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Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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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.
L. Rodrigo, J.A. Sawicki, R.E. Johnson
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 1410-1415
Tritium Storage, Distribution, and Transportation | Proceedings of the Fifth Topical Meeting on Tritium Technology In Fission, Fusion, and Isotopic Applications Belgirate, Italy May 28-June 3, 1995 | doi.org/10.13182/FST95-A30609
Articles are hosted by Taylor and Francis Online.
A postmortem analysis of samples of deactivated SAES St707 getter particles recovered from a glove box purification system was conducted to determine the cause for deactivation and eventual hydrogen capacity loss. Unused and used .getter samples were investigated by Auger Electron Spectroscopy (AES) and Mossbauer Transmission Spectroscopy (MTS) of 57Fe. Hydrogen absorption isotherms were measured to determine the extent of the hydrogen capacity loss, and the total impurity (0,N) loading levels were determined by vacuum fusion mass spectrometry. The effect of common gaseous impurities on the tritium-removal characteristics was investigated to determine the nature of impurity-getter interaction for different impurities. Hydrogen capacity loss observed in the purifier was found to be due to bulk nitriding, probably due to irreversible transformation of intermetallic Laves-phase Zr(Fe,V)2 to Zr4Fe2 (O,N)x. The temporary getter deactivation observed during operation of the purifier may have been caused by impurities such as CO, CO2 and volatile organics. Metallic Fe (considered to be responsible for dissociative chemisorption of H2) was found only on unused samples. A gradual loss of metallic Fe from the getter surface could also have contributed to getter deactivation.
