Movable Detector Modules for Radioactive Waste Nuclide Analysis
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Solution Overview
Problem
Current non-destructive nuclide analysis equipment is limited in its ability to efficiently measure and analyze radioactive waste packed in large or varied-sized containers, such as ISO containers, which are commonly used during nuclear power plant decommissioning, due to inefficiencies in handling and analyzing waste containing concrete and metal in large quantities.
Innovation Solution
A non-destructive measurement apparatus that adjusts the position of detector modules based on container size and characteristics, using paired upper and lower detector modules with radiation detectors and collimators to collect data in opposite directions, allowing for accurate nuclide analysis and concentration measurement regardless of container size.
Engineering Contradictions & Design Principles
Engineering Contradiction Analysis
1Productivity
If standard drum containers (200L or 320L) are used for radioactive waste packaging, then non-destructive nuclide analysis equipment can efficiently measure and analyze the waste, but the handling and analysis of large quantities of decommissioning waste becomes inefficient and economically problematic
Solution Approach 1:
The detector module is designed to be movable rather than fixed, allowing it to adjust its position according to different container sizes. The module can be moved closer to or farther from the container, and its angular position can be changed to optimize measurement geometry for various container dimensions, thereby maintaining measurement efficiency across different scales.
Solution Approach 2:
The system changes measurement parameters including detector-to-container distance, detector angular position, and measurement time based on container size. By dynamically adjusting these parameters, the system maintains optimal measurement conditions whether measuring small drum containers or large ISO containers.
2Productivity
If large-capacity containers (including ISO containers) are used to pack decommissioning waste, then waste disposal efficiency improves, but existing non-destructive nuclide analysis equipment cannot effectively measure and analyze the waste in these containers
Solution Approach 1:
The detector module's movable design enables it to achieve optimal measurement positions for large containers that would be impossible with fixed equipment. The module can be positioned closer to the container walls and adjusted to various angles to penetrate through the container contents effectively.
Solution Approach 2:
The system utilizes angular positioning in addition to radial distance adjustment, creating a two-dimensional adjustment space for the detector module. This allows the detector to approach the container from different angles, improving penetration through large container volumes and enhancing measurement capability.
3Device complexity
If the detector module position is fixed, then the equipment structure is simpler, but the equipment cannot adapt to different container sizes and measurements become inaccurate
Solution Approach 1:
The detector module is equipped with movable mechanisms including radial adjustment and angular positioning capabilities. These dynamic features allow the same equipment structure to adapt to various container sizes without requiring multiple specialized devices.
Solution Approach 2:
The detector module is designed as a universal component that can measure various container types (drum containers, large-capacity containers, ISO containers) through its adjustable positioning system, eliminating the need for multiple specialized measurement devices.
4Measurement precision
If measurement time is increased to improve analysis accuracy for large containers, then nuclide detection precision improves, but productivity decreases
Solution Approach 1:
The movable detector module can dynamically adjust its distance from the container and angular position to optimize measurement geometry. By positioning the detector closer to the container or at optimal angles, the system achieves better signal-to-noise ratios and measurement precision in shorter time periods.
Solution Approach 2:
The system adjusts measurement parameters including detector position, angular orientation, and measurement duration based on container characteristics. For large containers, the system can reduce measurement time by positioning the detector optimally rather than relying solely on extended measurement durations.
Applied Scientific Principles
This section explains which scientific principles are used to turn an abstract innovation direction into a practical engineering solution.
Function Achieved in This Case
Enables nuclide analysis on containers of various sizes by optimizing detector placement and data collection, improving measurement efficiency and accuracy through attenuation correction, thus addressing the limitations of existing systems.
Implementation Method 1
a radiation detector to measure radiation generated from the waste held in the packing container
Implementation Method 2
equipped with a collimator
Data Source
AI summary
An apparatus for analyzing nuclides and the concentration thereof in waste contained in a radioactive waste packaging container according to the present disclosure relates to an apparatus that has detector devices located above/under the waste packaging container and performs nuclide and concentration analysis on the waste in the packaging container by scanning the packaging container in the longitudinal direction thereof using a forward/backward driving device. In particular, upper/lower detector modules are equipped with multiple high-resolution gamma ray detectors to increase inspection efficiency, each module is designed to be driven up/down, and each detector in the module is designed to be driven left/right, thereby performing nuclide and concentration analysis on various types of packaging containers regardless of the size thereof.