GB2018010A - Methods of reactor power determination in nuclear reactors - Google Patents
Methods of reactor power determination in nuclear reactorsInfo
- Publication number
- GB2018010A GB2018010A GB7903330A GB7903330A GB2018010A GB 2018010 A GB2018010 A GB 2018010A GB 7903330 A GB7903330 A GB 7903330A GB 7903330 A GB7903330 A GB 7903330A GB 2018010 A GB2018010 A GB 2018010A
- Authority
- GB
- United Kingdom
- Prior art keywords
- power
- signal
- thermal
- power signal
- reactor
- 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.)
- Granted
Links
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
-
- 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)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
A method for rapidly and accurately generating an output signal (8) corresponding to the power of a nuclear reactor comprises generating out-of- core neutron flux reactor power signals (2) at different time intervals and utilising predetermined relationships therebetween to adjust a more accurate thermal power signal (1) which has a slow response to transient power conditions. By means of a feedback loop (9), a delayed power signal (3) is fed back to a difference unit (5) to generate a signal in proportion to the difference between the neutron power signal (2) and the delayed power signal (3), which signal is combined with the thermal power signal (1) in a summing unit (4) to obtain a value equal to the instantaneous core power then being perceived by thermal sensors but not immediately available due to the time lag of the thermal response. The output signal (8) is used for reactor control, power limitation or safety shut-down. <IMAGE>
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
DE19782804532 DE2804532A1 (en) | 1978-02-03 | 1978-02-03 | PROCEDURE FOR QUICK AND ACCURATE DETERMINATION OF REACTOR PERFORMANCE IN NUCLEAR REACTORS |
Publications (2)
Publication Number | Publication Date |
---|---|
GB2018010A true GB2018010A (en) | 1979-10-10 |
GB2018010B GB2018010B (en) | 1982-06-23 |
Family
ID=6031021
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB7903330A Expired GB2018010B (en) | 1978-02-03 | 1979-01-31 | Methods of reactor power determination in nuclear reactors |
Country Status (9)
Country | Link |
---|---|
JP (1) | JPS6021359B2 (en) |
AT (1) | AT362470B (en) |
CA (1) | CA1111153A (en) |
CH (1) | CH636982A5 (en) |
DE (1) | DE2804532A1 (en) |
ES (1) | ES477170A1 (en) |
FR (1) | FR2416531A1 (en) |
GB (1) | GB2018010B (en) |
MX (1) | MX6311E (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE10159432A1 (en) * | 2001-12-04 | 2003-06-26 | Framatome Anp Gmbh | Control system for nuclear power plant, comprises monitoring unit, sensors in reactor core, and comparison unit |
Families Citing this family (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2542493B1 (en) * | 1983-03-11 | 1985-12-27 | Framatome Sa | DEVICE FOR QUICK AND ACCURATE DETERMINATION OF THE POWER OF A PRESSURE WATER NUCLEAR REACTOR |
JPS6382457U (en) * | 1986-11-17 | 1988-05-30 | ||
CN110276219B (en) * | 2019-06-24 | 2021-05-04 | 中国原子能科学研究院 | Calibration method for output power of nuclear reactor |
Family Cites Families (9)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR1206861A (en) * | 1958-05-20 | 1960-02-12 | Indatom | Device for automatic control of the operation of a nuclear reactor |
FR1356683A (en) * | 1962-06-07 | 1964-03-27 | Sulzer Ag | Process for the operation of a nuclear reactor and nuclear reactor for its implementation |
CH404818A (en) * | 1963-09-19 | 1965-12-31 | Sulzer Ag | Method and device for determining the instantaneous power output of an atomic nuclear reactor |
NL152097B (en) * | 1964-05-22 | 1977-01-17 | Stichting Reactor Centrum | REACTOR INSTALLATION. |
FR1401115A (en) * | 1964-07-20 | 1965-05-28 | Sulzer Ag | Nuclear reactor and method for determining the instantaneous power that it delivers |
