GB1476939A – System and process for the control of a nuclear power system
– Google Patents
GB1476939A – System and process for the control of a nuclear power system
– Google Patents
System and process for the control of a nuclear power system
Info
Publication number
GB1476939A
GB1476939A
GB2215774A
GB2215774A
GB1476939A
GB 1476939 A
GB1476939 A
GB 1476939A
GB 2215774 A
GB2215774 A
GB 2215774A
GB 2215774 A
GB2215774 A
GB 2215774A
GB 1476939 A
GB1476939 A
GB 1476939A
Authority
GB
United Kingdom
Prior art keywords
nuclear power
control
violation
controlling
power system
Prior art date
1973-05-22
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
GB2215774A
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.)
1973-05-22
Filing date
1974-05-17
Publication date
1977-06-16
1974-05-17
Application filed by Combustion Engineering Inc
filed
Critical
Combustion Engineering Inc
1977-06-16
Publication of GB1476939A
publication
Critical
patent/GB1476939A/en
Status
Expired
legal-status
Critical
Current
Links
Espacenet
Global Dossier
Discuss
Classifications
G—PHYSICS
G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
G21D—NUCLEAR POWER PLANT
G21D3/00—Control of nuclear power plant
G21D3/001—Computer implemented control
G—PHYSICS
G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
G21D—NUCLEAR POWER PLANT
G21D3/00—Control of nuclear power plant
G21D3/04—Safety arrangements
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
G21C17/108—Measuring reactor flux
G—PHYSICS
G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
G21C—NUCLEAR REACTORS
G21C7/00—Control of nuclear reaction
G21C7/36—Control circuits
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
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
Abstract
1476939 Controlling nuclear reactors COMBUSTION ENG Inc 17 May 1974 [22 May 1973] 22157/74 Heading G6C The description relates to controlling the operation of a nuclear power generating system and is substantially the same as that of Specification 1,476,937 the claims relating to predicting the violation of a design limit, preventing the violation of the design limit, and calculating an operating limit for the system with a built in margin sufficient to allow time for the prediction and prevention to be effective.
GB2215774A
1973-05-22
1974-05-17
System and process for the control of a nuclear power system
Expired
GB1476939A
(en)
Applications Claiming Priority (1)
Application Number
Priority Date
Filing Date
Title
US05/362,697
US4330367A
(en)
1973-05-22
1973-05-22
System and process for the control of a nuclear power system
Publications (1)
Publication Number
Publication Date
GB1476939A
true
GB1476939A
(en)
1977-06-16
Family
ID=23427160
Family Applications (1)
Application Number
Title
Priority Date
Filing Date
GB2215774A
Expired
GB1476939A
(en)
1973-05-22
1974-05-17
System and process for the control of a nuclear power system
Country Status (3)
Country
Link
US
(1)
US4330367A
(en)
CA
(1)
CA1017077A
(en)
GB
(1)
GB1476939A
(en)
Cited By (3)
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Assignee
Title
GB2142758A
(en)
*
1983-06-10
1985-01-23
Toshiba Kk
Method and system for diagnosing a thermal power plant system
GB2177832A
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*
1985-07-01
1987-01-28
Charles Hoai Chi
Method and apparatus for protecting press from being damaged by overload conditions
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2020-05-25
2020-08-25
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Method for calculating thermodynamic hydraulic power of annular fuel reactor core under serious accident
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1981-12-07
1984-10-23
The Babcock & Wilcox Company
Nuclear power plant feedwater controller design
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1982-07-16
1984-01-24
株式会社東芝
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1982-07-27
1985-05-14
General Electric Company
Self-test subsystem for nuclear reactor protection system
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1982-09-16
1986-12-30
Combustion Engineering, Inc.
Nuclear plant safety evaluation system
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1983-04-19
1984-10-25
Kraftwerk Union AG, 4330 Mülheim
METHOD FOR MONITORING THE FATIGUE OF COMPONENTS, e.g. IN NUCLEAR POWER PLANTS
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1986-04-10
1988-09-27
Westinghouse Electric Corp.
Axial power distribution monitor and display using outputs from ex-core detectors and thermocouples
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1987-01-30
1991-11-29
Framatome Sa
METHOD FOR DETERMINING THE ALARM THRESHOLD OF THE CRITICAL WARMING RATIO, DEVICE FOR IMPLEMENTING IT, AND METHOD FOR DRIVING A NUCLEAR REACTOR
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1987-03-05
1988-11-08
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Westinghouse Electric Corp.
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1987-04-24
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Commissariat Energie Atomique
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1988-04-14
1990-03-27
Combustion Engineering, Inc.
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Westinghouse Electric Corp.
Thermocouple based control rod position indication system
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1988-11-28
1991-03-05
The Babcock & Wilcox Company
Real-time reactor coolant system pressure/temperature limit system
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1991-06-18
Westinghouse Electric Corp.
Reactor core model update system
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1992-06-24
1993-12-07
Westinghouse Electric Corp.
Nuclear reactor having a polyhedral primary shield and removable vessel insulation
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1992-08-01
1994-02-17
Siemens Aktiengesellschaft
Method and process control system for controlling, monitoring and regulating in particular complex industrial processes, such as for example in a nuclear power station
JPH06201884A
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*
1992-09-22
1994-07-22
Toshiba Corp
Reactor power monitor
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*
1994-07-21
1996-02-06
Westinghouse Electric Corporation
Method and a system for accurately calculating PWR power from excore detector currents corrected for changes in 3-D power distribution and coolant density
US6061412A
(en)
*
1995-10-05
2000-05-09
Westinghouse Electric Company Llc
Nuclear reaction protection system
US5912933A
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*
1997-12-04
1999-06-15
General Electric Company
Method and system for direct evaluation of operating limit minimum critical power ratios for boiling water reactors
US5881118A
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*
1997-12-23
1999-03-09
Combustion Engineering, Inc.
