ES458261A1 - Procedimiento para reducir rapidamente la potencia de un re-actor nuclear. - Google Patents

Procedimiento para reducir rapidamente la potencia de un re-actor nuclear.

Info

Publication number
ES458261A1
ES458261A1 ES77458261A ES458261A ES458261A1 ES 458261 A1 ES458261 A1 ES 458261A1 ES 77458261 A ES77458261 A ES 77458261A ES 458261 A ES458261 A ES 458261A ES 458261 A1 ES458261 A1 ES 458261A1
Authority
ES
Spain
Prior art keywords
reactor
power reduction
accelerated
occurrence
rod insertion
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
Application number
ES77458261A
Other languages
English (en)
Spanish (es)
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Combustion Engineering Inc
Original Assignee
Combustion Engineering Inc
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Combustion Engineering Inc filed Critical Combustion Engineering Inc
Publication of ES458261A1 publication Critical patent/ES458261A1/es
Expired legal-status Critical Current

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
    • G21D3/04—Safety arrangements
    • 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)
  • Business, Economics & Management (AREA)
  • Emergency Management (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
ES77458261A 1976-04-28 1977-04-28 Procedimiento para reducir rapidamente la potencia de un re-actor nuclear. Expired ES458261A1 (es)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US05/681,101 US4075059A (en) 1976-04-28 1976-04-28 Reactor power reduction system and method

Publications (1)

Publication Number Publication Date
ES458261A1 true ES458261A1 (es) 1978-04-01

Family

ID=24733830

Family Applications (1)

Application Number Title Priority Date Filing Date
ES77458261A Expired ES458261A1 (es) 1976-04-28 1977-04-28 Procedimiento para reducir rapidamente la potencia de un re-actor nuclear.

Country Status (6)

Country Link
US (1) US4075059A (enExample)
JP (1) JPS52132295A (enExample)
DE (1) DE2715433B2 (enExample)
ES (1) ES458261A1 (enExample)
FR (1) FR2349922A1 (enExample)
GB (1) GB1577261A (enExample)

