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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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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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Latest News
Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
Dong-Seong Sohn, Gordon E. Kohse, David M. Parks, Otto K. Harling
Nuclear Technology | Volume 92 | Number 3 | December 1990 | Pages 383-388
Technical Paper | Material | doi.org/10.13182/NT90-A16239
Articles are hosted by Taylor and Francis Online.
Considerable effort is currently being expended to develop mechanical property tests for various miniature specimens. Bend tests of thin 3-mm-diam disks (standard transmission electron microscopy specimens) have been used by various workers. A miniaturized disk bend test (MDBT) using a 3-mm-diam x 0.25-mm-thick disk is described and recent progress in extracting uniaxial yield stress values from bend test data is discussed. The method is based on the existence of an initial linear region in the load/deflection curve generated by the bend test. A strong relationship between the load at deviation from linearity and the uniaxial yield stress is found. By simulating observed load/deflection curves using a finite element stress/strain analysis, yield stresses can be calculated from MDBT data. Results using our approach to MDBT for a range of materials are presented, and good agreement with uniaxial tensile test data is shown. These results for the small specimen volume required for MDBT offer interesting possibilities for monitoring the mechanical properties of in-service structures, as well as for minimizing test volumes and specimen radioactivities in such programs as alloy development for irradiation performance in fusion reactors.