SE417259B - Forfarande for utstreckning av driften av ett kernkraftverks tryckvattenreaktor utover slutet av reaktorns normala brenslecykel - Google Patents
Forfarande for utstreckning av driften av ett kernkraftverks tryckvattenreaktor utover slutet av reaktorns normala brenslecykelInfo
- Publication number
- SE417259B SE417259B SE7414948A SE7414948A SE417259B SE 417259 B SE417259 B SE 417259B SE 7414948 A SE7414948 A SE 7414948A SE 7414948 A SE7414948 A SE 7414948A SE 417259 B SE417259 B SE 417259B
- Authority
- SE
- Sweden
- Prior art keywords
- reactor
- procedure
- power plant
- nuclear power
- required water
- Prior art date
Links
Classifications
-
- 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
- G21D3/12—Regulation of any parameters in the plant by adjustment of the reactor in response only to changes in engine demand
- G21D3/16—Varying reactivity
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/32—Control of nuclear reaction by varying flow of coolant through the core by adjusting the coolant or moderator temperature
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
-
- 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)
- Control Of Turbines (AREA)
- Engine Equipment That Uses Special Cycles (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
US05/419,746 US4000037A (en) | 1973-11-28 | 1973-11-28 | Reactor-turbine control for low steam pressure operation in a pressurized water reactor |
Publications (1)
Publication Number | Publication Date |
---|---|
SE417259B true SE417259B (sv) | 1981-03-02 |
Family
ID=23663578
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
SE7414948A SE417259B (sv) | 1973-11-28 | 1974-11-28 | Forfarande for utstreckning av driften av ett kernkraftverks tryckvattenreaktor utover slutet av reaktorns normala brenslecykel |
Country Status (12)
Country | Link |
---|---|
US (1) | US4000037A (sv) |
JP (1) | JPS5531920B2 (sv) |
BE (1) | BE822679A (sv) |
CA (1) | CA1022352A (sv) |
CH (1) | CH587539A5 (sv) |
DE (1) | DE2452151A1 (sv) |
ES (1) | ES432355A1 (sv) |
FR (1) | FR2252632B1 (sv) |
GB (1) | GB1456297A (sv) |
IT (1) | IT1026519B (sv) |
NL (1) | NL7414168A (sv) |
SE (1) | SE417259B (sv) |
Families Citing this family (13)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4263654A (en) * | 1976-09-28 | 1981-04-21 | Hitachi, Ltd. | System for determining the normal operating value of power plant data |
US4222822A (en) * | 1977-01-19 | 1980-09-16 | Westinghouse Electric Corp. | Method for operating a nuclear reactor to accommodate load follow while maintaining a substantially constant axial power distribution |
US4104117A (en) * | 1977-02-07 | 1978-08-01 | Westinghouse Electric Corp. | Nuclear reactor power generation |
US4290850A (en) * | 1978-09-01 | 1981-09-22 | Hitachi, Ltd. | Method and apparatus for controlling feedwater flow to steam generating device |
US4336105A (en) * | 1979-12-05 | 1982-06-22 | Westinghouse Electric Corp. | Nuclear power plant steam system |
JPH01168689U (sv) * | 1988-05-20 | 1989-11-28 | ||
US5215704A (en) * | 1991-06-24 | 1993-06-01 | Electric Power Research Institute | Method and apparatus for in situ testing of heat exchangers |
US9091182B2 (en) * | 2010-12-20 | 2015-07-28 | Invensys Systems, Inc. | Feedwater heater control system for improved rankine cycle power plant efficiency |
US9316122B2 (en) | 2010-12-20 | 2016-04-19 | Invensys Systems, Inc. | Feedwater heater control system for improved Rankine cycle power plant efficiency |
US9297278B2 (en) * | 2011-05-27 | 2016-03-29 | General Electric Company | Variable feedwater heater cycle |
US9328633B2 (en) | 2012-06-04 | 2016-05-03 | General Electric Company | Control of steam temperature in combined cycle power plant |
FR3008220B1 (fr) * | 2013-07-04 | 2015-08-14 | Areva Np | Procede de pilotage en prolongation de cycle d'un reacteur nucleaire a eau pressurisee |
RU2680380C1 (ru) * | 2017-12-01 | 2019-02-20 | Рашид Зарифович Аминов | Способ повышения мощности и безопасности энергоблока АЭС с реактором типа ВВЭР на основе теплового аккумулирования |
Family Cites Families (10)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3061533A (en) * | 1958-05-12 | 1962-10-30 | United Eng & Constructors Inc | Control means for a boiling water nuclear reactor power system |
NL291393A (sv) * | 1963-03-20 | |||
CH405517A (de) * | 1963-05-17 | 1966-01-15 | Sulzer Ag | Verfahren und Vorrichtung zur Regelung einer Reaktoranlage |
