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GAIN makes diverse selections for its third round of awards this year
The Department of Energy’s Gateway for Accelerated Innovation in Nuclear has recently awarded four third-round fiscal year 2026 vouchers to support the development of innovative nuclear technologies. Each company will get access to specific capabilities and expertise in the DOE’s national laboratory complex—in this round of awards Idaho National Laboratory, Oak Ridge National Laboratory, and Sandia National Laboratories are named—and will be responsible for a minimum 20 percent cost share, which can be an in-kind contribution.
David W. Nigg, Floyd J. Wheeler
Fusion Science and Technology | Volume 1 | Number 1 | January 1981 | Pages 90-98
Technical Paper | Fusion | doi.org/10.13182/FST81-A19918
Articles are hosted by Taylor and Francis Online.
The Poloidal Diverter Experiment (PDX) facility at Princeton University is the first operating tokamak to require substantial radiation shielding. A calculational model has been developed to estimate the radiation dose in the PDX control room and at the site boundary due to the skyshine effect. An efficient one-dimensional method is used to compute the neutron and capture gamma leakage currents at the top surface of the PDX roof shield. This method employs an Sn calculation in slab geometry and, for the PDX, is superior to spherical models found in the literature. If certain conditions are met, the slab model provides the exact probability of leakage out the top surface of the roof for fusion source neutrons and for capture gamma rays produced in the PDX floor and roof shield. The model also provides the correct neutron and capture gamma leakage current spectra and angular distributions, averaged over the top roof shield surface. For the PDX, this method is nearly as accurate as multidimensional techniques for computing the roof leakage and is much less costly. The actual neutron skyshine dose is computed using a Monte Carlo model with the neutron source at the roof surface obtained from the slab Sn calculation. The capture gamma dose is computed using a simple point-kernel single-scatter method.