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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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
Bipartisan Nuclear REFUEL Act introduced in the U.S. House
Peters
Latta
To streamline the licensing requirements for nuclear fuel recycling facilities and help increase investment in nuclear energy in the United States, U.S. Reps. Bob Latta (R., Ohio) and Scott Peters (D., Calif.) have introduced the bipartisan Nuclear REFUEL Act in the House of Representatives.
The bill, introduced on December 6, would amend the definition of “production facility” in the Atomic Energy Act, clarifying that a reprocessing facility producing uranium-transuranic mixed fuel would be licensed only under 10 CFR Part 70. According to the lawmakers, this single-step licensing process would significantly streamline the licensing requirements for fuel recycling facilities.
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.