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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
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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Strontium: Supply-and-demand success for the DOE’s Isotope Program
The Department of Energy’s Isotope Program (DOE IP) announced last week that it would end its “active standby” capability for strontium-82 production about two decades after beginning production of the isotope for cardiac diagnostic imaging. The DOE IP is celebrating commercialization of the Sr-82 supply chain as “a success story for both industry and the DOE IP.” Now that the Sr-82 market is commercially viable, the DOE IP and its National Isotope Development Center can “reassign those dedicated radioisotope production capacities to other mission needs”—including Sr-89.
Shigeyuki Nakanishi, Takusaburo Hosoya, Shigenobu Kubo, Shoji Kotake, Misao Takamatsu, Takafumi Aoyama, Iwao Ikarimoto, Jungo Kato, Yoshio Shimakawa, Kiyoshi Harada
Nuclear Technology | Volume 170 | Number 1 | April 2010 | Pages 181-188
Technical Paper | Special Issue on the 2008 International Congress on Advances in Nuclear Power Plants / Nuclear Plant Operations and Control | doi.org/10.13182/NT10-A9456
Articles are hosted by Taylor and Francis Online.
A sodium-cooled fast reactor (SFR) self-actuated shutdown system (SASS) is a passive safety feature by which control rods are inserted by gravity force and the rods would be detached by a rise in coolant temperature under anticipated transient without scram (ATWS) conditions. Various out-of-pile tests have already been carried out to investigate the basic characteristics of SASS, and a demonstration test of the holding stability under reactor operation conditions has been performed, where a function test of the driving system to reconnect and pull out the control rod has been done in the experimental reactor JOYO. Element irradiation tests have also been conducted to confirm that there is no impact from irradiation. The effectiveness of SASS for the reference core design of the Japan SFR (JSFR) has been evaluated through all ATWS types. As a result, it is ensured that JSFR will have a reliable passive shutdown system.