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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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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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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Canada clears Darlington to produce Lu-177 and Y-90
The Canadian Nuclear Safety Commission has amended Ontario Power Generation’s power reactor operating license for Darlington nuclear power plant to authorize the production of the medical radioisotopes lutetium-177 and yttrium-90.
L. Castelnau, T. Desmas, A. M. Lapicore, P. Mainy
Nuclear Technology | Volume 58 | Number 2 | August 1982 | Pages 171-183
Materials Performance in Nuclear Steam Generator | Material | doi.org/10.13182/NT82-A32929
Articles are hosted by Taylor and Francis Online.
Mandatory safety-related design requirements for this type of equipment include essentially the absolute leak-tightness of the heat exchange surfaces separating sodium from water and the prevention of violent sodium-water reactions. After briefly recalling the various situations likely to give rise to leaks, their evolution (self-wastage), and consequences (wastage and secondary ruptures), the precautions taken during steam generator (SG) designing, manufacturing, and operating phases to minimize leak hazards and satisfy the mechanical design basis requirements adopted for secondary loop components are analyzed. The in-service monitoring systems provided (hydrogen detection, acoustic detection) and the means devised to keep leak consequence within acceptable limits (rupture disks) are described. The automatic or operator-controlled actions initiated by signals from these systems are reviewed (reactor shutdown, SG isolation pressure relief, cooling and inertization of sodium or water-steam circuits). Plant overhaul procedures, servicing operations on the SG itself (whipping tube localization, damage assessment on adjoining tubes by insertion of an eddy-current probe, removal of damaged tubes) and on the secondary loop after detection and prior to restartup are presented. For each device and situation mentioned, a comparison is drawn, underlining the fundamental differences existing in the different types of SGs and tube materials.