RO134594B1 - Sistem de calcul central şi metodă de control a unei operaţii de întreţinere a unui reactor nuclear - Google Patents
Sistem de calcul central şi metodă de control a unei operaţii de întreţinere a unui reactor nuclear Download PDFInfo
- Publication number
- RO134594B1 RO134594B1 ROA201900931A RO201900931A RO134594B1 RO 134594 B1 RO134594 B1 RO 134594B1 RO A201900931 A ROA201900931 A RO A201900931A RO 201900931 A RO201900931 A RO 201900931A RO 134594 B1 RO134594 B1 RO 134594B1
- Authority
- RO
- Romania
- Prior art keywords
- equipment
- controller
- message
- reactor
- instruction
- Prior art date
Links
- 238000000034 method Methods 0.000 title claims description 112
- 238000012423 maintenance Methods 0.000 title claims description 29
- 238000004519 manufacturing process Methods 0.000 claims description 6
- 238000005259 measurement Methods 0.000 claims description 5
- 238000004891 communication Methods 0.000 description 146
- 230000008569 process Effects 0.000 description 35
- 239000000446 fuel Substances 0.000 description 27
- 230000006870 function Effects 0.000 description 24
- 238000010586 diagram Methods 0.000 description 19
- 230000033001 locomotion Effects 0.000 description 19
- 238000013461 design Methods 0.000 description 18
- 238000012544 monitoring process Methods 0.000 description 18
- 238000010276 construction Methods 0.000 description 16
- 230000000712 assembly Effects 0.000 description 15
- 238000000429 assembly Methods 0.000 description 15
- 238000005520 cutting process Methods 0.000 description 11
- 238000013500 data storage Methods 0.000 description 10
- 239000000463 material Substances 0.000 description 7
- 230000001681 protective effect Effects 0.000 description 7
- 230000001934 delay Effects 0.000 description 6
- 238000012795 verification Methods 0.000 description 6
- 238000012790 confirmation Methods 0.000 description 5
- 238000011900 installation process Methods 0.000 description 5
- 230000004044 response Effects 0.000 description 5
- 239000002826 coolant Substances 0.000 description 4
- 238000012772 sequence design Methods 0.000 description 4
- 238000007689 inspection Methods 0.000 description 3
- 238000009434 installation Methods 0.000 description 3
- 238000012545 processing Methods 0.000 description 3
- 238000003908 quality control method Methods 0.000 description 3
- 238000012552 review Methods 0.000 description 3
- 125000006850 spacer group Chemical group 0.000 description 3
- 230000000007 visual effect Effects 0.000 description 3
- IJGRMHOSHXDMSA-UHFFFAOYSA-N Atomic nitrogen Chemical compound N#N IJGRMHOSHXDMSA-UHFFFAOYSA-N 0.000 description 2
- CURLTUGMZLYLDI-UHFFFAOYSA-N Carbon dioxide Chemical compound O=C=O CURLTUGMZLYLDI-UHFFFAOYSA-N 0.000 description 2
- XLYOFNOQVPJJNP-ZSJDYOACSA-N Heavy water Chemical compound [2H]O[2H] XLYOFNOQVPJJNP-ZSJDYOACSA-N 0.000 description 2
- 229920004880 RTP PEK Polymers 0.000 description 2
- 230000009471 action Effects 0.000 description 2
- 230000008901 benefit Effects 0.000 description 2
- 239000003086 colorant Substances 0.000 description 2
- 230000008878 coupling Effects 0.000 description 2
- 238000010168 coupling process Methods 0.000 description 2
- 238000005859 coupling reaction Methods 0.000 description 2
- 230000003111 delayed effect Effects 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 239000007789 gas Substances 0.000 description 2
- 238000003780 insertion Methods 0.000 description 2
- 230000037431 insertion Effects 0.000 description 2
- 238000010030 laminating Methods 0.000 description 2
- 239000000203 mixture Substances 0.000 description 2
- 230000005855 radiation Effects 0.000 description 2
- 238000012502 risk assessment Methods 0.000 description 2
- 238000003860 storage Methods 0.000 description 2
- 230000001052 transient effect Effects 0.000 description 2
- 230000001755 vocal effect Effects 0.000 description 2
- YZCKVEUIGOORGS-OUBTZVSYSA-N Deuterium Chemical compound [2H] YZCKVEUIGOORGS-OUBTZVSYSA-N 0.000 description 1
- 229910000831 Steel Inorganic materials 0.000 description 1
- 229910052770 Uranium Inorganic materials 0.000 description 1
- 239000003570 air Substances 0.000 description 1
- 238000004458 analytical method Methods 0.000 description 1
- 239000001569 carbon dioxide Substances 0.000 description 1
