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Division Spotlight
Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
Four million nuclear jobs by 2050: Who will do them?
Industry leaders from around the globe met this month to discuss the talent development that will be necessary for the long-term success of the nuclear industry.
The International Conference on Nuclear Knowledge Management and Human Resources Development, hosted by the International Atomic Energy Agency, was held in Vienna earlier this month. Discussed there was the agency’s forecast for nuclear capacity to more than double—or hopefully triple—by 2050 and the requirement of more than four million professionals to support the industry.
Alireza Behbahani, Don W. Miller
Nuclear Technology | Volume 67 | Number 1 | October 1984 | Pages 14-22
Technical Paper | Fission Reactor | doi.org/10.13182/NT84-A33525
Articles are hosted by Taylor and Francis Online.
An analytical neutron sensor response model and methods for measurement of neutron sensor (compensated ionization chamber) transient response have been developed and evaluated. In situ measurement methods to meet the provisions of the Instrument Society of America Draft Standard dS67.06, Institute of Electrical and Electronics Engineers 338-1977, and U.S. Nuclear Regulatory Commission Guide 1.118 are included. In one in situ method, the high-voltage sensor power supply is perturbed and subsequent sensor response measured. The response is analytically and experimentally related to the response of the sensor to a transient change in radiation flux. Random signal analysis was a second in situ technique evaluated to monitor the transient response of the neutron sensor. In this method the power spectrum of the inherent random fluctuations from the neutron sensor output is measured and analyzed. Transient response was experimentally and analytically evaluated to identify mechanisms that may cause degradation in the response of neutron sensors. Response time degradation was investigated by changing the sensor and signal cable response time in a predictable manner (through changes in the detector fill gas and the use of a delay line and different terminations in series or parallel with the signal cable). Sensors and attached cables having different response times were evaluated using power supply perturbation, transient change in radiation flux, and analysis of the random signals from the neutron sensor. The primary objectives of the experimental evaluation were to correlate the measured response time using transient radiation flux changes with response to a power supply perturbation and to confirm the analytical model. The primary objectives of developing the analytical model of sensor response were to predict response time and to evaluate degradation mechanisms. It is shown that degradation in neutron sensor response time, which may not be significant to the operation of a reactor protection system, is related to degradation in sensitivity and linearity, and that simulated degradation in response time can be detected through the two techniques developed.