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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
May 2025
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Industry Update—May 2025
Here is a recap of industry happenings from the recent past:
TerraPower’s Natrium reactor advances on several fronts
TerraPower has continued making aggressive progress in several areas for its under-construction Natrium Reactor Demonstration Project since the beginning of the year. Natrium is an advanced 345-MWe reactor that has liquid sodium as a coolant, improved fuel utilization, enhanced safety features, and an integrated energy storage system, allowing for a brief power output boost to 500-MWe if needed for grid resiliency. The company broke ground for its first Natrium plant in 2024 near a retiring coal plant in Kemmerer, Wyo.
Claus Petersen, Gerhard Schanz, Siegfried Leistikow
Nuclear Technology | Volume 80 | Number 1 | January 1988 | Pages 161-172
Technical Paper | Advanced Light Water Reactor / Fission Reactor | doi.org/10.13182/NT88-A35556
Articles are hosted by Taylor and Francis Online.
To investigate the potential of the austenitic 15Cr-15Ni steel DIN Material No. 1.4970 as fuel cladding material for an advanced pressurized water reactor (APWR), rod and tube samples were mechanically tested under inert and oxidizing conditions by uniaxial loading and internal pressure up to 1200°C, to receive recent information about its safety potential under emergency cooling conditions. Uniaxial strength values are not influenced by test atmosphere. The total strain is quite low up to 950°C and increases sharply above this temperature to a maximum of ∼80% at 1100°C. The uniaxial creep strength shows a transition to more pronounced temperature and time dependence at 800°C, which is due to recrystallization. Creep rupture strain, which remains around 20% below 950°C, rises above that temperature to a level of 80 to 90%. Steam oxidation slightly decreases burst creep strength, mainly due to metal consumption, and markedly decreases the circumferential strain, especially due to the pronounced tendency to localized deformation at cracks through the defective oxide scale. Even then the circumferential strain of steel tubes is not small enough to meet reactor safety considerations with respect to the emergency cooling of a densely packed APWR core.