DE3869800D1 - Methode zur bestimmung der alarmschwelle des verhaeltnisses der kritischen aufheizung und anlage zur durchfuehrung der methode. - Google Patents
Methode zur bestimmung der alarmschwelle des verhaeltnisses der kritischen aufheizung und anlage zur durchfuehrung der methode.Info
- Publication number
- DE3869800D1 DE3869800D1 DE8888101234T DE3869800T DE3869800D1 DE 3869800 D1 DE3869800 D1 DE 3869800D1 DE 8888101234 T DE8888101234 T DE 8888101234T DE 3869800 T DE3869800 T DE 3869800T DE 3869800 D1 DE3869800 D1 DE 3869800D1
- Authority
- DE
- Germany
- Prior art keywords
- implementing
- determining
- alarm threshold
- heating ratio
- critical heating
- 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 - Lifetime
Links
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/08—Regulation of any parameters in the plant
- G21D3/10—Regulation of any parameters in the plant by a combination of a variable derived from neutron flux with other controlling variables, e.g. derived from temperature, cooling flow, pressure
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/36—Control circuits
-
- 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)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
FR8701162A FR2610446B1 (fr) | 1987-01-30 | 1987-01-30 | Procede de determination du seuil d'alarme du rapport d'echauffement critique, dispositif de mise en oeuvre, et procede de pilotage d'un reacteur nucleaire |
Publications (1)
Publication Number | Publication Date |
---|---|
DE3869800D1 true DE3869800D1 (de) | 1992-05-14 |
Family
ID=9347449
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
DE8888101234T Expired - Lifetime DE3869800D1 (de) | 1987-01-30 | 1988-01-28 | Methode zur bestimmung der alarmschwelle des verhaeltnisses der kritischen aufheizung und anlage zur durchfuehrung der methode. |
Country Status (8)
Country | Link |
---|---|
US (1) | US4836973A (de) |
EP (1) | EP0277594B1 (de) |
JP (1) | JPS63193090A (de) |
KR (1) | KR960013028B1 (de) |
CN (1) | CN1015680B (de) |
DE (1) | DE3869800D1 (de) |
ES (1) | ES2031164T3 (de) |
FR (1) | FR2610446B1 (de) |
Families Citing this family (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2619950B1 (fr) * | 1987-08-24 | 1991-11-29 | Framatome Sa | Procede de protection d'un reacteur nucleaire a eau pressurisee contre les defaillances du dispositif d'arret d'urgence |
FR2665013B1 (fr) * | 1990-07-17 | 1992-09-18 | Framatome Sa | Procede de protection d'un reacteur nucleaire en cas d'elevation de sa charge. |
CN104425047B (zh) * | 2013-09-11 | 2018-08-21 | 中国广核集团有限公司 | 一种核电站中防止堆芯热功率超限值的方法 |
FR3069694A1 (fr) * | 2017-07-28 | 2019-02-01 | Areva Np | Procede de surveillance d'un coeur nucleaire comprenant une relaxation d'un seuil, programme, support et reacteur nucleaire associes |
FR3075449B1 (fr) | 2017-12-18 | 2020-01-10 | Areva Np | Procede de determination d'au moins une valeur limite d'au moins un parametre de fonctionnement d'un reacteur nucleaire, programme d'ordinateur et systeme electronique associes |
Family Cites Families (12)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3998693A (en) * | 1970-11-23 | 1976-12-21 | Combustion Engineering, Inc. | Thermal margin control |
US4330367A (en) * | 1973-05-22 | 1982-05-18 | Combustion Engineering, Inc. | System and process for the control of a nuclear power system |
US4318778A (en) * | 1973-05-22 | 1982-03-09 | Combustion Engineering, Inc. | Method and apparatus for controlling a nuclear reactor |
US4080251A (en) * | 1973-05-22 | 1978-03-21 | Combustion Engineering, Inc. | Apparatus and method for controlling a nuclear reactor |
US4075059A (en) * | 1976-04-28 | 1978-02-21 | Combustion Engineering, Inc. | Reactor power reduction system and method |
DE2735915C2 (de) * | 1977-08-10 | 1983-01-20 | Continental Gummi-Werke Ag, 3000 Hannover | Fahrzeugluftreifen für einspurige Fahrzeuge |
US4568513A (en) * | 1982-07-26 | 1986-02-04 | The Babcock & Wilcox Company | Reactor power peaking information display |
US4637911A (en) * | 1984-07-24 | 1987-01-20 | Massachusetts Institute Of Technology | Apparatus and method for closed-loop control of reactor power |
US4707324A (en) * | 1984-12-27 | 1987-11-17 | Westinghouse Electric Corp. | Controlling the response of a pressurized water reactor to rapid fluctuations in load |
US4699749A (en) * | 1985-05-07 | 1987-10-13 | Westinghouse Electric Corp. | Controlling a nuclear reactor with dropped control rods |
US4711753A (en) * | 1986-03-19 | 1987-12-08 | Westinghouse Electric Corp. | Calibration of a nuclear reactor core parameter predictor |
US4738818A (en) * | 1986-09-29 | 1988-04-19 | Westinghouse Electric Corp. | Feedwater control in a PWR following reactor trip |
-
1987
- 1987-01-30 FR FR8701162A patent/FR2610446B1/fr not_active Expired - Lifetime
-
1988
- 1988-01-28 DE DE8888101234T patent/DE3869800D1/de not_active Expired - Lifetime
- 1988-01-28 ES ES198888101234T patent/ES2031164T3/es not_active Expired - Lifetime
- 1988-01-28 EP EP88101234A patent/EP0277594B1/de not_active Expired - Lifetime
- 1988-01-29 KR KR1019880000754A patent/KR960013028B1/ko not_active IP Right Cessation
- 1988-01-29 US US07/150,269 patent/US4836973A/en not_active Expired - Fee Related
- 1988-01-29 JP JP63019470A patent/JPS63193090A/ja active Pending
- 1988-01-30 CN CN88101339A patent/CN1015680B/zh not_active Expired
Also Published As
Publication number | Publication date |
---|---|
US4836973A (en) | 1989-06-06 |
FR2610446B1 (fr) | 1991-11-29 |
CN88101339A (zh) | 1988-08-10 |
EP0277594B1 (de) | 1992-04-08 |
KR960013028B1 (ko) | 1996-09-25 |
EP0277594A1 (de) | 1988-08-10 |
KR880009385A (ko) | 1988-09-15 |
FR2610446A1 (fr) | 1988-08-05 |
CN1015680B (zh) | 1992-02-26 |
ES2031164T3 (es) | 1992-12-01 |
JPS63193090A (ja) | 1988-08-10 |
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Legal Events
Date | Code | Title | Description |
---|---|---|---|
8364 | No opposition during term of opposition | ||
8339 | Ceased/non-payment of the annual fee |