A neutron grid, comprises: a grid including: a plurality of spacers through which at least a part of first neutrons from a target passes; and a plurality of absorbers to absorb at least a part of second neutrons scattered thorough the target, the spacers and the absorbers being alternately arranged along a first direction and extending along a second direction intersecting with the first direction; and a pair of covers through which at least a part of the first neutrons and at least a part of the second neutrons pass, sandwiching the grid along a third direction intersecting with the first and second directions. A thermal expansion coefficient difference between one of the spacers and one of the absorbers is 910.sup.6/ C. or less, or Young's modulus of the spacer is 100 GPa or more.

A method for evaluating the crosslink concentration in a crosslinked rubber is provided. The present invention relates to a method for evaluating the crosslink concentration in a crosslinked rubber by small-angle X-ray scattering or small-angle neutron scattering using measurement samples prepared by swelling the crosslinked rubber to different degrees of swelling.

High-throughput high-pressure (HT HP) sample cells and sampling environments are disclosed herein. The HT HP sample cells include a top cell member and a bottom cell member that can be sealed together enclosing a sample in a pressure transmitter chamber. Further, the HT HP sample cells include a compressible, circular internal separator for compressing a sub-mL soft matter liquid sample. Further, the radiation beam windows of the HT HP sample cells are integral to the HT HP sample cell members. The novel and innovative HT HP sample cell design enables SANS measurements of the soft matter liquid sample when exposed to extreme temperatures and pressures without exhibiting leakage or cross-contamination of the soft matter liquid sample with the pressurizing fluid. Methods for using the HT HP sample cells in a pressurizing system for SANS analysis are also disclosed.

A pipeline inspection apparatus for moving through an interior of a pipeline and inspecting a region surrounding the pipeline, comprising a neutron source and scintillator sensors housed within one or more sections and including a positioning system that cooperates to position the one or more sections within the pipeline.

A non-destructive inspection device includes a neutron generation portion, a neutron shield portion, a gamma ray detector, and a gamma ray shield portion. The neutron generation portion emits neutrons spontaneously, or emits neutrons by DD nuclear fusion reaction or DT nuclear fusion reaction. The neutron shield portion is covers the neutron generation portion from at least an area around the neutron generation portion and thereby shields the neutrons at the area, and allows the neutrons to be emitted to a front side of the neutron generation portion. The gamma ray detector detects gamma rays generated in an inspection object on a front side of the neutron generation portion. The gamma rays are generated by the neutrons incident on the inspection object. The neutron shield portion, the gamma ray shield portion, and the gamma ray detector are arranged in this order in alignment with each other in a lateral direction.

A component residual stress testing platform based on neutron diffraction and experimental method thereof are provided, the testing platform includes a component support, a rotating mainshaft, a first thrust cylindrical roller bearing, a first cylindrical roller bearing, a bearing spacing sleeve, a second cylindrical roller bearing, a sleeve, and a first fixed baffle. The rotating mainshaft is disposed on the component support. The first thrust cylindrical roller bearing, the first cylindrical roller bearing, the bearing spacing sleeve and the second cylindrical roller bearing are sleeved on the rotating mainshaft, the sleeve is sleeved outside the first cylindrical roller bearing, the bearing spacing sleeve and the second cylindrical roller bearing, a component to be tested is sleeved on the sleeve. The testing platform can support, move, tilt and rotate the component to be tested in a process of a residual stress testing.

A method for determining a spatial distribution of a radiation damage of a heterogenous material. The steps include some or all of the following. Representing a multiphase microstructure of the heterogenous material as a 2D or 3D image. Determine a first energy of a primary knock-on atom (PKA) ion at a first interface at a first distance from an incident PKA ion to a first phase material of the microstructure image representation. Then determine a second PKA energy in a second phase across a first interface using the first PKA energy and PKA energy-depth-damage profiles of the same PKA in the bulk (isolated) materials of the parent phases. The process is repeated at subsequent interfaces. The radiation damage being determined from the PKA ion energy deposited in each phase material.

A system includes one or more neutron sources configured to emit neutrons. The system also includes one or more electron detectors configured to detect electrons. Further, the system includes a control system comprising one or more processors. The control system is configured to determine a lithium concentration based on the electrons. Further, the control system is configured to generate a lithium extraction output based on the lithium concentration.

A system includes one or more neutron sources configured to emit neutrons. The system also includes one or more electron detectors configured to detect electrons. Further, the system includes a control system comprising one or more processors. The control system is configured to determine a lithium concentration based on the electrons. Further, the control system is configured to generate a lithium extraction output based on the lithium concentration.

A concentration detector includes: a neutron source emitting neutrons to a target; a gamma ray detector detecting and determining an amount of specific gamma rays that are among gamma rays generated in the target by interactions with the neutrons; and a concentration calculator calculating a concentration of the target at selected depths in the inspection target, based on the detected amount. A relational expression expressing a relation between a plurality of concentrations of the target in a plurality of virtual layers and a detected amount of the specific gamma rays is predetermined for each type of the specific gamma rays or each detection condition. The concentration calculator applies the detected amount for each gamma ray type or each detection condition, to the relational expression for the type or the detection condition, and calculates a concentration of the target component in the layer at each depth or the specific depth.