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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
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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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Crude oil transportation: Pick your poison
We all know that nuclear energy is the best energy source available—the safest and most reliable with the lowest life-cycle carbon footprint and the lowest environmental impact of any source, according to the latest UN report (unece.org/sites/default/files/2021-11/LCA_final.pdf).
L. P. Leach, L. J. Ybarrondo, G. D. McPherson
Nuclear Technology | Volume 33 | Number 2 | April 1977 | Pages 126-149
Technical Paper | Reactor | doi.org/10.13182/NT77-A31772
Articles are hosted by Taylor and Francis Online.
The first two loss-of-coolant experiments have been performed in the Loss-of-Fluid Test (LOFT) Facility. The experimental results are compared to analytical model results from the RELAP4 computer code. LOFT is a pressurized water reactor specially designed and instrumented to perform experiments representative of a loss-of-coolant accident (LOCA) in a power reactor. For these first two experiments, the nuclear core was not installed in LOFT. The first experiment was initiated from a pressure of 9.3 MPa with water at 282°C, and the break represented a half-size double-ended offset shear in the hot leg of a power reactor. The second experiment was initiated from a pressure of 15.3 MPa, a temperature of 282°C, and simulated a complete double-ended offset shear in the cold leg of a power reactor. In the first experiment, emergency core cooling was injected by low-pressure, high-pressure, and accumulator emergency core cooling systems at times representative of what would occur in a LOCA in a power reactor.