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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.
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International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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Latest News
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
Timo A. Vanttola, Markku K. Rajamäki
Nuclear Technology | Volume 85 | Number 1 | April 1989 | Pages 33-74
Technical Paper | Nuclear Safety | doi.org/10.13182/NT89-A34225
Articles are hosted by Taylor and Francis Online.
Some of the most frequently presented scenarios for the initial power excursion of the Chernobyl accident are evaluated based on computer simulations. The applied transient model uses one-dimensional descriptions of the reactor core and the main flow circuit. According to the simulations, a slow flow decrease caused by gradual slowing down of the four main circulation pumps could have initiated the accident only if the void reactivity coefficient had been considerably larger than the original Soviet figure. On the other hand, a faster flow reduction, such as pump cavitation or deliberate stopping of even some of the pumps, would have produced enough void for prompt criticality. However, this scenario is sensitive to the size of the void coefficient and to the amount of flow reduction. The most probable initiator was considered to be the positive scram caused by the graphite followers of the manual control rods. Such a mechanism would naturally have brought the additional reactivity to the bottom half of the reactor, and the timing of the power surge would have been the reported one. The simulations indicated that the positive scram was possible only because of the double-humped axial power profile that probably prevailed in the reactor before the accident. The simulations also demonstrated the inability of the shutdown system in this sequence.