Core protection calculator input filter
US6091790A
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*
1998-05-08
2000-07-18
Combustion Engineering, Inc.
Control element assembly position system
US6748348B1
(en)
1999-12-30
2004-06-08
General Electric Company
Design method for nuclear reactor fuel management
US20030086520A1
(en)
*
2001-11-07
2003-05-08
Russell William Earl
System and method for continuous optimization of control-variables during operation of a nuclear reactor
US7087332B2
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*
2002-07-31
2006-08-08
Sustainable Energy Systems, Inc.
Power slope targeting for DC generators
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2002-09-19
2009-02-03
Global Nuclear Fuel – Americas, Llc
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*
2002-09-23
2004-01-06
Westinghouse Electric Company Llc
Method of operating a nuclear power plant at multiple power levels
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*
2002-10-21
2005-02-18
Framatome Anp
METHOD FOR DETERMINING A LIMIT VALUE OF AN OPERATING PARAMETER OF A NUCLEAR REACTOR, PROGRAM AND SUPPORT THEREFOR
US8041548B2
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2004-12-30
2011-10-18
Global Nuclear Fuels-Americas, LLC
Method and apparatus for evaluating a proposed solution to a constraint problem for a nuclear reactor involving channel deformation
US7620139B2
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*
2005-06-30
2009-11-17
Global Nuclear Fuel – Americas, Llc
Method of improving nuclear reactor performance during reactor core operation
US7808125B1
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2006-07-31
2010-10-05
Sustainable Energy Technologies
Scheme for operation of step wave power converter
US8842802B2
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*
2006-10-16
2014-09-23
Global Nuclear Fuel-Americas, Llc.
Fuel rods for nuclear reactor fuel assemblies and methods of manufacturing thereof
JP4616847B2
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*
2007-02-16
2011-01-19
三菱重工業株式会社
Steam system and control system and control method thereof
JP4699401B2
(en)
*
2007-02-20
2011-06-08
三菱重工業株式会社
Steam system control method and control apparatus
CN101790827B
(en)
*
2007-06-04
2013-06-12
可持续能源技术公司
Prediction scheme for step wave power converter and inductive inverter topology
US9443623B2
(en)
*
2009-04-16
2016-09-13
Terrapower, Llc
Nuclear fission reactor fuel assembly and system configured for controlled removal of a volatile fission product and heat released by a burn wave in a traveling wave nuclear fission reactor and method for same
US9704604B2
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*
2009-04-16
2017-07-11
Terrapower, Llc
Nuclear fission reactor fuel assembly and system configured for controlled removal of a volatile fission product and heat released by a burn wave in a traveling wave nuclear fission reactor and method for same
KR20110138285A
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*
2009-04-16
2011-12-26
시리트 엘엘씨
Controlled removal of a volatile fission product and heat released by a burn wave
US9159461B2
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*
2009-04-16
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Terrapower, Llc
Nuclear fission reactor fuel assembly and system configured for controlled removal of a volatile fission product
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2017-05-23
Terrapower, Llc
Nuclear fission reactor fuel assembly and system configured for controlled removal of a volatile fission product and heat released by a burn wave in a traveling wave nuclear fission reactor and method for same
JP5642460B2
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*
2010-09-03
2014-12-17
三菱重工業株式会社
Critical heat flux prediction device, critical heat flux prediction method, safety evaluation system, and core fuel evaluation monitoring system
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2012-01-09
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한국전력기술 주식회사
Methodology on reducing errors in determination of shape annealing function (saf) for ex-core detector of nuclear power plant using 3-dimensional monte carlo method
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한전원자력연료 주식회사
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PROCESS FOR OPERATING A NUCLEAR REACTOR WITH ONLINE RFTC CALCULATION, CORRESPONDING NUCLEAR REACTOR
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*
2019-11-13
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patent/US4330367A/en
not_active
Expired – Lifetime
1974
1974-05-08
CA
CA199,228A
patent/CA1017077A/en
not_active
Expired
1974-05-17
GB
GB2215774A
patent/GB1476939A/en
not_active
Expired
Cited By (5)
* Cited by examiner, † Cited by third party
Publication number
Priority date
Publication date
Assignee
Title
GB2142758A
(en)
*
1983-06-10
1985-01-23
Toshiba Kk
Method and system for diagnosing a thermal power plant system
US4630189A
(en)
*
1983-06-10
1986-12-16
Kabushiki Kaisha Toshiba
System for determining abnormal plant operation based on whiteness indexes
GB2177832A
(en)
*
1985-07-01
1987-01-28
Charles Hoai Chi
Method and apparatus for protecting press from being damaged by overload conditions
GB2177832B
(en)
*
1985-07-01
1989-07-19
Charles Hoai Chi
Method and apparatus for protecting press from being damaged by overload conditions
CN111581849A
(en)
*
2020-05-25
2020-08-25
中国原子能科学研究院
Method for calculating thermodynamic hydraulic power of annular fuel reactor core under serious accident
Also Published As
Publication number
Publication date
CA1017077A
(en)
1977-09-06
US4330367A
(en)
1982-05-18
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Legal Events
Date
Code
Title
Description
1977-10-26
PS
Patent sealed [section 19, patents act 1949]
1987-01-07
PCNP
Patent ceased through non-payment of renewal fee
