200267 ⎘
Monitoring; Testing Maintaining; Devices or arrangements for monitoring coolant or moderator for monitoring liquid coolants or moderators
Sub-classes:COMPUTER APPARATUS FOR MONITORING AND VERIFYING NUCLEAR AND FOSSIL POWER PLANT HEAT LOSSES BASED ON THE REVISED NCV METHOD
#2PLANT RELIABILITY EVALUATION SYSTEM, PLANT RELIABILITY EVALUATION METHOD, AND PLANT RELIABILITY EVALUATION PROGRAM
#3APPARATUS FOR THERMAL PERFORMANCE MONITORING AND SAFE OPERATION OF A NUCLEAR POWER PLANT
#4A METHOD OF ADJUSTING OXOACIDITY
#5METHOD OF COMMUNICATING TEMPERATURE DATA INCLUDING A HEATING ELEMENT COUPLED TO TEMPERATURE SENSOR AT INTERFACE
#6Method for thermal performance monitoring of a nuclear power plant using the NCV method
#7METHOD FOR ONLINE RADIOISOTOPE MEASUREMENT FOR FAILED FUEL CHARACTERIZATION IN PRIMARY SODIUM SYSTEMS
#8DEVICE AND METHOD FOR MEASURING A NEUTRON ABSORBER IN A FLUID
#9WAVEGUIDES FOR NON-INVASIVE MEASUREMENT OF FLOW IN A HIGH TEMPERATURE PIPE AND APPARATUSES, SYSTEMS, AND METHODS OF USE THEREOF
#10Computer-Based Simulation Methods for Boiling Water Reactors (BWR)
#11APPARATUS AND METHOD FOR REAL-TIME PRECISION MEASUREMENT OF THE THERMAL POWER OF A NUCLEAR REACTOR
#12Combined power generation system and method of small fluoride-salt-cooled high-temperature reactor and solar tower
#13Device for measuring total gas content of primary circuit of PWR nuclear power
#14Hydrogenation system for a pressurized water reactor
#15Experimental facility and method for studying jet impact characteristics at core outlet of fast reactor
#16Multi-loop natural circulation experimental device under six-degree-of-freedom motion conditions and method therefor
#17TWO AND THREE-DIMENSIONAL MODEL BASED CORRECTION OF ELBOW TAP FLOW MEASUREMENT
#18Nuclear fuel failure protection system
#19Apparatus with flow assembly including temperature sensors and heating element
#20Method for replacing a cesium trap and cesium trap assembly thereof
#21Device for prediction of reactor water quality of nuclear reactor
#22Waveguides for non-invasive measurement of flow in a high temperature pipe and apparatuses, systems, and methods of use thereof
#23Heat exchanger assemblies having embedded sensors
#24Power plant chemical control system
#25Real-time reactor coolant system boron concentration monitor utilizing an ultrasonic spectroscpopy system
#26FLUID SLOSHING BEHAVIOR ANALYSIS APPARATUS AND METHOD THEREOF
#27Method of replacing cesium trap and cesium trap assembly thereof
#28Nuclear fuel failure protection method
#29Apparatus, systems, and methods for non-invasive measurement of flow in a high temperature pipe
#30Heat pipe assembly of nuclear apparatus having fiber optical temperature detection system
#31Apparatus and method for producing fibrous debris of test for nuclear power plant
#32NUCLEAR REACTOR FLUID THERMAL MONITORING ARRAY
#33IN SITU PROBE FOR MEASUREMENT OF LIQUIDUS TEMPERATURE IN A MOLTEN SALT REACTOR
#34REAL-TIME REACTOR COOLANT SYSTEM BORON CONCENTRATION MONITOR UTILIZING AN ULTRASONIC SPECTROSCPOPY SYSTEM
#35Reactor coolant system piping temperature distribution measurement system
#36Method of evaluating amount of foreign matter passed through recirculation sump screen
#37Method for controlling a pressurized water nuclear reactor during stretchout
#38Nuclear grade air accumulating, isolating, indicating and venting device
#39Process for the accurate characterization of low level nuclear waste
#40SYSTEM FOR THE IN-LINE CHARACTERIZATION OF PRODUCTS OF CORROSION
#41SYSTEM FOR THE IN-LINE CHARACTERISATION OF CORROSION PRODUCTS
#42Transportable monitoring system
#43Method for monitoring boron dilution during a reactor outage
#44Nuclear grade air accumulation, indication and venting device
#45METHOD AND SYSTEM FOR MEASURING A SPENT FUEL POOL TEMPERATURE AND LIQUID LEVEL WITHOUT EXTERNAL ELECTRICAL POWER
#46Method of separating amorphous iron oxides
#47Apparatus and method for limiting and analyzing stress corrosion cracking in pressurized water reactors
#48Method of adjusting oxygen concentration of reactor water samples using demineralized water
#49REACTOR ADAPTED FOR MITIGATING LOSS-OF-COOLANT ACCIDENT AND MITIGATION METHOD THEREOF
#50Passive Gamma Thermometer Level Indication And Inadequate Core Monitoring System And Methods For Power Reactor Applications During A Station Electrical Blackout (SBO) Or Prolonged Station Blackout (PSBO) Event
#51Electrochemical corrosion potential device and method
#52Heat removal system and method for use with a nuclear reactor
#53Electrochemical corrosion potential probe assembly
#54Chemistry probe assemblies and methods of using the same in nuclear reactors
#55Nuclear power plant, method of forming corrosion-resistant coating therefor, and method of operating nuclear power plant
#56Nuclear power plant, method of forming corrosion-resistant coating therefor, and method of operating nuclear power plant
#57Apparatus for detecting contaminants in a liquid and a system for use thereof
#58Two-phase flow exciting force evaluation method and device acting on a plurality of tube bodies arranged to intersect with the flow
#59Nuclear grade air accumulation, indication and venting device
#60Method for estimating the concentration of a chemical element in the primary coolant of a nuclear reactor
#61Electrochemical corrosion potential sensor
#62REACTOR START-UP MONITORING SYSTEM
#63Methods for detecting contaminants in a liquid
#64Apparatus and method for limiting and analyzing stress corrosion cracking in pressurized water reactors
#65Nuclear power plant, method of forming corrosion-resistant coating therefor, and method of operating nuclear power plant
#66Reactor structural member and method of suppressing corrosion of the same