研究目的
Investigating the feasibility of gamma emission tomography (GET) for the inspection of spent nuclear fuel, focusing on the verification of the integrity of an assembly and consistency with fissile-material content.
研究成果
The PGET has demonstrated a capability to allow automated detection of single or multiple missing or replaced pins in all fuel types examined to date, offering an exciting new device for safeguards examination of spent nuclear fuel.
研究不足
Improved image reconstruction and analysis routines are still required for optimal performance.
1:Experimental Design and Method Selection:
The study employs a gamma-emission-tomography (GET) system with a discrete array of CdZnTe detectors and a tungsten collimator for parallel-beam line integrals measurement.
2:Sample Selection and Data Sources:
Spent nuclear fuel assemblies with various cooling times and non-fuel items were tested.
3:List of Experimental Equipment and Materials:
CdZnTe detectors, tungsten collimator, watertight stainless steel torus, and data acquisition system.
4:Experimental Procedures and Operational Workflow:
The system is placed in a spent-fuel pond, and the fuel is transported to and lowered into the center of the measurement torus for data collection.
5:Data Analysis Methods:
Image reconstruction and analysis routines are used for automated detection of missing or replaced pins.
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