Ridolfo et al., 1993 - Google Patents
The Nuplex 80+™ advanced control complex from ABB Combustion EngineeringRidolfo et al., 1993
View HTML- Document ID
- 3497183212731506431
- Author
- Ridolfo F
- Harmon D
- Scarola K
- Publication year
- Publication venue
- Nuclear Safety
External Links
Snippet
Nuclear power-plant designs are in the process of extraordinary change. Worldwide social, political, industrial, and regulatory institutions are exerting unprecedented pressures to significantly increase the overall safety and availability of power plants while improving their …
- 238000002485 combustion reaction 0 title description 6
Classifications
-
- 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 GASES [GHG] EMISSION, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
- Y02E30/40—Other aspects relating to nuclear fission
-
- 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 GASES [GHG] EMISSION, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
- Y02E30/39—Control of nuclear reactions
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/02—Devices or arrangements for monitoring coolant or moderator
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/18—Emergency cooling arrangements; Removing shut-down heat
-
- 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
-
- 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
- G21Y—INDEXING SCHEME RELATING TO NUCLEAR REACTORS, POWER PLANTS AND EXPLOSIVES, TO PROTECTION AGAINST RADIATION, TO THE TREATMENT OF RADIOACTIVELY CONTAMINATED MATERIAL, TO APPLICATIONS OF RADIOACTIVE SOURCES AND TO THE UTILISATION OF COSMIC RADIATION
- G21Y2002/00—PROBLEM
- G21Y2002/201—Inadequate efficiency
-
- 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
- G21Y—INDEXING SCHEME RELATING TO NUCLEAR REACTORS, POWER PLANTS AND EXPLOSIVES, TO PROTECTION AGAINST RADIATION, TO THE TREATMENT OF RADIOACTIVELY CONTAMINATED MATERIAL, TO APPLICATIONS OF RADIOACTIVE SOURCES AND TO THE UTILISATION OF COSMIC RADIATION
- G21Y2004/00—SOLUTION
-
- 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
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21Y—INDEXING SCHEME RELATING TO NUCLEAR REACTORS, POWER PLANTS AND EXPLOSIVES, TO PROTECTION AGAINST RADIATION, TO THE TREATMENT OF RADIOACTIVELY CONTAMINATED MATERIAL, TO APPLICATIONS OF RADIOACTIVE SOURCES AND TO THE UTILISATION OF COSMIC RADIATION
- G21Y2002/00—PROBLEM
- G21Y2002/50—Safety, security and safeguard shortcomings
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
- G21C13/10—Means for preventing contamination in the event of leakage, e.g. double wall
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D1/00—Details of nuclear power plant
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
Similar Documents
Publication | Publication Date | Title |
---|---|---|
US5361198A (en) | Compact work station control room | |
KR100191566B1 (en) | How to Validate Indicators in a Nuclear Power Plant Control Complex | |
EP2839473B1 (en) | Control room for nuclear power plant | |
Hunton et al. | Vendor-Independent Design Requirements for a Boiling Water Reactor Safety System Upgrade | |
Ball et al. | Advanced control and protection system design methods for modular HTGRs | |
Ridolfo et al. | The Nuplex 80+™ advanced control complex from ABB Combustion Engineering | |
Santoso et al. | Preliminary design of human-machine interface for control room of modular reactor | |
Wang et al. | The implementation of diverse actuation system in ACPR1000 nuclear power plants | |
Suh et al. | An overview of instrumentation and control systems of a Korea standard nuclear power plant: A signal interface standpoint | |
Burchill | Insights from the Three | |
GB2286907A (en) | Compact work station control room | |
Cappelli | Principles of I&C systems for nuclear plants | |
Yoshikawa et al. | Integrated functional modeling method for configuring NPP plant DiD risk monitor and its application for AP1000 | |
Yu | Instrumentation and Control System | |
Bouwmeester | Ergonomic design of an overview display in a nuclear power plant control room. Integrated process status overview | |
Zhen-Ying et al. | The Implementation of Diverse Actuation System in ACPR1000 Nuclear Power Plants | |
Kernei¨ s et al. | Methodology and Principle for Emergency Operation Computerization in Loviisa NPP Automation Renewal Project | |
O'Brien et al. | Protection systems | |
Guinard et al. | SIPA-SWORD: a" configurable" simulator for safety | |
Tong | Reactor design and safety | |
Lepp et al. | Control and instrumentation systems for the 600 MWe CANDU PHW nuclear power plants | |
Kim et al. | The Development of the Advanced Light Water Reactor in Korea-The Korean Next Generation Reactor | |
YVON et al. | Preussen Elektra, Hannover | |
Cahn | Advanced light water reactor program at ABB-Combustion Engineering Nuclear Power | |
Jang et al. | System design strategies of post-accident monitoring system for a PGSFR in Korea |