ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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!
Latest Magazine Issues
Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
May 2025
Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Michael J. Morgan, Michael H. Tosten
Fusion Science and Technology | Volume 39 | Number 2 | March 2001 | Pages 590-595
Fusion Materials | doi.org/10.13182/FST01-A11963301
Articles are hosted by Taylor and Francis Online.
Crack initiation and propagation were studied in three tritium-exposed stainless steels. The purpose was to measure cracking thresholds and velocities as a function of helium concentration in Type 21-6-9 stainless steel and compare the results to earlier measurements on Types 316L and 304L steels. Fracture toughness specimens were cut from forgings, fatigue-cracked and exposed to tritium at 423 K and 31 MPa. The samples were aged for selected times at 273 K to “build-in” 3He from tritium decay. Tritium concentrations ranged from 0-2600 atomic parts-per-million (appm) and 3He concentrations ranged from 0-600 appm. The samples were step-loaded at room temperature in air using a screw-driven mechanical testing machine and held at fixed displacement until crack initiation was detected. Crack propagation was monitored by continuously recording the drop in load until crack arrest. Threshold stress intensity was calculated from the load and the crack length at the end of the test. Crack velocities were determined from the load-time records and compliance relationships and verified on some samples using a DC potential-drop technique. The crack path was along grain and twin boundaries. For 21-6-9, the threshold for cracking decreased with increasing helium concentrations from about 90 MPa-m1/2 (50 appm helium) to 25 MPa-m1/2 (600 appm helium). Steady-state-crack velocities averaged 10-7 m/s and was not strongly dependent on helium concentration. The data show that embrittlement of tritium-exposed stainless steels is a form of hydrogen embrittlement made worse by the hardening of the microstructure from nanometer-sized helium bubbles that build-in with tritium decay.