMENS AG 19 April 1971 [19 Feb 1970] 21867/71 Heading G6C In the power regulation of a pressurized water nuclear reactor, in particular in the control of load cycles, using a power control-rod bank, the compensation of the Doppler effect, occurring with load variations and caused by variation of the fuel temperature, is carried out by means of a Doppler control-rod bank, while the power control-rod bank has a constant entry depth. The rods of the power bank are generally inserted only into the upper region of the core, even if the desired power output is quite low. The number of rods in the Doppler bank, which may consist of a partial group of the power bank, is selected such that it fully enters the reactor core at the minimum load in order to compensate for the effects of the fuel temperature variation and in order that it should absorb uniformly over the entire core height. At larger partial loads, a smaller number of rods will be selected for the Doppler bank, which would fully enter the core for the larger partial loads also. Owing to the initially rising coolant temperature when the load is reduced, the control rods of the Doppler bank at first receive entry command to provide adequate rod effectiveness, accompanying entry ofthe control rods of the power bank being necessary since the Doppler bank works slowly. After adequate regulation of coolant temperature, the power bank receives upwards command to its former working position, while the Doppler bank alone takes over the compensation. On the load being restored, the Doppler bank returns to its full load position corresponding to the working position of the power bank. It is advantageous for the rods of the Doppler bank to be exchangeable at relatively long time intervals with the rods of the power bank to avoid long-term different burnup effects.
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
DE2007564A DE2007564C3 (en) | 1970-02-19 | 1970-02-19 | Method for regulating the output of a pressurized water reactor |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1341131A true GB1341131A (en) | 1973-12-19 |
Family
ID=5762680
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB2186771A Expired GB1341131A (en) | 1970-02-19 | 1971-04-19 | Methods of operating nuclear reactors |
Country Status (6)
Country | Link |
---|---|
JP (1) | JPS5147837B1 (en) |
BE (1) | BE760096A (en) |
DE (2) | DE2007564C3 (en) |
FR (1) | FR2080625B1 (en) |
GB (1) | GB1341131A (en) |
SE (1) | SE363919B (en) |
Cited By (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
WO2013158701A1 (en) | 2012-04-17 | 2013-10-24 | Babcock & Wilcox Mpower, Inc. | Extended operating cycle for pressurized water reactor |
US10847276B2 (en) | 2013-07-04 | 2020-11-24 | Areva Np | Method for controlling a pressurized water nuclear reactor during stretchout |
CN113874957A (en) * | 2019-05-07 | 2021-12-31 | 法玛通股份有限公司 | Method for managing pressurized water nuclear reactor and corresponding management system |
Families Citing this family (11)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE2337354C3 (en) * | 1973-07-23 | 1981-06-25 | Siemens AG, 1000 Berlin und 8000 München | Device for regulating a pressurized water reactor with adjustable control rods |
US4129475A (en) * | 1975-07-31 | 1978-12-12 | Westinghouse Electric Corp. | Method of operating a nuclear reactor |
DE2702077C2 (en) * | 1977-01-19 | 1987-01-29 | Hitachi, Ltd., Tokio/Tokyo | Method for operating a boiling water or pressurized water reactor |
FR2395572A1 (en) * | 1977-06-23 | 1979-01-19 | Framatome Sa | PROCEDURE FOR MONITORING THE REACTIVITY EFFECTS DUE TO POWER VARIATIONS IN NUCLEAR REACTORS WITH PRESSURIZED WATER |
FR2493582A1 (en) * | 1980-11-03 | 1982-05-07 | Framatome Sa | METHOD FOR CONDUCTING A NUCLEAR REACTOR BY MOVING INTO THE HEART OF THIS REACTOR CONTROL BAR GROUPS |
US4582669A (en) * | 1982-01-08 | 1986-04-15 | Westinghouse Electric Corp. | Xenon suppression in a nuclear fueled electric power generation system |
JPS5944689A (en) * | 1982-09-06 | 1984-03-13 | 株式会社日立製作所 | Method of controlling operation of bwr type reactor |
FR2535509B1 (en) * | 1982-10-27 | 1985-07-26 | Framatome Sa | PROCESS FOR OPERATING A MODERATE NUCLEAR REACTOR COOLED WITH LIGHT WATER |
FR2535508B1 (en) * | 1982-10-27 | 1986-07-04 | Framatome Sa | NUCLEAR REACTOR WITH IMPROVED YIELD |
JPS59184895A (en) * | 1983-04-06 | 1984-10-20 | 株式会社日立製作所 | Method of controlling reactor load following-up |
FR2901401A1 (en) * | 2006-05-22 | 2007-11-23 | Areva Np Sas | Controlling operating parameters of a nuclear reactor core in pressurized water, comprises evaluating the actual values of operating parameters according to the acquired quantities of operating conditions of the reactor core |
-
0
- BE BE760096D patent/BE760096A/en unknown
-
1970
- 1970-02-19 DE DE2007564A patent/DE2007564C3/en not_active Expired
-
1971
- 1971-02-18 FR FR7105599A patent/FR2080625B1/fr not_active Expired
- 1971-02-19 JP JP717902A patent/JPS5147837B1/ja active Pending
- 1971-02-19 SE SE02149/71A patent/SE363919B/xx unknown
- 1971-04-19 GB GB2186771A patent/GB1341131A/en not_active Expired
-
1974
- 1974-09-27 DE DE19742446247 patent/DE2446247A1/en active Pending
Cited By (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
WO2013158701A1 (en) | 2012-04-17 | 2013-10-24 | Babcock & Wilcox Mpower, Inc. | Extended operating cycle for pressurized water reactor |
CN104508749A (en) * | 2012-04-17 | 2015-04-08 | 巴布科克和威尔科克斯M能量股份有限公司 | Extended operating cycle for pressurized water reactor |
EP2839467A4 (en) * | 2012-04-17 | 2015-12-23 | Babcock & Wilcox Mpower Inc | Extended operating cycle for pressurized water reactor |
US10847276B2 (en) | 2013-07-04 | 2020-11-24 | Areva Np | Method for controlling a pressurized water nuclear reactor during stretchout |
CN113874957A (en) * | 2019-05-07 | 2021-12-31 | 法玛通股份有限公司 | Method for managing pressurized water nuclear reactor and corresponding management system |
CN113874957B (en) * | 2019-05-07 | 2024-05-24 | 法玛通股份有限公司 | Method for managing a pressurized water nuclear reactor and corresponding management system |
Also Published As
Publication number | Publication date |
---|---|
DE2446247A1 (en) | 1976-04-01 |
DE2007564C3 (en) | 1973-10-18 |
DE2007564B2 (en) | 1973-03-29 |
SE363919B (en) | 1974-02-04 |
FR2080625B1 (en) | 1976-05-28 |
FR2080625A1 (en) | 1971-11-19 |
JPS5147837B1 (en) | 1976-12-17 |
DE2007564A1 (en) | 1971-09-02 |
BE760096A (en) | 1971-05-17 |
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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 |