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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
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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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.
Xiao Pan, Xianglin Wu, Geng Fu, James F. Stubbins
Fusion Science and Technology | Volume 52 | Number 3 | October 2007 | Pages 521-525
Technical Paper | The Technology of Fusion Energy - High Heat Flux Components | doi.org/10.13182/FST07-A1541
Articles are hosted by Taylor and Francis Online.
The fatigue and creep-fatigue response of OFHC copper with three different grain sizes has been studied. Tests were carried out at room temperature and hold times were applied at maximum tensile and compressive strain to simulate the creep effect. The results show that fatigue life decreases with increasing grain size for a fixed applied strain range. Hold times resulted in a major reduction in the number of cycles to failure. This reduction was largest at the lowest strain amplitudes and the longest fatigue lives, the region of most interest for component design. The large reduction in fatigue life is apparently due to a change in the crack initiation mode from transgranular in continuous cycle fatigue to intergranular in creep-fatigue conditions.
