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Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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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
College students help develop waste-measuring device at Hanford
A partnership between Washington River Protection Solutions (WRPS) and Washington State University has resulted in the development of a device to measure radioactive and chemical tank waste at the Hanford Site. WRPS is the contractor at Hanford for the Department of Energy’s Office of Environmental Management.
Mikhail Tikhonchev, Artem Muralev, Vyacheslav Svetukhin
Fusion Science and Technology | Volume 66 | Number 1 | July-August 2014 | Pages 91-99
Technical Paper | doi.org/10.13182/FST13-721
Articles are hosted by Taylor and Francis Online.
The present paper is devoted to radiation damage simulation of Fe-9at.%Cr binary alloy with twin grain boundaries (GBs) by the molecular dynamics method. Evaluations of specific energy of five GBs and sizes of corresponding GB regions have been obtained for iron and FeCr alloy at temperatures of 0 and 300 K. The binding energies of the vacancy, self-interstitial atom (SIA) and substitutional Cr atom to the GB in pure Fe have been estimated. The results showed that GB regions are energetically preferable for the point defects. Interaction of 10 keV displacement cascades with the GBs has been studied. The tendency to accumulate at the GB region has been shown for produced defects. Some quantitative results which describe features of radiation damage nearby the GB have been obtained. It is revealed that Cr fraction in SIAs inside the GB region is slightly lower than that in the initial alloy matrix. Cr fraction in interstitial configurations outside the GB region is almost three times as high. However, no remarkable chromium redistribution nearby the GB has been detected.