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The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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2024 ANS Annual Conference
June 16–19, 2024
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Fusion Science and Technology
Latest News
Glass strategy: Hanford’s enhanced waste glass program
The mission of the Department of Energy’s Office of River Protection (ORP) is to complete the safe cleanup of waste resulting from decades of nuclear weapons development. One of the most technologically challenging responsibilities is the safe disposition of approximately 56 million gallons of radioactive waste historically stored in 177 tanks at the Hanford Site in Washington state.
ORP has a clear incentive to reduce the overall mission duration and cost. One pathway is to develop and deploy innovative technical solutions that can advance baseline flow sheets toward higher efficiency operations while reducing identified risks without compromising safety. Vitrification is the baseline process that will convert both high-level and low-level radioactive waste at Hanford into a stable glass waste form for long-term storage and disposal.
Although vitrification is a mature technology, there are key areas where technology can further reduce operational risks, advance baseline processes to maximize waste throughput, and provide the underpinning to enhance operational flexibility; all steps in reducing mission duration and cost.
Stanislav P. Simakov, Boris V. Devkin, Michael G. Kobozev, Ulrich von Möllendorff, Dimitriy Yu. Chuvilin
Fusion Science and Technology | Volume 36 | Number 2 | September 1999 | Pages 173-180
Technical Paper | doi.org/10.13182/FST99-A100
Articles are hosted by Taylor and Francis Online.
The results of a transmission experiment on a spherical nickel shell with a 7.5-cm-thick wall and a 14-MeV neutron point source at the center are reported. The neutron leakage spectrum from 14 MeV down to 100 keV was measured by the time-of-flight (TOF) method. Descriptions of the experimental arrangement, TOF spectrometer, measurements, and data-reduction procedures are given. The measured data are compared with results obtained in other laboratories. Three-dimensional Monte Carlo calculations with the MCNP code using the FENDL-1, EFF-2.4, and JENDL-FF nuclear data libraries were made. The FENDL-1 library predicted the neutron leakage from nickel more accurately than the other libraries.
