A device for detecting a contaminant on a scaffolding pole. The device includes an outer detector for detecting a contaminant on an outer surface and an inner detector for detecting a contaminant on an inner surface. The device also includes a mechanism for transporting a scaffolding pole through the device, past the detectors. A contaminant is detected on the outer and inner surfaces of the scaffolding pole using the outer and inner detectors respectively.

A device for detecting a contaminant on a scaffolding pole. The device includes an outer detector for detecting a contaminant on an outer surface and an inner detector for detecting a contaminant on an inner surface. The device also includes a mechanism for transporting a scaffolding pole through the device, past the detectors. A contaminant is detected on the outer and inner surfaces of the scaffolding pole using the outer and inner detectors respectively.

A system for measuring radiation activity of a target radioisotope being produced in a reactor core is disclosed. The system includes a cable assembly and a radiation detector. The cable assembly includes a housing, a target cable configured to position the housing, and a drive cable couplable and decouplable with the target cable. The target radioisotope is positioned within the housing. The drive cable is configured to drive the target cable. The radiation detector configured to periodically measure the radiation activity of the target radioisotope being produced.

A system for measuring radiation activity of a target radioisotope being produced in a reactor core is disclosed. The system includes a cable assembly and a radiation detector. The cable assembly includes a housing, a target cable configured to position the housing, and a drive cable couplable and decouplable with the target cable. The target radioisotope is positioned within the housing. The drive cable is configured to drive the target cable. The radiation detector configured to periodically measure the radiation activity of the target radioisotope being produced.

Provided herein are neutron-based detection systems and methods that provide, for example, high throughput analysis of elemental analysis of scrap materials. Such systems and methods find use for the commercial-scale evaluation of bulk process materials where hazardous or otherwise undesirable materials or high value materials may be interspersed with the primary process material. In certain embodiments, the system is used to detect and potentially remove unexploded ordinance (UXO) from a conveyor of demilitarized shell casings being recycled by detecting the presence of nitrogen and other elements present in the UXO. In other embodiments, the system detects and removes unwanted or highly valuable materials from a stream of scrap material.

Provided herein are neutron-based detection systems and methods that provide, for example, high throughput analysis of elemental analysis of scrap materials. Such systems and methods find use for the commercial-scale evaluation of bulk process materials where hazardous or otherwise undesirable materials or high value materials may be interspersed with the primary process material. In certain embodiments, the system is used to detect and potentially remove unexploded ordinance (UXO) from a conveyor of demilitarized shell casings being recycled by detecting the presence of nitrogen and other elements present in the UXO. In other embodiments, the system detects and removes unwanted or highly valuable materials from a stream of scrap material.

Disclosed is a population and contamination estimation method for severe accidents in nuclear power plants. The population estimation method performed by a population estimation device according to an embodiment may include storing location information of a nuclear power plant on a map and predicting a multi-unit accident occurrence point based on information on a plurality of single units associated with the nuclear power plant stored on the map.

A method including: manufacturing a standard transmission object; simulating a transmission measurement process using simulation calculation method, to establish a database with respect to a transmission thickness, an equivalent water density, an original reconstruction density of the standard transmission object, a space angle cosine of the transmission source and an energy of a γ ray, fitting a corresponding relationship of the space angle cosine of the transmission source with respect to parameters of the standard transmission object and the energy of the γ ray based on the database; selecting a corresponding standard transmission object for transmission measurement for a transmission source to be characterized, to obtain an original reconstruction density of the standard transmission object; reading the space angle cosine of the transmission source to be characterized from the database according to fitted corresponding relationship of known parameters of the standard transmission object and the energy of the γ ray.

A method including: manufacturing a standard transmission object; simulating a transmission measurement process using simulation calculation method, to establish a database with respect to a transmission thickness, an equivalent water density, an original reconstruction density of the standard transmission object, a space angle cosine of the transmission source and an energy of a γ ray, fitting a corresponding relationship of the space angle cosine of the transmission source with respect to parameters of the standard transmission object and the energy of the γ ray based on the database; selecting a corresponding standard transmission object for transmission measurement for a transmission source to be characterized, to obtain an original reconstruction density of the standard transmission object; reading the space angle cosine of the transmission source to be characterized from the database according to fitted corresponding relationship of known parameters of the standard transmission object and the energy of the γ ray.

A method of determining a quantity of a first radioisotope in a source term, disintegrating into a second radioisotope, the radioisotopes respectively emitting first and second gamma rays screened by the source term, the method comprising the steps: a) determining the theoretical ratio of counts between the first and second rays emitted in the absence of screening; b) measuring the net counts associated with the first and second rays emitted by the first and second radioisotopes; c) determining the screening rates of the first and second rays by the source term based on the ratio obtained in step a) and the counts obtained in step b); d) determining the quantity of the first radioisotope based on the screening rate of either the first or the second ray determined in step c).