US3752735A (en) * | 1970-07-16 | 1973-08-14 | Combustion Eng | Instrumentation for nuclear reactor core power measurements |
US3933580A (en) * | 1971-03-08 | 1976-01-20 | Siemens Aktiengesellschaft | Limit regulation system for pressurized water nuclear reactors |
US4103161A (en) * | 1976-07-15 | 1978-07-25 | The Babcock & Wilcox Company | Composite transducer |
JPS5811036B2 (en) * | 1976-10-08 | 1983-03-01 | 株式会社日立製作所 | Output control device for pressure tube reactor |
-
1978
- 1978-02-03 DE DE19782804532 patent/DE2804532A1/en not_active Ceased
- 1978-11-29 CH CH1219578A patent/CH636982A5/en not_active IP Right Cessation
-
1979
- 1979-01-18 CA CA319,862A patent/CA1111153A/en not_active Expired
- 1979-01-25 MX MX797683U patent/MX6311E/en unknown
- 1979-01-25 ES ES79477170A patent/ES477170A1/en not_active Expired
- 1979-01-29 AT AT62279A patent/AT362470B/en not_active IP Right Cessation
- 1979-01-29 JP JP54008285A patent/JPS6021359B2/en not_active Expired
- 1979-01-29 FR FR7902235A patent/FR2416531A1/en active Granted
- 1979-01-31 GB GB7903330A patent/GB2018010B/en not_active Expired
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE10159432A1 (en) * | 2001-12-04 | 2003-06-26 | Framatome Anp Gmbh | Control system for nuclear power plant, comprises monitoring unit, sensors in reactor core, and comparison unit |
Also Published As
Publication number | Publication date |
---|---|
JPS54123692A (en) | 1979-09-26 |
ES477170A1 (en) | 1979-12-01 |
ATA62279A (en) | 1980-10-15 |
CA1111153A (en) | 1981-10-20 |
GB2018010B (en) | 1982-06-23 |
DE2804532A1 (en) | 1979-08-09 |
MX6311E (en) | 1985-04-01 |
AT362470B (en) | 1981-05-25 |
FR2416531A1 (en) | 1979-08-31 |
CH636982A5 (en) | 1983-06-30 |
JPS6021359B2 (en) | 1985-05-27 |
FR2416531B1 (en) | 1984-09-28 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
ES8702057A1 (en) | Method and apparatus for determining the nearness to criticality of a nuclear reactor. | |
ES8802348A1 (en) | Fission-couple neutron sensor | |
GB2018010A (en) | Methods of reactor power determination in nuclear reactors | |
ES465869A1 (en) | Instrumentation assembly for nuclear reactor | |
US3079315A (en) | Nuclear reactor control | |
GB1005940A (en) | Improvements in and relating to nuclear reactors | |
US2931761A (en) | Neutronic reactor control | |
US4297581A (en) | Method for the fast and accurate identification of core power in nuclear reactors | |
GB899747A (en) | Improvements in burst jacket detection in nuclear reactors | |
ES478693A1 (en) | Incore power limit control technique | |
GB1417914A (en) | Nuclear power plant | |
JPS6479695A (en) | Incore nuclear instrumentation for fast breeder reactor | |
GB1522388A (en) | Process for the operation of nuclear reactors | |
FR2372495A1 (en) | NUCLEAR REACTOR AND METHOD FOR DETERMINING THE POWER DISTRIBUTION IN A REACTOR CORE | |
GB1149062A (en) | Electric control apparatus | |
ES8609800A1 (en) | Method and device for detecting reactivity variations in a PWR's core. | |
GB975742A (en) | Improvements in or relating to nuclear reactor control | |
GB1047152A (en) | Control systems | |
GB1454189A (en) | Method for preventing tritium contamination in a nuclear reactor | |
GB1206728A (en) | Nuclear reactor reactivity control method | |
JPS54155392A (en) | Device for prenotifying maximum permissible power changing time of nuclear reactor fuel element | |
GB1282787A (en) | Improvements in and relating to reactivity meters | |
GB1191807A (en) | Thermal Neutron Source | |
Tzanos et al. | Sensitivity of the power distribution in large heterogeneous LMFBR designs | |
TURNER | Dynamic analysis of gas-core reactor system(Model for dynamic analysis of gas core reactor system)[Final Report] |
Legal Events
Date | Code | Title | Description |
---|---|---|---|
PE20 | Patent expired after termination of 20 years |
Effective date: 19990130 |