摘要:
A test lead assembly is provided for an electrical connector assembly, such as a terminal board. The terminal board includes a generally planar member and a number of fasteners, such as terminal screws, which are structured to fasten and electrically connect electrical conductors to the generally planar member. The test lead assembly includes an extension member having first and second opposing ends, and an intermediate portion extending therebetween. The first end is fastened to the enlarged head of a corresponding one of the terminal screws. A connection element is disposed at or about the second end of the extension member. In one embodiment the connection element is a thumb screw that electrically connects a test element to the extension member. The test lead assembly enables the terminal board to be tested, without loosening or otherwise disturbing the electrical connections of the terminal board. An associated method is also disclosed.
摘要:
A method for applying a burnable poison onto the cladding of a nuclear fuel rod (2) which comprises, providing a nuclear fuel rod (2) and at least one application device (8), rotating the nuclear fuel rod, optionally removing one or more oxides and/or surface deposits on the outer surface of the nuclear fuel rod (2) by spraying an abrasive material onto the nuclear fuel rod via the application device (8) while adjusting the position of the application device in relation to the nuclear fuel rod (2), and applying burnable poison particles (33) onto the outer surface (6) of the nuclear fuel rod (2) by spraying the burnable poison onto the nuclear fuel rod via the application device while adjusting the position of the application device (8) in relation to the nuclear fuel rod, where the burnable poison particles are applied at a velocity sufficient to cause adhesion to the outer surface (6) of the cladding.
摘要:
A permanent cavity seal ring that replaces the function of the temporary cavity seal ring typically used in narrow thermal expansion gap pressurized water reactors, to seal the gap between the reactor cavity well and the reactor during refueling. The permanent seal ring uses a C-shaped flexure that is shielded by a rigid cantilevered support arm from any accidentally dropped equipment from above in the refueling canal. The construction accommodates the thermal expansion of the reactor vessel while permitting the reactor cavity cooling air to exit the annulus between the vessel and the reactor cavity wall during plant operation, without a significant increase in pressure drop.
摘要:
A grading system for a pressurized water reactor steam generator secondary side performance that provides a cumulative assessment of tube bundle deposit inventory and characteristics, i.e., scale density and distribution, hard scale collar formation, thermal performance, loose parts management, and steam generator secondary side chemistry performance. Results are summarized in a cumulative quality point average with individual parameter ratings available so that specific performance improvement may be achieved.
摘要:
A nuclear fuel assembly having an instrumentation tube having an insert that centers the in-core instrumentation while permitting bugling or welding of the instrumentation tube wall to a grid strap to obtain a rigid connection there between at any elevation along the instrumentation tube.
摘要:
A method is provided for recovering operating margin in a nuclear reactor. The reactor includes a steam generator, a Reactor Coolant System (RCS) having a hot leg with a temperature, Thot, and a cold leg with a temperature, Tcold, a Reactor Trip System (RTS) having an Over Temperature Delta Temperature (OTDT) trip function and an Over Power Delta Temperature (OPDT) trip function, and a control system. The method improves the RTS by filtering only the hot leg temperature signal of the RCS. Thus, the needs for separate Tavg and Delta-T filters, and for filtering of temperature signals in both the hot leg and cold leg are eliminated. A reactor system is also disclosed.
摘要:
The present invention provides a method for removing niobium-rich second-phase-particle (SPP) deposits from zirconium-niobium alloy components. The method comprises washing a freshly pickled and rinsed zirconium-niobium alloy component with an acidified oxalic acid or ammonium oxalate washing solution. The method of the present invention results in a rapid, efficient and complete removal of surface SPP deposits from the zirconium-niobium alloy component without pitting, leaving behind a clean, shiny surface without the need to use water blasting or mechanical wiping operations.
摘要:
A vacuum arc remelt furnace system that automatically monitors for electrode to crucible arcing in a VAR furnace. The vacuum arc remelt furnace system includes a crucible, an electrode provided within the crucible, and a spectrometer operatively coupled to the gap between the electrode and the crucible. The spectrometer detects the presence of one or more copper-specific light wavelengths in light that is present in the gap, and preferably generates an alarm and/or shuts the furnace down depending upon what is detected. Also, a method of operating a vacuum arc remelt furnace to automatically monitor for electrode top crucible arcing. The method includes collecting light that is present in the gap between the crucible and said electrode, and determining whether one or more copper-specific light wavelengths are present in the light. An alarm is generated and/or the furnace is shut down depending upon what is detected.
摘要:
A method is for establishing a nuclear reactor core loading pattern (LP) for fuel assemblies and burnable absorbers (BAs). The method establishes an optimum LP through the steps of: a) providing nuclear data representing fuel assemblies and BAs in a nuclear reactor core; b) depleting the nuclear data to form a reference core depletion; c) incorporating the nuclear data into a system of linear equations of a nuclear design quality flux solution method; d) defining the system of linear equations to include constraints which accurately represent the neutron physics of the reactor; employing the equations as a constraint matrix for a MIP solver to find an optimum core pattern solution; f) repeating steps b) through e) updating the constraints and objective functions to satisfy specified engineering requirements and establish an optimum core loading pattern. An algorithm for deriving the system of equations is also disclosed.
摘要:
An ultrasonic testing assembly structured to examine a test object, wherein the test object has a surface, and the examination examines the structure of the test object under the surface as well as the profile of the surface. The ultrasonic testing assembly includes a sled assembly structured to support a plurality of ultrasonic transducers, the sled assembly including at least one support member having a lower surface, at least one surface ultrasonic transducer coupled to the sled assembly and structured to extend below the support member lower surface and further structured to engage the test object surface, the surface ultrasonic transducer structured to examine internal structure of the test object and provide a first output, at least one profiling device coupled to the sled assembly, the profiling device structured to measure the profile of the test object surface and provide a second output, and a control device structured to correlate the first output and the second output and to calculate a corrected output.