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GAO: Clarification of HLW definition could save DOE billions
A clearer definition of what constitutes high-level radioactive waste could save the Department of Energy’s Office of Environmental Management “tens of billions of dollars” in waste management costs and accelerate its cleanup schedule by decades, according to a report by the U.S. Government Accountability Office.
DOE-EM’s efforts to manage waste resulting from legacy spent nuclear fuel reprocessing have been hindered for decades by the ambiguity of the statutory definition of HLW as laid out in the Atomic Energy Act and Nuclear Waste Policy Act, the report states. While admitting that the DOE has taken steps to overcome this ambiguity, the GAO says that the department has not fully evaluated all available opportunities to treat and dispose of waste more economically as either transuranic or low-level radioactive waste.
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.