- 229910002092 carbon dioxide Inorganic materials 0.000 description 1
- 239000000498 cooling water Substances 0.000 description 1
- 230000001419 dependent effect Effects 0.000 description 1
- 229910052805 deuterium Inorganic materials 0.000 description 1
- 238000011161 development Methods 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 238000011156 evaluation Methods 0.000 description 1
- 239000000835 fiber Substances 0.000 description 1
- 239000001307 helium Substances 0.000 description 1
- 229910052734 helium Inorganic materials 0.000 description 1
- SWQJXJOGLNCZEY-UHFFFAOYSA-N helium atom Chemical compound [He] SWQJXJOGLNCZEY-UHFFFAOYSA-N 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 229910052757 nitrogen Inorganic materials 0.000 description 1
- 239000003758 nuclear fuel Substances 0.000 description 1
- 238000002360 preparation method Methods 0.000 description 1
- 238000013349 risk mitigation Methods 0.000 description 1
- 230000011664 signaling Effects 0.000 description 1
- 239000010959 steel Substances 0.000 description 1
- 238000006467 substitution reaction Methods 0.000 description 1
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 description 1
- 238000012800 visualization Methods 0.000 description 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/04—Thermal reactors ; Epithermal reactors
- G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
- G21C1/14—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor
- G21C1/16—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor
- G21C1/18—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor coolant being pressurised
- G21C1/20—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor coolant being pressurised moderator being liquid, e.g. pressure-tube reactor
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/26—Arrangements for removing jammed or damaged fuel elements or control elements; Arrangements for moving broken parts thereof
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/017—Inspection or maintenance of pipe-lines or tubes in nuclear installations
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/14—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel characterised by their adaptation for use with horizontal channels in the reactor core
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/20—Arrangements for introducing objects into the pressure vessel; Arrangements for handling objects within the pressure vessel; Arrangements for removing objects from the pressure vessel
- G21C19/205—Interchanging of fuel elements in the core, i.e. fuel shuffling
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/001—Computer implemented control
-
- 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
- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- General Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Conveying And Assembling Of Building Elements In Situ (AREA)
- Manipulator (AREA)
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
RO202100323A RO135345A2 (ro) | 2017-06-23 | 2018-06-22 | Sisteme şi metode de comunicaţii pentru echipamentele reacto- rului nuclear |
Applications Claiming Priority (5)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
US201762524411P | 2017-06-23 | 2017-06-23 | |
US62/524411 | 2017-06-23 | ||
US201862646449P | 2018-03-22 | 2018-03-22 | |
US62/646449 | 2018-03-22 | ||
PCT/CA2018/050769 WO2018232525A1 (en) | 2017-06-23 | 2018-06-22 | COMMUNICATION SYSTEMS AND METHODS FOR NUCLEAR REACTOR TOOLS |
Publications (2)
Publication Number | Publication Date |
---|---|
RO134594A2 RO134594A2 (ro) | 2020-11-27 |
RO134594B1 true RO134594B1 (ro) | 2023-02-28 |
Family
ID=64735405
Family Applications (2)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
ROA201900931A RO134594B1 (ro) | 2017-06-23 | 2018-06-22 | Sistem de calcul central şi metodă de control a unei operaţii de întreţinere a unui reactor nuclear |
RO202100323A RO135345A2 (ro) | 2017-06-23 | 2018-06-22 | Sisteme şi metode de comunicaţii pentru echipamentele reacto- rului nuclear |
Family Applications After (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
RO202100323A RO135345A2 (ro) | 2017-06-23 | 2018-06-22 | Sisteme şi metode de comunicaţii pentru echipamentele reacto- rului nuclear |
Country Status (5)
Country | Link |
---|---|
