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7532698 |
Systems and methods of predicting a critical effective k for a nuclear reactor
Systems and methods for a method for determining a critical effective k at an off-rated core state of a nuclear power plant includes determining, for the off-rated core state a control rod density,...
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7333585 |
Radiation measurement device
A radiation measurement device includes a radiation detector generating an analog signal containing pulse components, an A/D converter converting the analog signal into sampled data, an n-th power...
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7139355 |
Method of operating a nuclear power plant at multiple power levels
A method of operating a nuclear power plant includes determining and licensing a maximum power level at which the power plant can be operated subsequent to the beginning of a fuel cycle, and with...
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7139354 |
Radiation measurement device
A radiation measurement device includes a radiation detector generating an analog signal containing pulse components, an A/D converter converting the analog signal into sampled data, an n-th power...
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7133488 |
Neutron flux mapping system for nuclear reactor
A neutron flux mapping system for a nuclear reactor including: drivers each including a geared motor, a helical gear driven by the geared motor, and a storage reel adapted to supply, to the helical...
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6950489 |
Guide tube for an instrumentation lance extending into a pressure vessel, reactor pressure vessel, and a method for preventing the accumulation of particles outside the pressure vessel in a guide tube
The invention relates to a guide tube especially for an instrumentation lance extending into a reactor pressure vessel. The guide tube includes a lower tube section and an upper tube section that...
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6801593 |
Subcritical reactivity measurement method
A method of monitoring reactivity changes in a nuclear reaction when the nuclear reaction is subcritical. The method controls the parameter of the nuclear reaction that affects reactivity of the...
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6785633 |
Method and apparatus for assessing performance of combined cycle power-plants
A method of determining performance impact of individual components of a power plant on overall thermal performance of the power plant, the method including (a) designing a first thermal model of...
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6744840 |
Incore monitoring method and incore monitoring equipment
An incore monitoring method of a nuclear reactor, includes, measuring neutron flux levels at pitch levels corresponding to local power range monitor sensors arranged along an axial direction inside...
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6674826 |
Method of operating a nuclear power plant at multiple power levels
A method of operating a nuclear power plant includes determining and licensing a maximum power level at which the power plant can be operated subsequent to the beginning of a fuel cycle, and with...
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6633622 |
Reactor power output measurement device
A reactor power output measurement device measuring a neutron flux with a traversing incore probe (TIP) traversing in a vertical direction in a core of a reactor, and calibrating a detection...
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6598029 |
Bidding for energy supply with request for service
An auction service is provided that stimulates competition between energy suppliers (i.e., electric power or natural gas). A bidding moderator (Moderator) receives bids from the competing suppliers...
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6563899 |
Neutron monitoring system
The neutron monitoring system measures neutrons by counting both the negative pulse signals and the positive noise pulse signals output from a neutron detector 1 , and subtracts the positive pulse...
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6553090 |
Control system of nuclear power plant, and control method thereof
A method of controlling a nuclear power plant includes determining a first maximum linear heat generation rate and a first minimum critical power ratio by a core monitoring system, and determining...
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6542565 |
Semiconductor radiation source power monitor
A solid state semiconductor neutron detector that automatically varies its sensitivity to provide a pulsed output over the entire range of operation of a nuclear reactor. The sensitivity is varied...
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6522709 |
Nuclear in-core instrument (ICI) assembly with compressed flexible hose sheath
A protective hose, and a method of making the same, for an in-core instrument assembly used in a nuclear reactor, including a first end that is hermetically sealed to a first member of in-core...
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6493412 |
Method of calibrating exit thermocouples in a nuclear reactor
The exit thermocouples of a pressurized water reactor (PWR) are calibrated by recording the thermocouple temperature measurements periodically during power ascension of the reactor together with a...
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6477219 |
Nuclear reactor power distribution monitoring system and method including nuclear reactor instrumentation system
A nuclear reactor instrumentation system including a plurality of incore nuclear instrumentation assemblies arranged in a gap between a number of fuel assemblies charged in a reactor core. The...
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6456681 |
Neutron flux measuring apparatus
A neutron flux measuring apparatus, adapted to a boiling-water reactor (BWR) of a nuclear power plant and an advanced boiling-water reactor (ABWR) of a nuclear power plant, for measuring a neutron...
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6430247 |
Method and system for monitoring at least one operating parameter of the core of a nuclear reactor
Neutron flux is measured using a subset of detectors ( 8 ) selected from a set of detectors ( 8 ) introduced into fuel assemblies ( 2 ) of the core ( 1 ) to obtain measurement signals, the number n...
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6406064 |
Positive locking device for reactor instrumentation protection sleeve assembly
A locking device for a reactor instrumentation protective sleeve and reactor instrumentation column assembly. The locking device includes a protective sleeve coupled to the instrumentation column...
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6408041 |
In-core fixed nuclear instrumentation system and power distribution monitoring system
In an in-core fixed nuclear instrumentation system for a reactor, each of a plurality of in-core nuclear instrumentation assemblies has a nuclear instrumentation tube. LPRM detectors are housed in...
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6404437 |
Nuclear reactor core performance data visualization system
A nuclear reactor core performance data visualization system provides a method and apparatus for extracting and visually displaying large amounts of numerical performance data acquired from an...
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6400786 |
Process and device for monitoring at least one operating parameter of the core of a nuclear reactor
During operation of the nuclear reactor, at specified time intervals, a neutron flux is measured using a set of neutron flux detectors which are fixed and arranged in the core ( 1 ) of the nuclear...
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6353650 |
Reduced in-core instrument patterns for pressurized water reactors
A method for determining a reduced ICI patterns is provided to achieve core monitoring and surveillance and other required functions using fewer ICIs. Candidate ICI patterns having a reduced number...
