[go: up one dir, main page]

GB1341131A - Methods of operating nuclear reactors - Google Patents

Methods of operating nuclear reactors

Info

Publication number
GB1341131A
GB1341131A GB2186771A GB2186771A GB1341131A GB 1341131 A GB1341131 A GB 1341131A GB 2186771 A GB2186771 A GB 2186771A GB 2186771 A GB2186771 A GB 2186771A GB 1341131 A GB1341131 A GB 1341131A
Authority
GB
United Kingdom
Prior art keywords
bank
doppler
power
rods
load
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
GB2186771A
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.)
Siemens Corp
Original Assignee
Siemens Corp
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 Siemens Corp filed Critical Siemens Corp
Publication of GB1341131A publication Critical patent/GB1341131A/en
Expired legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C7/00Control of nuclear reaction
    • FMECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F15FLUID-PRESSURE ACTUATORS; HYDRAULICS OR PNEUMATICS IN GENERAL
    • F15BSYSTEMS ACTING BY MEANS OF FLUIDS IN GENERAL; FLUID-PRESSURE ACTUATORS, e.g. SERVOMOTORS; DETAILS OF FLUID-PRESSURE SYSTEMS, NOT OTHERWISE PROVIDED FOR
    • F15B11/00Servomotor systems without provision for follow-up action; Circuits therefor
    • F15B11/06Servomotor systems without provision for follow-up action; Circuits therefor involving features specific to the use of a compressible medium, e.g. air, steam
    • F15B11/064Servomotor systems without provision for follow-up action; Circuits therefor involving features specific to the use of a compressible medium, e.g. air, steam with devices for saving the compressible medium
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C7/00Control of nuclear reaction
    • G21C7/06Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
    • G21C7/08Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Plasma & Fusion (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Fluid Mechanics (AREA)
  • Mechanical Engineering (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

1341131 Controlling reactors SIEMENS AG 19 April 1971 [19 Feb 1970] 21867/71 Heading G6C In the power regulation of a pressurized water nuclear reactor, in particular in the control of load cycles, using a power control-rod bank, the compensation of the Doppler effect, occurring with load variations and caused by variation of the fuel temperature, is carried out by means of a Doppler control-rod bank, while the power control-rod bank has a constant entry depth. The rods of the power bank are generally inserted only into the upper region of the core, even if the desired power output is quite low. The number of rods in the Doppler bank, which may consist of a partial group of the power bank, is selected such that it fully enters the reactor core at the minimum load in order to compensate for the effects of the fuel temperature variation and in order that it should absorb uniformly over the entire core height. At larger partial loads, a smaller number of rods will be selected for the Doppler bank, which would fully enter the core for the larger partial loads also. Owing to the initially rising coolant temperature when the load is reduced, the control rods of the Doppler bank at first receive entry command to provide adequate rod effectiveness, accompanying entry ofthe control rods of the power bank being necessary since the Doppler bank works slowly. After adequate regulation of coolant temperature, the power bank receives upwards command to its former working position, while the Doppler bank alone takes over the compensation. On the load being restored, the Doppler bank returns to its full load position corresponding to the working position of the power bank. It is advantageous for the rods of the Doppler bank to be exchangeable at relatively long time intervals with the rods of the power bank to avoid long-term different burnup effects.
GB2186771A 1970-02-19 1971-04-19 Methods of operating nuclear reactors Expired GB1341131A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
DE2007564A DE2007564C3 (en) 1970-02-19 1970-02-19 Method for regulating the output of a pressurized water reactor

Publications (1)

Publication Number Publication Date
GB1341131A true GB1341131A (en) 1973-12-19

Family

ID=5762680

Family Applications (1)

Application Number Title Priority Date Filing Date
GB2186771A Expired GB1341131A (en) 1970-02-19 1971-04-19 Methods of operating nuclear reactors

Country Status (6)

Country Link
JP (1) JPS5147837B1 (en)
BE (1) BE760096A (en)
DE (2) DE2007564C3 (en)
FR (1) FR2080625B1 (en)
GB (1) GB1341131A (en)
SE (1) SE363919B (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2013158701A1 (en) 2012-04-17 2013-10-24 Babcock & Wilcox Mpower, Inc. Extended operating cycle for pressurized water reactor
US10847276B2 (en) 2013-07-04 2020-11-24 Areva Np Method for controlling a pressurized water nuclear reactor during stretchout
CN113874957A (en) * 2019-05-07 2021-12-31 法玛通股份有限公司 Method for managing pressurized water nuclear reactor and corresponding management system