KR (2) | KR20240039235A (zh) |
CN (2) | CN117198575A (zh) |
CA (2) | CA3066049A1 (zh) |
RO (2) | RO134594B1 (zh) |
WO (1) | WO2018232525A1 (zh) |
Families Citing this family (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN113760433B (zh) * | 2021-09-06 | 2023-12-15 | 中广核工程有限公司 | 面向顺序控制的核电厂监控方法、系统和计算机设备 |
Family Cites Families (9)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4815014A (en) * | 1987-02-27 | 1989-03-21 | Westinghouse Electric Corp. | Machine assisted execution of process operating procedures |
JPH09159788A (ja) * | 1995-12-11 | 1997-06-20 | Toshiba Corp | 原子炉内遠隔作業装置およびその作業方法 |
US6640151B1 (en) * | 1999-12-22 | 2003-10-28 | Applied Materials, Inc. | Multi-tool control system, method and medium |
JP3689767B2 (ja) * | 2000-09-22 | 2005-08-31 | 株式会社日立製作所 | 火力発電プラント保守サービス提供方法 |
JP2007144541A (ja) * | 2005-11-25 | 2007-06-14 | Murata Mach Ltd | 加工機械の工具情報表示装置 |
KR100926013B1 (ko) * | 2007-08-31 | 2009-11-11 | 두산중공업 주식회사 | 현장기기연계모듈 |
EP2154652A1 (en) * | 2008-08-11 | 2010-02-17 | Caterpillar Work Tools B. V. | System for determining the work time of a work tool |
US10725442B2 (en) * | 2014-09-12 | 2020-07-28 | Fisher-Rosemount Systems, Inc. | Methods and apparatus to communicatively couple on/off valves to controllers in a process control system |
EP3082133B1 (en) * | 2015-04-14 | 2023-06-07 | General Electric Technology GmbH | Nuclear instrumentation and control system |
-
2018
- 2018-06-22 KR KR1020247009179A patent/KR20240039235A/ko active Application Filing
- 2018-06-22 CA CA3066049A patent/CA3066049A1/en active Pending
- 2018-06-22 CN CN202311216524.XA patent/CN117198575A/zh active Pending
- 2018-06-22 WO PCT/CA2018/050769 patent/WO2018232525A1/en active Application Filing
- 2018-06-22 CN CN201880054720.2A patent/CN111133530B/zh active Active
- 2018-06-22 KR KR1020197038015A patent/KR102650516B1/ko active IP Right Grant
- 2018-06-22 RO ROA201900931A patent/RO134594B1/ro unknown
- 2018-06-22 RO RO202100323A patent/RO135345A2/ro unknown
- 2018-06-22 CA CA3213882A patent/CA3213882A1/en active Pending
Also Published As
Publication number | Publication date |
---|---|
KR20240039235A (ko) | 2024-03-26 |
KR102650516B1 (ko) | 2024-03-21 |
WO2018232525A1 (en) | 2018-12-27 |
RO134594A2 (ro) | 2020-11-27 |
CA3066049A1 (en) | 2018-12-27 |
KR20200019894A (ko) | 2020-02-25 |
RO135345A2 (ro) | 2021-11-29 |
CN111133530B (zh) | 2023-10-20 |
CA3213882A1 (en) | 2018-12-27 |
CN117198575A (zh) | 2023-12-08 |
CN111133530A (zh) | 2020-05-08 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
CN107193375B (zh) | 一种基于虚拟现实的电力安全生产场景交互系统 | |
US5490185A (en) | System for automatic refueling of a nuclear reactor | |
EP3276568A1 (en) | Production manager with location and inspection data | |
US20180276582A1 (en) | Geolocation assist plant operation management system | |
KR102069442B1 (ko) | 원자력 발전소 운전지원 및 감시 시스템 | |
RO134594B1 (ro) | Sistem de calcul central şi metodă de control a unei operaţii de întreţinere a unui reactor nuclear | |
Jharko et al. | Aspects of nuclear power plant digital decommissioning | |
Arzhaev et al. | NPP unit life management based on digital twin application | |
Chatzidakis et al. | A Versatile Remediation Module for Remote Repair of Spent Nuclear Fuel and High-Level Waste Storage Containers | |
KR101716480B1 (ko) | Gui 기반의 테스트케이스 입력 장치 | |
CN115423152A (zh) | 一种核燃料装卸与位置自动化跟踪方法、装置及系统 | |
CN114722628A (zh) | 一种基于psa模型及建模软件的配置风险评价方法 | |
JPWO2003100678A1 (ja) | 設備の製作又はその保全作業の支援システム及び監視操作システム | |
JP7237873B2 (ja) | 定期検査工程作成支援装置及び定期検査工程作成支援方法 | |
He et al. | Application of Combining 3D Model and Survey on Site to Simulate Dome Lifting | |
Collins et al. | Remote handling operator training at JET | |
Bouveret et al. | PWR reactor vessel in-service inspection according to RSEM | |
CN118821485A (zh) | 反应堆厂房内设备的失效分析方法、装置、介质及设备 | |
Bucher et al. | Keep It Smart and Simple-Henriette-The Advanced Designed Drum Gripper for Remote Handling Tasks-19327 | |
Marttila | Regulatory oversight of nuclear safety in Finland: Annual report 2020 | |
CN118211959A (zh) | 基于4GWi-Fi的实验室巡检维保综合信息管理系统及方法 | |
Lew et al. | Ensuring operator reliability in digital control rooms-102 | |
JP2021144517A (ja) | 定期検査工程作成支援装置及び定期検査工程作成支援方法並びに定期検査情報連携システム | |
CN118332288A (zh) | 一种电厂设备维修检测预防性试验数据分析方法及系统 | |
KR20150076729A (ko) | 자재 시공완료기한 관리 지원시스템 |