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Conference Spotlight
2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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
Seconds Matter: Rethinking Nuclear Facility Security for the Modern Threat Landscape
In today’s rapidly evolving threat environment, nuclear facilities must prioritize speed and precision in their security responses—because in critical moments, every second counts. An early warning system serves as a vital layer of defense, enabling real-time detection of potential intrusions or anomalies before they escalate into full-blown incidents. By providing immediate alerts and actionable intelligence, these systems empower security personnel to respond decisively, minimizing risk to infrastructure, personnel, and the public. The ability to anticipate and intercept threats at the earliest possible stage not only enhances operational resilience but also reinforces public trust in the safety of nuclear operations. Investing in such proactive technologies is no longer optional—it’s essential for modern nuclear security.
L. Pantera, Y. Garnier, F. Jeury
Nuclear Science and Engineering | Volume 183 | Number 2 | June 2016 | Pages 247-260
Technical Paper | doi.org/10.13182/NSE15-77
Articles are hosted by Taylor and Francis Online.
The CABRI facility is an experimental nuclear reactor of the French Atomic Energy Commission (CEA) designed to study the behavior of fuel rods at high burnup under reactivity initiated accident conditions, such as a control rod ejection. The distinctive feature of this reactor is its reactivity injection system. The power can rise from 100 kW to 25 GW in a few milliseconds. To know the energy released into a test rod, it is necessary to access the driver core power online. The neutron flux is measured online by compensated boron chambers. These neutron detectors are calibrated during the commissioning phase thanks to standards given by a conventional heat balance. The boron chamber signal depends on the temperature of the pool and the magnitude of the core power according to a nonlinear multivariate model. The uncertainties of the standards and those of the neutron chamber signal cannot be neglected. Moreover, the size of the sample is very small due to the operational constraints. A classic regression method does not take into account all these parameters. In such a situation, we show how the statistical bootstrap method can prove to be a useful and easy tool in tackling this issue. This paper describes first the adjustment of the calibration model that will be used for the prediction during the core power transient and second how we take into account both the uncertainties of the physical variables and the small size of the experimental sample.
