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Division Spotlight
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 Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
Standards Program
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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Latest News
Tank waste operations resume at Idaho’s IWTU
The Department of Energy’s Office of Environmental Management announced yesterday that waste processing operations have resumed at the Integrated Waste Treatment Unit (IWTU) at the Idaho National Laboratory Site. The resumption of operations follows the completion of two maintenance campaigns at the radioactive liquid waste treatment facility.
Sümer Sahin, Ralph W. Moir, Abdulmuttalip ŞAHINASLAN, Haci Mehmet ŞAHIN
Fusion Science and Technology | Volume 30 | Number 3 | December 1996 | Pages 1027-1035
Fusion Blanket and Shield Technology | doi.org/10.13182/FST96-A11963072
Articles are hosted by Taylor and Francis Online.
Material damage through displacements per atom (DPA) and helium gas production, as well as the tritium breeding and energy absorption in an IFE (Inertial Fusion Energy) reactor chamber have been investigated with variable coolant zone thickness using different liquids. Examples are given for HYLIFE-II (an IFE reactor design) energy conversion chambers using Flibe (Li2BeF4), natural lithium and Li17Pb83 cutectic as both coolant and wall protection. To achieve a useful energy density for energy conversion purposes with sufficient tritium breeding (TBR= 1.1), material protection (DPA < 100 and He < 500 appm in 30 years of operation) and shallow burial criteria, coolant zone thickness values are found to be 56 cm for Flibe, 160 cm for natural lithium and 170 cm for Li17Pb83 with SS-304 as structural material.
Material damage investigations are extended to structural materials made of SiC and graphite for the same blanket. DPA values and He production rates in graphite turn out to be comparable to those in SS-304. However, they are higher in SiC, as compared to SS-304 and graphite.