US3197380A (en) * | 1964-09-16 | 1965-07-27 | Dahlgren Jons Arthur | Power plant for superheating the steam originating from the steam generator of a nuclear pressurized water reactor |
FR1527695A (fr) * | 1966-02-03 | 1968-06-07 | Stein & Roubaix S A | Installation thermique |
US3660229A (en) * | 1969-02-07 | 1972-05-02 | Gen Electric Canada | Reactor control system |
BE758888A (fr) * | 1969-11-18 | 1971-05-13 | Westinghouse Electric Corp | Systeme de reactivation d'une boucle de reacteur nucleaire |
US3700552A (en) * | 1969-11-19 | 1972-10-24 | Babcock & Wilcox Co | Nuclear reactor with means for adjusting coolant temperature |
BE767821R (fr) * | 1971-06-02 | 1971-10-18 | Sulzer Ag | Centrale nucleaire a cuve sous |
US3778347A (en) * | 1971-09-27 | 1973-12-11 | Giras T | Method and system for operating a boiling water reactor-steam turbine plant preferably under digital computer control |
-
1973
- 1973-11-28 US US05/419,746 patent/US4000037A/en not_active Expired - Lifetime
-
1974
- 1974-10-28 CA CA212,458A patent/CA1022352A/en not_active Expired
- 1974-10-30 NL NL7414168A patent/NL7414168A/xx not_active Application Discontinuation
- 1974-11-02 DE DE19742452151 patent/DE2452151A1/de not_active Withdrawn
- 1974-11-15 CH CH1528874A patent/CH587539A5/xx not_active IP Right Cessation
- 1974-11-18 GB GB4974474A patent/GB1456297A/en not_active Expired
- 1974-11-26 IT IT29837/74A patent/IT1026519B/it active
- 1974-11-27 ES ES432355A patent/ES432355A1/es not_active Expired
- 1974-11-27 BE BE1006299A patent/BE822679A/xx unknown
- 1974-11-27 FR FR7438895A patent/FR2252632B1/fr not_active Expired
- 1974-11-27 JP JP13565874A patent/JPS5531920B2/ja not_active Expired
- 1974-11-28 SE SE7414948A patent/SE417259B/sv unknown
Also Published As
Publication number | Publication date |
---|---|
BE822679A (fr) | 1975-05-27 |
FR2252632B1 (sv) | 1977-11-04 |
JPS5084731A (sv) | 1975-07-08 |
JPS5531920B2 (sv) | 1980-08-21 |
DE2452151A1 (de) | 1975-06-05 |
CH587539A5 (sv) | 1977-05-13 |
US4000037A (en) | 1976-12-28 |
CA1022352A (en) | 1977-12-13 |
FR2252632A1 (sv) | 1975-06-20 |
IT1026519B (it) | 1978-10-20 |
NL7414168A (nl) | 1975-05-30 |
GB1456297A (en) | 1976-11-24 |
ES432355A1 (es) | 1977-06-16 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
SE7409170L (sv) | Forfarande for automatisk overvakning av effektfordelningen i en kernreaktor med rorliga i kernan anbragta detektorer. | |
SE7705457L (sv) | Termiskt kraftverk forbundet med en anleggning for avsaltning av havsvatten | |
SE7801365L (sv) | Syrsystem for matarvattnet vid ett kernkraftverk | |
SE411970B (sv) | Brenslestav avsedd for en kernreaktor | |
BE816789A (fr) | Installation de transfert de combustible pour reacteur nucleaire | |
SE417259B (sv) | Forfarande for utstreckning av driften av ett kernkraftverks tryckvattenreaktor utover slutet av reaktorns normala brenslecykel | |
SE389217B (sv) | Serskilt for en kernreaktors herd avsett tryckkerl | |
IT1118619B (it) | Assemblaggio combustibile facilmente smontabile per reattore nucleare | |
BE841175A (fr) | Systeme de reglage d'un reacteur de centrale nucleaire | |
SE402664B (sv) | Brenslestavknippe for en kernreaktor | |
BE818024A (fr) | Reacteur nucleaire a cuve indeformable | |
BR7400476D0 (pt) | Um gerador de vapor aperfeicoado de reator nuclear compacto | |
FR2333200A1 (fr) | Perfectionnement a l'alimentation en eau d'un generateur de vapeur destine a une centrale nucleaire | |
FR2283520A1 (fr) | Reacteur a moderateur en eau | |
FR2345665A1 (fr) | Generateur de vapeur pour reacteurs nucleaires a eau pressurisee | |
ES518712A0 (es) | Procedimiento para controlar la salida de potencia de un reactor nuclear. | |
FR2284170A1 (fr) | Structure de reduction des courants de convection a l'interieur de la cuve d'un reacteur nucleaire | |
BE822492A (fr) | Procede d'utilisation de l'energie calorifique d'un reacteur nucleaire a haute temperature en gazeifiant des matieres carbonees solides | |
IT1034050B (it) | Sistema di regolazione di un reattore nucleare | |
FR2280179A1 (fr) | Reacteur nucleaire a refroidissement par l'eau | |
FR2299703A1 (fr) | Reacteur nucleaire a refroidissement par l'eau | |
BE818026A (fr) | Installation de reacteur nucleaire a securite d'eclatement | |
AT342727B (de) | Kernkraftwerk mit einem dampferzeuger | |
BE822282A (fr) | Generateur de vapeur pour reacteur nucleaire | |
SE396834B (sv) | Forfarande for simulering av driften av en kernreaktor |