CA1127778A - Nuclear reactor safety system - Google Patents
Nuclear reactor safety systemInfo
- Publication number
- CA1127778A CA1127778A CA334,051A CA334051A CA1127778A CA 1127778 A CA1127778 A CA 1127778A CA 334051 A CA334051 A CA 334051A CA 1127778 A CA1127778 A CA 1127778A
- Authority
- CA
- Canada
- Prior art keywords
- reactor
- computing
- safety system
- parameter
- station
- 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
Links
- 230000006870 function Effects 0.000 claims abstract description 19
- 230000014509 gene expression Effects 0.000 claims description 12
- 238000004364 calculation method Methods 0.000 claims description 8
- 230000004907 flux Effects 0.000 claims description 4
- 239000012809 cooling fluid Substances 0.000 claims description 2
- 238000012360 testing method Methods 0.000 description 3
- 238000000034 method Methods 0.000 description 2
- 238000012986 modification Methods 0.000 description 2
- 230000004048 modification Effects 0.000 description 2
- 238000012552 review Methods 0.000 description 2
- 208000036366 Sensation of pressure Diseases 0.000 description 1
- 230000008901 benefit Effects 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 229940000425 combination drug Drugs 0.000 description 1
- 238000002474 experimental method Methods 0.000 description 1
- 238000005259 measurement Methods 0.000 description 1
- 230000001105 regulatory effect Effects 0.000 description 1
- 230000003252 repetitive effect Effects 0.000 description 1
Classifications
-
- 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
- G21D3/04—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)
- Business, Economics & Management (AREA)
- Emergency Management (AREA)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Safety Devices In Control Systems (AREA)
Applications Claiming Priority (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| US06/005,123 US4308099A (en) | 1979-01-22 | 1979-01-22 | Nuclear reactor safety system |
| US5,123 | 1979-01-22 |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CA1127778A true CA1127778A (en) | 1982-07-13 |
Family
ID=21714299
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CA334,051A Expired CA1127778A (en) | 1979-01-22 | 1979-08-17 | Nuclear reactor safety system |
Country Status (10)
| Country | Link |
|---|---|
| US (1) | US4308099A (enExample) |
| JP (1) | JPS5599097A (enExample) |
| CA (1) | CA1127778A (enExample) |
| CH (1) | CH643673A5 (enExample) |
| DE (1) | DE2929508C2 (enExample) |
| ES (1) | ES8101805A1 (enExample) |
| FR (1) | FR2447080A1 (enExample) |
| GB (1) | GB2040522B (enExample) |
| IT (1) | IT1123844B (enExample) |
| MX (1) | MX6481E (enExample) |
Families Citing this family (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2494877A1 (fr) * | 1980-11-26 | 1982-05-28 | Commissariat Energie Atomique | Systeme logique de securite pour declencher l'action de protection d'un actionneur de surete |
| US4427620A (en) | 1981-02-04 | 1984-01-24 | Westinghouse Electric Corp. | Nuclear reactor power supply |
| FR2518288A1 (fr) * | 1981-12-11 | 1983-06-17 | Commissariat Energie Atomique | Dispositif de declenchement d'un actionneur de surete |
| GB2177832B (en) * | 1985-07-01 | 1989-07-19 | Charles Hoai Chi | Method and apparatus for protecting press from being damaged by overload conditions |
| US5112565A (en) * | 1990-01-03 | 1992-05-12 | Ball Russell M | Nuclear reactor multi-state digital control using digital topology |
| FR2665013B1 (fr) * | 1990-07-17 | 1992-09-18 | Framatome Sa | Procede de protection d'un reacteur nucleaire en cas d'elevation de sa charge. |
| FR2665014B1 (fr) * | 1990-07-17 | 1992-09-18 | Framatome Sa | Procede et dispositif de protection d'un reacteur nucleaire. |
Family Cites Families (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| BE561894A (enExample) * | 1956-10-26 | |||
| US3202804A (en) * | 1961-08-31 | 1965-08-24 | North American Aviation Inc | Method and apparatus for monitoring the operation of a system |