Families Citing this family (33)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2395572A1 (fr) * 1977-06-23 1979-01-19 Framatome Sa Procede de controle des effets de reactivite dus aux variations de puissance dans les reacteurs nucleaires a eau pressurisee
US4399095A (en) * 1977-12-16 1983-08-16 Westinghouse Electric Corp. Protection and control system for a nuclear reactor
US4308099A (en) * 1979-01-22 1981-12-29 The Babcock & Wilcox Company Nuclear reactor safety system
JPS5722587A (en) * 1980-07-17 1982-02-05 Tokyo Shibaura Electric Co Nuclear reactor power control device
US4386048A (en) * 1980-11-24 1983-05-31 Combustion Engineering, Inc. Variable overlap control
US4459259A (en) * 1982-06-29 1984-07-10 The United States Of America As Represented By The United States Department Of Energy Digital computer operation of a nuclear reactor
JPS5944689A (ja) * 1982-09-06 1984-03-13 株式会社日立製作所 沸騰水型原子炉の運転制御方法
FR2542493B1 (fr) * 1983-03-11 1985-12-27 Framatome Sa Dispositif de determination rapide et precise de la puissance d'un reacteur nucleaire a eau sous pression
FR2544907B1 (fr) * 1983-04-21 1985-07-19 Framatome Sa Procede de reglage automatique de la teneur en bore soluble de l'eau de refroidissement d'un reacteur nucleaire a eau sous pression
FR2546329B1 (fr) * 1983-05-19 1985-08-23 Framatome Sa Procede de detection des variations de la reactivite du coeur d'un reacteur nucleaire a eau sous pression et dispositif de mise en oeuvre de ce procede
US4637910A (en) * 1984-01-20 1987-01-20 Westinghouse Electric Corp. Method and apparatus for continuous on-line synthesis of power distribution in a nuclear reactor core
JPS61118692A (ja) * 1984-11-13 1986-06-05 ウエスチングハウス　エレクトリック　コ−ポレ−ション 加圧水型原子炉発電システムの運転方法
US4717528A (en) * 1985-02-19 1988-01-05 Westinghouse Electric Corp. Control rod control system
US4777009A (en) * 1986-06-30 1988-10-11 Combustion Engineering, Inc. Automatic steam generator feedwater control over full power range
FR2610446B1 (fr) * 1987-01-30 1991-11-29 Framatome Sa 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
FR2611302B1 (fr) * 1987-02-20 1989-04-07 Framatome Sa Procede de detection de la chute d'un element antireactif dans le reacteur d'une centrale nucleaire et centrale protegee contre une telle chute
FR2614461B1 (fr) * 1987-04-24 1989-06-09 Commissariat Energie Atomique Procede de controle d'un reacteur nucleaire
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
JPH07119827B2 (ja) * 1987-12-25 1995-12-20 三菱電機株式会社 原子炉出力分布の測定装置
FR2629624B1 (fr) * 1988-04-05 1990-11-16 Framatome Sa Procede de determination et d'evaluation de la capacite de retour en puissance d'un reacteur nucleaire a eau pressurisee
FR2629623B1 (fr) * 1988-04-05 1990-11-16 Framatome Sa Procede de determination et d'evaluation de la marge d'arret d'urgence d'un reacteur nucleaire a eau pressurisee
US4912732A (en) * 1988-04-14 1990-03-27 Combustion Engineering, Inc. Automatic steam generator control at low power
KR19980024802A (ko) * 1996-09-30 1998-07-06 존 에이치. 물홀랜드 펌프 선택 논리 회로
US6091790A (en) * 1998-05-08 2000-07-18 Combustion Engineering, Inc. Control element assembly position system
JP3810615B2 (ja) * 2000-05-18 2006-08-16 三菱重工業株式会社 タービンの遠隔制御方法及びシステム
US8109759B2 (en) * 2006-03-29 2012-02-07 Fives North America Combustion, Inc. Assured compliance mode of operating a combustion system
JP4901631B2 (ja) * 2007-07-30 2012-03-21 原子燃料工業株式会社 ドップラー反応度係数の測定方法
US20170263342A1 (en) * 2016-03-10 2017-09-14 Westinghouse Electric Company Llc Real-time reactor coolant system boron concentration monitor utilizing an ultrasonic spectroscpopy system
RU2673448C1 (ru) * 2017-12-06 2018-11-27 Российская Федерация, от имени которой выступает Государственная корпорация по атомной энергии "Росатом" (Госкорпорация "Росатом") Устройство для защиты ядерного реактора по превышению мощности
CN111724920A (zh) * 2020-05-21 2020-09-29 岭东核电有限公司 核电站反应堆寿期末降功率的轴向功率偏差控制方法
CN112233824A (zh) * 2020-09-08 2021-01-15 中广核研究院有限公司 核电反应堆堆芯控制棒叠步运动方法及核电反应堆堆芯
CN121171661A (zh) * 2025-11-20 2025-12-19 上海核工程研究设计院股份有限公司 基于快速降功率系统的反应堆控制方法、电子设备及介质
CN121148748A (zh) * 2025-11-20 2025-12-16 上海核工程研究设计院股份有限公司 基于调节棒组的快速降功率方法、系统和压水堆

Family Cites Families (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3267002A (en) * 1965-01-28 1966-08-16 Jr Leonard W Fromm Method for controlling a nuclear reactor
US3423285A (en) * 1966-01-27 1969-01-21 Westinghouse Electric Corp Temperature control for a nuclear reactor
US3565760A (en) * 1967-10-23 1971-02-23 Gen Electric Nuclear reactor power monitor system
US3578562A (en) * 1968-10-23 1971-05-11 Combustion Eng Method and apparatus for continuous monitoring and control of neutron absorption properties of chemical shim
US3933580A (en) * 1971-03-08 1976-01-20 Siemens Aktiengesellschaft Limit regulation system for pressurized water nuclear reactors
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

Also Published As

Publication number Publication date
US4075059A (en) 1978-02-21
DE2715433B2 (de) 1979-07-12
FR2349922B1 (enExample) 1980-05-09
GB1577261A (en) 1980-10-22
DE2715433A1 (de) 1977-11-10
JPS52132295A (en) 1977-11-05
FR2349922A1 (fr) 1977-11-25

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Legal Events

Date Code Title Description
FD1A Patent lapsed

Effective date: 19970612