External Gamma-Ray Detection for Real-Time Reactor Thermal Power
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Solution Overview
Problem
Existing methods for measuring the thermal power of a nuclear reactor are expensive, complex, and require installation inside the reactor vessel, posing challenges for real-time, precise, and safe monitoring.
Innovation Solution
A gamma-ray sensitive detector is placed outside the biological shield of a nuclear reactor, utilizing a gamma-ray sensitive spectrometer to measure gamma-ray counts from neutron absorption in the cooling water, enabling real-time, precise, and non-invasive thermal power determination.
Engineering Contradictions & Design Principles
Engineering Contradiction Analysis
1Measurement precision
If detectors are installed inside or near the reactor vessel to measure thermal power, then measurement precision is improved, but device complexity and accessibility deteriorate
Solution Approach 1:
The detector is extracted from the reactor vessel interior and relocated to the exterior, specifically to a position behind the biological shield. This eliminates the need for complex internal installation while maintaining measurement capability through detection of gamma rays that penetrate the shield.
Solution Approach 2:
Gamma rays serve as an intermediary carrier to transmit information about the thermal power from the reactor core through the biological shield to the external detector. This mediator enables non-invasive measurement without direct contact with the reactor interior.
2Loss of time
If detectors are installed inside the reactor vessel for real-time measurement, then real-time measurement capability is improved, but ease of operation and maintenance deteriorate
Solution Approach 1:
The detector is moved from the reactor interior to the exterior behind the biological shield, enabling easy access for operation and maintenance while maintaining real-time measurement capability through continuous detection of penetrating gamma radiation.
3Measurement precision
If standard measurement methods are used with complex apparatus, then measurement capability is improved, but cost and device complexity increase
Solution Approach 1:
The system uses a relatively simple and inexpensive gamma-ray detector rather than complex neutron detectors or elaborate heat flow measurement systems. The detector can be a standard scintillation or semiconductor detector, significantly reducing cost while maintaining measurement precision.
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
The method provides high-precision, real-time thermal power measurements without the need for invasive access to the reactor, ensuring safety and reliability, and is cost-effective with minimal maintenance.
Implementation Method 1
measuring the thermal power of a nuclear power plant with a gamma-ray sensitive detector that is placed outside a biological shield of a nuclear reactor core
Data Source
AI summary
A method for determining real-time thermal power of a nuclear reactor based on number of gamma rays counted comprising measuring a number of gamma-ray counts by a gamma-ray detector that is placed outside a biological shield at a primary cooling circuit of a fission nuclear power plant so that maintenance of the detector is possible during normal operation of the fission nuclear power plant, and determining, by a computing device in real-time, a thermal power of the fission nuclear power plant based on the number of gamma-ray counts measured by the gamma-ray detector.