| US3423285A (en) * | 1966-01-27 | 1969-01-21 | Westinghouse Electric Corp | Temperature control for a nuclear reactor |
| US3752735A (en) * | 1970-07-16 | 1973-08-14 | Combustion Eng | Instrumentation for nuclear reactor core power measurements |
| JPS5122591B1 (enExample) * | 1970-11-16 | 1976-07-10 | ||
| 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 |
| US4080251A (en) * | 1973-05-22 | 1978-03-21 | Combustion Engineering, Inc. | Apparatus and method for controlling a nuclear reactor |
| FR2303355A1 (fr) * | 1975-03-04 | 1976-10-01 | Commissariat Energie Atomique | Procede et dispositif de controle thermique du coeur d'un reacteur nucleaire |
| US4075059A (en) * | 1976-04-28 | 1978-02-21 | Combustion Engineering, Inc. | Reactor power reduction system and method |
-
1979
- 1979-01-22 US US06/005,123 patent/US4308099A/en not_active Expired - Lifetime
- 1979-07-20 DE DE2929508A patent/DE2929508C2/de not_active Expired
- 1979-08-03 GB GB7927092A patent/GB2040522B/en not_active Expired
- 1979-08-17 CA CA334,051A patent/CA1127778A/en not_active Expired
- 1979-09-19 CH CH844979A patent/CH643673A5/de not_active IP Right Cessation
- 1979-10-11 MX MX798435U patent/MX6481E/es unknown
- 1979-10-15 IT IT26494/79A patent/IT1123844B/it active
- 1979-10-15 ES ES485030A patent/ES8101805A1/es not_active Expired
- 1979-11-06 JP JP14287479A patent/JPS5599097A/ja active Pending
- 1979-11-27 FR FR7929119A patent/FR2447080A1/fr active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| DE2929508C2 (de) | 1984-07-19 |
| CH643673A5 (de) | 1984-06-15 |
| ES485030A0 (es) | 1980-12-16 |
| MX6481E (es) | 1985-06-13 |
| FR2447080B1 (enExample) | 1983-04-22 |
| US4308099A (en) | 1981-12-29 |
| JPS5599097A (en) | 1980-07-28 |
| FR2447080A1 (fr) | 1980-08-14 |
| IT1123844B (it) | 1986-04-30 |
| IT7926494A0 (it) | 1979-10-15 |
| ES8101805A1 (es) | 1980-12-16 |
| DE2929508A1 (de) | 1980-07-24 |
| GB2040522A (en) | 1980-08-28 |
| GB2040522B (en) | 1983-02-09 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| EP1057189B1 (en) | Nuclear reaction protection system | |
| US6167547A (en) | Automatic self-test system utilizing multi-sensor, multi-channel redundant monitoring and control circuits | |
| CA1127778A (en) | Nuclear reactor safety system | |
| JPH11264887A (ja) | 原子炉核計装システム、このシステムを備えた原子炉出力分布監視システムおよび原子炉出力分布監視方法 | |
| US3752735A (en) | Instrumentation for nuclear reactor core power measurements | |
| WO1988006796A1 (en) | Reactor control system verification | |
| US4333797A (en) | Reactor power control apparatus | |
| CA1146285A (en) | Nuclear reactor safety system | |
| CN106024078A (zh) | 一种诊断反应堆中子探测器失效的方法 | |
| Lin et al. | Implementation of a built-in self-test for nuclear power plant FPGA-based safety-critical control systems | |
| KR830001225B1 (ko) | 원자로 안전시스템(system) | |
| Ning et al. | Construction and evaluation of fault detection network for signal validation | |
| Wang et al. | Verification and validation optimization method for signal quality bits in digital control system application software of nuclear power plant | |
| Ray et al. | On-line fault diagnosis in a nuclear reactor by sequential testing | |
| JP2001042083A (ja) | 炉内中性子束計測装置の自動校正装置 | |
| KR820002371B1 (ko) | 원자로 안전장치 | |
| JPS58134313A (ja) | プラント異常診断装置 | |
| Johnson et al. | Validating data from instruments in harsh environments: the designer's dilemma | |
| Benoni et al. | Malfunction detection in a PWR nuclear plant | |
| KR20230007026A (ko) | 원자력발전소의 공통원인 고장 감지 장치 및 이의 동작 방법 | |
| Uhrig et al. | Integration of artificial intelligence systems for nuclear power plant surveillance and diagnostics | |
| JPH02231597A (ja) | 原子炉出力監視装置 | |
| Ho et al. | Use of operational data for the validation of the SOPHT thermal-hydraulic code | |
| Gourdon et al. | The detection of anomalies in fast reactor cores | |
| Ombrellaro et al. | Evaluation of MSM for assessing subcritical reactivities in FFTF |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| MKEX | Expiry |