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6339629 |
System for monitoring power of nuclear reactor
In a system for monitoring power of a nuclear reactor, a plurality of neutron flux measuring devices are arranged in a reactor core of the nuclear reactor for measuring neutron flux so as to...
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6252923 |
In-situ self-powered monitoring of stored spent nuclear fuel
Detectors are used to monitor the status of spent nuclear fuel storage containers non-invasively while they remain in storage casks. The detectors measure neutron flux and γ-ray flux and may also...
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6181761 |
Apparatus and method of monitoring reactor power of reactor at the time of startup thereof
The reactor start-up monitoring apparatus is provided with an SRNM detector, an analog amplifier, an N/D converter, a pulse measurement system, a Campbell measurement system and reactor power...
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6181759 |
Method and apparatus for determining nearness to criticality of a nuclear fueled electric power generating unit
A method is provided for determining the closeness to criticality of a nuclear reactor during start-up, comprising the steps of completing a control rod withdrawal step, thereby generating a change...
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6173026 |
System for monitoring reactor instability and controlling reactor suppression
A power oscillation monitoring system and method for indicating instability of a nuclear reactor. The monitoring system facilitates monitoring reactor instability and maintaining a nuclear reactor...
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6169775 |
Radiation detecting apparatus
A radiation detecting apparatus comprises a container having a vacuum space, a radiation detecting element disposed in the vacuum space for detecting radiation, and a cooling element disposed in...
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6134289 |
Thermal neutron detection system
According to the present invention, a system for measuring a thermal neutron emission from a neutron source, has a reflector/moderator proximate the neutron source that reflects and moderates...
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6122339 |
Method and device for operating a reactor in an unstable state
A transiently unstable state of a boiling-water reactor is damped by measuring the oscillating neutron flux and, after a first threshold value is exceeded over a plurality of oscillation periods,...
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6081573 |
Reactor internal equipment hoisting apparatus
There is provided a reactor internal equipment hoisting apparatus which is hung down from an upper side of a reactor pressure vessel to hoist reactor internal equipment installed inside the reactor...
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6061412 |
Nuclear reaction protection system
A safety grade protection system for monitoring parameters indicative of the status of a core of a nuclear reactor, and reducing the criticality of the nuclear reaction when the onset of unsafe...
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6035010 |
Monitor for measuring both the gamma spectrum and neutrons emitted by an object, such as spent nuclear fuel
The present invention concerns a monitor for measuring both the gamma spectrum and neutrons emitted by an object such as a spent nuclear fuel pin or pin assembly or nuclear waste material....
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5960050 |
Method of fission heat flux determination from experimental data
A method is provided for determining the fission heat flux of a prime specimen inserted into a specimen of a test reactor. A pair of thermocouple test specimens are positioned at the same level in...
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5956380 |
Method and apparatus for determining neutron flux density, in particular in a nuclear power facility
A method and an apparatus are used for determining the neutron flux density of a neutron-emitting source, in particular a reactor core of a nuclear power facility. In the method, a first...
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5930317 |
Power range monitor system for nuclear reactor
A power range monitor apparatus includes a plurality of average power range monitors for calculating/monitoring local power values, average reactor power values, and core flow rate values, a...
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5802127 |
Device for protecting in-core monitors against damage during servicing of nuclear reactor
An in-core monitor protector intended for use during in-vessel services while work is being performed in the reactor core region of a BWR. The purpose of the protector is to prevent damage to or...
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5787138 |
Supervision of a neutron detector in a nuclear reactor
A method of monitoring neutron flex detectors in a nuclear reactor in a neural network is provided. The network comprises an input layer which receives a number of input signals corresponding to...
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5786975 |
Electronic switching circuits
A switching circuit especially suitable for protecting electronic components such as integrated circuits (2) from the harmful effects of ionizing radiation. The circuit comprises two switches for...
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5774515 |
Particle measuring apparatus, method for particle measurement, and nuclear power plant
A neutron particle measuring apparatus includes a neutron converter to generate alpha rays in response to incidence of neutron, a scintillator to receive as input the alpha rays generated from the...
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5745538 |
Self-powered fixed incore detector
A self-powered fixed incore detector for a nuclear reactor has a neutron sensitive emitter element having a low neutron absorption cross section, such as a vanadium element, which extends the...
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5682410 |
Method for determining core flow rate and water temperature/density in boiling water reactor
A method for determining the core flow rate from pump differential pressure method equations and a heat balance equation for determining the temperature and density of the reactor water in the...
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5682409 |
Neutron fluence surveillance capsule holder modification for boiling water reactor
An apparatus for carrying out a surveillance program to monitor the neutron fluence and its effect on vessel materials at a position in the annular space between the pressure vessel and core shroud...
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5661767 |
Method for replacing a through-tube of the vessel bottom head of a nuclear reactor cooled by pressurized water
The tube to be replaced is extracted and an internal surface of the bottom head (1b) is then machined around the through opening (10), a hollow shell (20) is attached and fixed on the machined...
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5621776 |
Fault-tolerant reactor protection system
A reactor protection system having four divisions, with quad redundant sensors for each scram parameter providing input to four independent microprocessor-based electronic chassis. Each electronic...
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5555279 |
System for monitoring and controlling nuclear reactors
A computer-based power oscillation detection system and method for detecting, monitoring and indicating thermal-hydraulic stability margin in a nuclear reactor is provided. A group of neutron flux...
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5544209 |
Process for repairing and protecting from cracking the inner wall of a tube for penetrating the bottom head of a pressurized-water nuclear reactor vessel
During shutdown of the nuclear reactor, the closure head of the vessel having been dismounted and the vessel (3) and the pool of the reactor both being filled with water, an inner zone of the...
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