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The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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2024 ANS Annual Conference
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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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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.
David P. Hartmangruber, Bojan Petrovic
Nuclear Technology | Volume 175 | Number 1 | July 2011 | Pages 187-197
Technical Paper | Special Issue on the 16th Biennial Topical Meeting of the Radiation Protection and Shielding Division / Radiation Transport and Protection | doi.org/10.13182/NT10-165
Articles are hosted by Taylor and Francis Online.
IRIS is an advanced, smaller-power pressurized water reactor, with aggressive dose reduction objectives. Because of its integral configuration, IRIS has a thick downcomer region that significantly reduces the radiation field outside the reactor vessel, forming the technical basis for achieving the objectives. However, this feature also makes the shielding analysis very challenging. The goal of evaluating the dose rate distribution throughout the IRIS nuclear power plant and, in particular, in all accessible areas further amplifies the problem.The MAVRIC sequence of the SCALE6 code system was selected for this analysis. MAVRIC employs a hybrid deterministic-stochastic approach, with CADIS and Forward-CADIS methods being used to develop variance-reduction parameters for Monte Carlo simulations. MAVRIC was successfully applied to determine the dose rate distribution throughout a large portion of the IRIS nuclear power plant including the control room. The obtained results confirmed that the dose rate is below the set target limit in the relevant plant areas and, in particular, in the control room.