Drying Spent Nuclear Fuel Using Gas Spectroscopy
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Solution Overview
Problem
Current methods for drying spent nuclear fuel canisters are time-consuming, prone to errors, and expose workers to radiation, as they require manual vacuum monitoring and complex equipment setups to achieve the necessary low vapor pressure for safe storage and transportation.
Innovation Solution
An apparatus using gas spectroscopy to evaluate drying characteristics, selectively circulating non-reactive gases through contaminated or non-contaminated circulation systems to determine the dryness of the canister and prevent radiation exposure, while automatically controlling the drying process.
Engineering Contradictions & Design Principles
Engineering Contradiction Analysis
1Reliability
If manual vacuum monitoring and complex equipment setups are used to achieve low vapor pressure, then the drying safety and reliability are improved, but the device complexity and operation difficulty increase
Solution Approach 1:
The patent replaces manual vacuum monitoring and complex mechanical equipment with a gas spectroscopy-based detection system. The spectroscopy device directly measures water content in the canister by analyzing gas absorption spectra, eliminating the need for complex vacuum equipment and manual monitoring procedures, thereby maintaining drying safety while significantly reducing device complexity
Solution Approach 2:
The patent introduces a gas spectroscopy device as an intermediary measurement tool. Instead of directly measuring vapor pressure through complex vacuum systems, the spectroscopy device measures water content through gas absorption spectra, serving as a simpler intermediary that provides the necessary safety information with reduced equipment complexity
2Measurement precision
If manual vacuum monitoring is used to ensure proper drying, then the measurement accuracy is improved, but the time consumption and productivity decrease
Solution Approach 1:
The patent replaces manual vacuum monitoring with automated gas spectroscopy measurement. The spectroscopy device automatically measures water content by analyzing the absorption spectra of water vapor in the canister headspace, providing accurate drying assessment without manual intervention, thereby maintaining measurement precision while significantly improving productivity
Solution Approach 2:
The gas spectroscopy device performs self-measurement of water content by directly analyzing the gas phase inside the canister. The system automatically determines drying status without requiring external manual monitoring or complex vacuum setups, achieving both high measurement precision and operational efficiency
3Measurement precision
If complex equipment setups are used for drying monitoring, then the measurement precision is improved, but the radiation exposure risk to workers increases
Solution Approach 1:
The patent replaces complex vacuum monitoring equipment with a gas spectroscopy system that can measure water content through the canister wall or through a simple gas sampling port. This substitution eliminates the need for workers to be present in high-radiation areas for equipment setup and monitoring, maintaining measurement precision while reducing radiation exposure risk
Solution Approach 2:
The gas spectroscopy device acts as an intermediary measurement tool that can obtain drying information without direct contact with the spent nuclear fuel. By measuring water content through gas absorption spectra from the canister headspace, the system provides accurate drying assessment while keeping workers away from radiation sources
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
This approach allows for quick and accurate determination of dryness, minimizing radiation exposure and equipment complexity, enabling efficient and safe drying of spent nuclear fuel canisters.
Implementation Method 1
a parameter of drying operation characteristic is extracted from a signal outputted from a gas spectroscopy that directly measures a hot non-reactive gas discharged from a gas outlet port of the canister
Data Source
AI summary
Apparatus and method for drying spent nuclear fuel loaded in a cavity of a canister. A non-reactive gas discharged from the canister is selectively circulated through one of a contaminated circulation system and a non-contaminated circulation system according to a measured radiation dose rate.