Tester for monitoring alpha contamination of fuel elements containing tandem loading module and unloading module of fuel elements, each having a fixed frame with cradles, position indicators of fuel elements, measurement module located between the loading module and unloading module, which includes the detection units of alpha radiation from the surface of fuel elements, pneumatic cylinders with position indicators of the rods for samples forwarding with the source of alpha radiation. The loading module is supplied with a movable automated carriage with cradles for forwarding fuel elements to the measurement module and then to the unloading module, besides the loading and unloading modules are provided with movable racks for placing the fuel elements on the cradles of the modules and carriage, and the samples with natural uranium isotopes are used as the source of alpha radiation for setup of the measurement module.

A system for servicing a nuclear reactor module comprises a crane operable to attach to the nuclear reactor module, wherein the crane includes provisions for routing signals from one or more sensors of the nuclear reactor module to one or more sensor receivers.

Proposed is a light-water reactor nuclear fuel rod loading force measuring apparatus provided on a nuclear fuel rod loading apparatus, which comprises a spacer grid holder and a loading power device installed with a traction module configured to reciprocally move toward the spacer grid holder, the measuring apparatus including: a hollow cladding tube sample positioned on one side of a spacer grid and having the same diameter as a nuclear fuel rod cladding tube; a pulling bar having one end part passing through a cell of the spacer grid and coupled to the hollow cladding tube sample and an opposite end part coupled to the traction module; and a measuring means installed on the pulling bar and configured to measure force of the traction module loading the pulling bar.

Proposed is a light-water reactor nuclear fuel rod loading force measuring apparatus provided on a nuclear fuel rod loading apparatus, which comprises a spacer grid holder and a loading power device installed with a traction module configured to reciprocally move toward the spacer grid holder, the measuring apparatus including: a hollow cladding tube sample positioned on one side of a spacer grid and having the same diameter as a nuclear fuel rod cladding tube; a pulling bar having one end part passing through a cell of the spacer grid and coupled to the hollow cladding tube sample and an opposite end part coupled to the traction module; and a measuring means installed on the pulling bar and configured to measure force of the traction module loading the pulling bar.

A nuclear system. The nuclear system includes a fuel rod for use in a nuclear reactor. The fuel rod includes a cladding comprising an interior region, unspent fuel pellets housed in the interior region of the cladding, and a resonant electrical circuit supported within the interior region of the cladding. The resonant electrical circuit is configured to receive an excitation pulse through the cladding, and responsive to the received excitation pulse, generate a response pulse in the form of a magnetic field signal that is structured to travel wirelessly from the interior region and through the cladding. The nuclear system also includes a receiver positioned outside of the cladding and within the nuclear reactor. The receiver is configured to receive the response pulse and generate an output based on the received response pulse.

A method is for manufacturing a nuclear fuel assembly (2) comprising nuclear fuel rods (4) arranged in a bundle and a skeleton (6) supporting the fuel rods (4). The method comprise the steps of inserting fuel rods (4) into the skeleton (6) to obtain a fuel assembly (2) and packaging the fuel assembly (2) in view of transportation. The steps are being performed in a same nuclear fuel assembly manufacturing plant (20), preferably in a same nuclear fuel assembly manufacturing building (60).

A method is for manufacturing a nuclear fuel assembly (2) comprising nuclear fuel rods (4) arranged in a bundle and a skeleton (6) supporting the fuel rods (4). The method comprise the steps of inserting fuel rods (4) into the skeleton (6) to obtain a fuel assembly (2) and packaging the fuel assembly (2) in view of transportation. The steps are being performed in a same nuclear fuel assembly manufacturing plant (20), preferably in a same nuclear fuel assembly manufacturing building (60).

Provided is a statistical overpower penalty calculation system for a generic thermal margin analysis model, the system including: a random number generating unit generating a plurality of random numbers; an power distribution generating unit generating power information of an axial direction and a radial direction for a core burnup; an operating condition generating unit extracting an arbitrary value for a plurality of operating conditions from the random number generated above; a POL calculating unit calculating a POL of a reload core thermal margin analysis model and a POL of a generic thermal margin analysis model and calculating a plurality of the overpower penalties through the POLs; and a statistics processing unit calculating tolerance limit values according to the core burnup by statistically analyzing a distribution formed of the plurality of the overpower penalties and selecting a smallest tolerance limit value as a representative value of the overpower penalties.

Provided is a statistical overpower penalty calculation system for a generic thermal margin analysis model, the system including: a random number generating unit generating a plurality of random numbers; an power distribution generating unit generating power information of an axial direction and a radial direction for a core burnup; an operating condition generating unit extracting an arbitrary value for a plurality of operating conditions from the random number generated above; a POL calculating unit calculating a POL of a reload core thermal margin analysis model and a POL of a generic thermal margin analysis model and calculating a plurality of the overpower penalties through the POLs; and a statistics processing unit calculating tolerance limit values according to the core burnup by statistically analyzing a distribution formed of the plurality of the overpower penalties and selecting a smallest tolerance limit value as a representative value of the overpower penalties.

Described herein are methods and systems for improved inspection, measurements, monitoring, and tracking of equipment installed underwater. They include structures or equipment installed in a nuclear reactor and fuel storage pools. This includes, but is not limited to an entire nuclear reactor pool, an entire nuclear reactor, fuel assemblies, fuel assembly identification numbers, core barrels, core plates, lower internals, upper internals, fuel transfer systems, alignment pins, baffle walls, former baffle assemblies, vessels, instrument ports, coolant tubes, spent fuel pools, dry cask storage areas, weir gates, steam dryers, steam separators, top guides, jet pumps, inside and outside of pipes, and weld seams. The described methods and devices increase the performance and integrity of the inspection and measurements during nuclear refuel, inspection or outage activities. The described methods and devices utilize one or more non-touch underwater optical system (including laser systems) for underwater equipment inspection, measurements, maintenance, monitoring, tracking and servicing.