Disclosed are a voltage drop measurement system and methods for measuring resistivity of a nuclear reactor cladding. The system includes a short cladding sample of a nuclear reactor cladding. Two electrically conductive plugs are attached to the short cladding. A power supply is electrically coupled to the each of the two electrically conductive plugs and is configured to apply an electrical current to the short cladding through the two electrically conductive plugs. Two needle like probes are electrically coupled to a surface of the short cladding between the two electrically conductive plugs. The needle like probes are spaced apart by a distance L. Resistivity and heat flux are determined in accordance with Equations (1)-(4).

A system and method for performing active scanning on a nuclear fuel rod are provided. The system includes an electrically-driven neutron generator including an ion source, an accelerator, and a target; a moderator surrounding the neutron generator and configured to moderate neutrons generated by the neutron generator; a fuel rod channel disposed within the moderator, the fuel rod channel configured to receive a nuclear fuel rod and subject the nuclear fuel rod to a predetermined neutron flux; and a plurality of radiation detectors. When the nuclear fuel rod is subjected to the predetermined neutron flux, neutrons induce a secondary radiation of prompt and delayed gamma emissions, neutron emission, or a combination thereof that are detected by the plurality of radiation detectors to determine an amount of fissile material in the nuclear fuel rod and a spatial distribution of the fissile material along a length of the nuclear fuel rod.

A system and method for performing active scanning on a nuclear fuel rod are provided. The system includes an electrically-driven neutron generator including an ion source, an accelerator, and a target; a moderator surrounding the neutron generator and configured to moderate neutrons generated by the neutron generator; a fuel rod channel disposed within the moderator, the fuel rod channel configured to receive a nuclear fuel rod and subject the nuclear fuel rod to a predetermined neutron flux; and a plurality of radiation detectors. When the nuclear fuel rod is subjected to the predetermined neutron flux, neutrons induce a secondary radiation of prompt and delayed gamma emissions, neutron emission, or a combination thereof that are detected by the plurality of radiation detectors to determine an amount of fissile material in the nuclear fuel rod and a spatial distribution of the fissile material along a length of the nuclear fuel rod.

A method for detecting the thicknesses of coating layers of nuclear fuel particles, comprising: collecting a surface image of a sample to be tested under a first amplification factor (S310); determining a testable particle in the surface image (S320); collecting a cross section image of the testable particle under a second amplification factor, wherein the second amplification factor is greater than the first amplification factor (S330); and determining the center of the testable particle in the cross section image and profile lines of all coating layers, and determining the thickness of each coating layer according to the center and the profile lines of each coating layer (S340). Also provided is a device for detecting the thicknesses of coating layers of the nuclear fuel particles.

A method for detecting the thicknesses of coating layers of nuclear fuel particles, comprising: collecting a surface image of a sample to be tested under a first amplification factor (S310); determining a testable particle in the surface image (S320); collecting a cross section image of the testable particle under a second amplification factor, wherein the second amplification factor is greater than the first amplification factor (S330); and determining the center of the testable particle in the cross section image and profile lines of all coating layers, and determining the thickness of each coating layer according to the center and the profile lines of each coating layer (S340). Also provided is a device for detecting the thicknesses of coating layers of the nuclear fuel particles.

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.

Provided is an apparatus for fatigue testing a bulge tool having a WH-type skeleton, the apparatus including: a fixing bracket having tool holes penetrated through opposite sides thereof; a tool housing coupled to the tool hole of the fixing bracket and having the bulge tool inserted and installed therein; a moving rail installed at one side of the fixing bracket in a lengthwise direction of the tool housing and providing a reciprocating movement path facing the tool housing; a moving bracket reciprocating along the moving rail; a pusher protrudingly installed from the moving bracket toward the tool housing and moving in and out of the bulge tool; a measurement means installed between the pusher and the moving bracket, measuring a load applied to the bulge tool; and a drive means for generating power reciprocating the moving bracket on the moving rail.

Provided is a standard for mobile equipment for measuring structural deformation of a nuclear fuel assembly, the standard including: a fixed frame fixed to one side of measuring equipment accommodated in a container; a standard member configured to be attached to and detached from the fixed frame, to rotate with one end portion of the fixed frame as a center, and to correspond to a nuclear fuel assembly standard specification, wherein an upper plate provided with a coupling means configured to be coupled with a transport device is coupled on one end portion of the standard member, a lower plate configured to be erected upright on and fixed to one side of the measuring equipment is coupled on an opposite end portion of the standard member.

Provided is a standard for mobile equipment for measuring structural deformation of a nuclear fuel assembly, the standard including: a fixed frame fixed to one side of measuring equipment accommodated in a container; a standard member configured to be attached to and detached from the fixed frame, to rotate with one end portion of the fixed frame as a center, and to correspond to a nuclear fuel assembly standard specification, wherein an upper plate provided with a coupling means configured to be coupled with a transport device is coupled on one end portion of the standard member, a lower plate configured to be erected upright on and fixed to one side of the measuring equipment is coupled on an opposite end portion of the standard member.

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.