Families Citing this family (11)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE2337354C3 (en) * 1973-07-23 1981-06-25 Siemens AG, 1000 Berlin und 8000 München Device for regulating a pressurized water reactor with adjustable control rods
US4129475A (en) * 1975-07-31 1978-12-12 Westinghouse Electric Corp. Method of operating a nuclear reactor
DE2702077C2 (en) * 1977-01-19 1987-01-29 Hitachi, Ltd., Tokio/Tokyo Method for operating a boiling water or pressurized water reactor
FR2395572A1 (en) * 1977-06-23 1979-01-19 Framatome Sa PROCEDURE FOR MONITORING THE REACTIVITY EFFECTS DUE TO POWER VARIATIONS IN NUCLEAR REACTORS WITH PRESSURIZED WATER
FR2493582A1 (en) * 1980-11-03 1982-05-07 Framatome Sa METHOD FOR CONDUCTING A NUCLEAR REACTOR BY MOVING INTO THE HEART OF THIS REACTOR CONTROL BAR GROUPS
US4582669A (en) * 1982-01-08 1986-04-15 Westinghouse Electric Corp. Xenon suppression in a nuclear fueled electric power generation system
JPS5944689A (en) * 1982-09-06 1984-03-13 株式会社日立製作所 Method of controlling operation of bwr type reactor
FR2535509B1 (en) * 1982-10-27 1985-07-26 Framatome Sa PROCESS FOR OPERATING A MODERATE NUCLEAR REACTOR COOLED WITH LIGHT WATER
FR2535508B1 (en) * 1982-10-27 1986-07-04 Framatome Sa NUCLEAR REACTOR WITH IMPROVED YIELD
JPS59184895A (en) * 1983-04-06 1984-10-20 株式会社日立製作所 Method of controlling reactor load following-up
FR2901401A1 (en) * 2006-05-22 2007-11-23 Areva Np Sas Controlling operating parameters of a nuclear reactor core in pressurized water, comprises evaluating the actual values of operating parameters according to the acquired quantities of operating conditions of the reactor core

Cited By (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2013158701A1 (en) 2012-04-17 2013-10-24 Babcock & Wilcox Mpower, Inc. Extended operating cycle for pressurized water reactor
CN104508749A (en) * 2012-04-17 2015-04-08 巴布科克和威尔科克斯M能量股份有限公司 Extended operating cycle for pressurized water reactor
EP2839467A4 (en) * 2012-04-17 2015-12-23 Babcock & Wilcox Mpower Inc Extended operating cycle for pressurized water reactor
US10847276B2 (en) 2013-07-04 2020-11-24 Areva Np Method for controlling a pressurized water nuclear reactor during stretchout
CN113874957A (en) * 2019-05-07 2021-12-31 法玛通股份有限公司 Method for managing pressurized water nuclear reactor and corresponding management system
CN113874957B (en) * 2019-05-07 2024-05-24 法玛通股份有限公司 Method for managing a pressurized water nuclear reactor and corresponding management system

Also Published As

Publication number Publication date
DE2446247A1 (en) 1976-04-01
DE2007564C3 (en) 1973-10-18
DE2007564B2 (en) 1973-03-29
SE363919B (en) 1974-02-04
FR2080625B1 (en) 1976-05-28
FR2080625A1 (en) 1971-11-19
JPS5147837B1 (en) 1976-12-17
DE2007564A1 (en) 1971-09-02
BE760096A (en) 1971-05-17

Similar Documents

Publication Publication Date Title
GB1341131A (en) Methods of operating nuclear reactors
GB1069362A (en) Nuclear reactor
GB1366622A (en) Shipping container for radioactive material
ES440293A1 (en) Method of operating a nuclear reactor which maintains a substantially constant axial power distribution profile with changes in load
GB919171A (en) Drive means for control members in nuclear reactors
SE8500900D0 (en) METHOD FOR OPERATING BOILING WATER-TYPE ATOMIC POWER PLANT
GB904610A (en) Improvements in and relating to nuclear reactors
GB1132228A (en) Method and means for controlling a nuclear reactor
ES397143A1 (en) Thermal margin protection system for a nuclear reactor
GB915338A (en) A core for a thermal nuclear reactor
GB919637A (en) Nuclear power reactor
ES8403648A1 (en) Self rupturing gas moderator rod for a nuclear reactor
GB1209632A (en) Improvements in or relating to nuclear reactors
GB1480148A (en) Pressurised water reactor
GB1068526A (en) Nuclear reactor
GB1106488A (en) Nuclear-power sea-water conversion plant
GB1519836A (en) Gas-cooled nuclear power reactor and a process for controlling the reactor
GB1302685A (en)
GB1067136A (en) Thermal neutron reactor
ES483709A1 (en) Storage of spent fuel of bwr type reactor
GB1038087A (en) Improvements in or relating to nuclear reactors
GB1077375A (en) Improvements relating to power generation from nuclear reactor plant
GB925747A (en) Improvements in or relating to nuclear reactors
GB1075476A (en) Nuclear reactor and pressure vessel therefor
GB1066010A (en) Coupled reactors

Legal Events

Date Code Title Description
PS Patent sealed [section 19, patents act 1949]
PCNP Patent ceased through non-payment of renewal fee