SU1025203A1 - Method for automatic control of water level in steam generator drum of two-circuit atomic power plant - Google Patents
Method for automatic control of water level in steam generator drum of two-circuit atomic power plant Download PDFInfo
- Publication number
- SU1025203A1 SU1025203A1 SU813352563A SU3352563A SU1025203A1 SU 1025203 A1 SU1025203 A1 SU 1025203A1 SU 813352563 A SU813352563 A SU 813352563A SU 3352563 A SU3352563 A SU 3352563A SU 1025203 A1 SU1025203 A1 SU 1025203A1
- Authority
- SU
- USSR - Soviet Union
- Prior art keywords
- circuit
- water level
- steam generator
- drum
- power plant
- Prior art date
Links
Landscapes
- Control Of Non-Electrical Variables (AREA)
Abstract
СПОСОБ АВТОМАТИЧЕСКОГО РЕГУЛИРОВАНИЯ УРОВНЯ ВОДЫ В БАРАБАНЕ 1ТАРОГЕНЕРАТОРА ДВУХКОНТУРНОЙ АТОМНОЙ ЭЛЕКТРИЧЕСКОЙ СТАНЦИИ, имеющем встроенный теплообменник, изменени подачи питательной воды по величине и знаку алгебраической суммы сигналов по уровню в барабане,расходу питательной воды и тепловой нагрузке , отличающийс тем, что, с целью повьшени точности регулировани , измер ют температуру на входе и выходе встроенного теплообMeHHHka , определ ют разность измеренных температур и используют ее в качестве сигнала по тепловой нагрузке.A WAY OF AUTOMATIC REGULATION OF THE WATER LEVEL IN THE DRUM OF 1TOROGENERATOR OF TWO-CIRCUIT ATOMIC ELECTRIC STATION with the built-in heat exchanger, changes in the supply of feed water in terms of size and sign of the algebraic sum of signals by the level of the resource, and the time, I can use. , measure the temperature at the entrance and exit of the built-in heat MeHHHka, determine the difference between the measured temperatures and use it as a signal for thermal load kyo.
Description
(Л(L
if jif j
ю елyou ate
tsOtsO
ЮYU
о соabout with
Claims (1)
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
SU813352563A SU1025203A1 (en) | 1981-11-02 | 1981-11-02 | Method for automatic control of water level in steam generator drum of two-circuit atomic power plant |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
SU813352563A SU1025203A1 (en) | 1981-11-02 | 1981-11-02 | Method for automatic control of water level in steam generator drum of two-circuit atomic power plant |
Publications (1)
Publication Number | Publication Date |
---|---|
SU1025203A1 true SU1025203A1 (en) | 1987-06-30 |
Family
ID=20982008
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
SU813352563A SU1025203A1 (en) | 1981-11-02 | 1981-11-02 | Method for automatic control of water level in steam generator drum of two-circuit atomic power plant |
Country Status (1)
Country | Link |
---|---|
SU (1) | SU1025203A1 (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN102446566B (en) * | 2009-01-05 | 2014-06-04 | 中国广东核电集团有限公司 | Steam generator water-level control method and device and nuclear power plant of nuclear power generating unit |
-
1981
- 1981-11-02 SU SU813352563A patent/SU1025203A1/en active
Non-Patent Citations (1)
Title |
---|
Патейт FR № 2312728, кл. F 22 D 5/34, 1977. * |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN102446566B (en) * | 2009-01-05 | 2014-06-04 | 中国广东核电集团有限公司 | Steam generator water-level control method and device and nuclear power plant of nuclear power generating unit |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
ES8302906A1 (en) | Device for locally measuring the power in a nuclear reactor. | |
SU1025203A1 (en) | Method for automatic control of water level in steam generator drum of two-circuit atomic power plant | |
ES8505133A1 (en) | Device for fast and accurate power determination of a pressurised water nuclear reactor. | |
Mohr et al. | Perturbations of reactor flow and inlet temperature in EBR-II for reactivity feedback validation | |
Sweeney et al. | Measurement of core coolant flow velocities in PWRs using temperature: neutron noise cross correlation | |
FR2372495A1 (en) | NUCLEAR REACTOR AND METHOD FOR DETERMINING THE POWER DISTRIBUTION IN A REACTOR CORE | |
JPS562843A (en) | Control of temperature of reactor | |
JPS5653332A (en) | Controlling method of hot water supply system in solar energy air conditioning and hot water supply system | |
SU586329A1 (en) | Thermoanemometric flowmeter | |
JPS52139897A (en) | Measuring method and device for core coolant flow quantity in reactor | |
GB1365775A (en) | Process for the steady state measurement of the subcriticality of a nuclear reactor | |
JPS54145889A (en) | Controlling method and device for sodium temperature at fast breeder inlet | |
SU1190150A1 (en) | System for slag removal control | |
JPS56157745A (en) | Controller for number of refrigerators of cooling water supplier | |
Singer et al. | Response of EBR-II to a complete loss of primary forced flow during power operation | |
Gruzdeva et al. | Device for permanent testing tightness of steam generators | |
SU1481598A2 (en) | Calorimetric flow meter | |
Hicks et al. | Preliminary tests of a model of cooling-pond thermal performance | |
SU945590A1 (en) | Method of ac control of feed-water supply into boiler | |
KR830001313B1 (en) | Protection of Pressurized Water Reactor | |
SU618658A1 (en) | Heat quantity measuring device | |
JPS5631610A (en) | Measuring unit of flow rate | |
Hicks et al. | PREUMINARY TESTS OF A MODEL OF COOUNG-POND THERMAL PERFORMANCE | |
JPS57153163A (en) | Method of regulating flow of circulation in heat collecting device | |
JPS5321302A (en) | Steam generator |