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
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
Feb 2025
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
March 2025
Nuclear Technology
Fusion Science and Technology
February 2025
Latest News
Colin Judge: Testing structural materials in Idaho’s newest hot cell facility
Idaho National Laboratory’s newest facility—the Sample Preparation Laboratory (SPL)—sits across the road from the Hot Fuel Examination Facility (HFEF), which started operating in 1975. SPL will host the first new hot cells at INL’s Materials and Fuels Complex (MFC) in 50 years, giving INL researchers and partners new flexibility to test the structural properties of irradiated materials fresh from the Advanced Test Reactor (ATR) or from a partner’s facility.
Materials meant to withstand extreme conditions in fission or fusion power plants must be tested under similar conditions and pushed past their breaking points so performance and limitations can be understood and improved. Once irradiated, materials samples can be cut down to size in SPL and packaged for testing in other facilities at INL or other national laboratories, commercial labs, or universities. But they can also be subjected to extreme thermal or corrosive conditions and mechanical testing right in SPL, explains Colin Judge, who, as INL’s division director for nuclear materials performance, oversees SPL and other facilities at the MFC.
SPL won’t go “hot” until January 2026, but Judge spoke with NN staff writer Susan Gallier about its capabilities as his team was moving instruments into the new facility.
Akiko Hamada, Makoto Kobayashi, Rie Kurata, Masato Suzuki, Hajimu Yamana, Toshiyuki Fujii, Yasuhisa Oya, Kenji Okuno
Fusion Science and Technology | Volume 60 | Number 1 | July 2011 | Pages 399-402
Materials Development & Plasma-Material Interactions | Proceedings of the Nineteenth Topical Meeting on the Technology of Fusion Energy (TOFE) (Part 1) | doi.org/10.13182/FST11-A12388
Articles are hosted by Taylor and Francis Online.
Annihilation behaviors of irradiation defect and, correlation of these behaviors with deuterium trapping and desorption in gamma-ray irradiated Li2TiO3, which is one of the candidates for tritium breeding material, were studied by means of an ESR(Electron Spin Resonance) method and TDS (Thermal Desorption Spectroscopy). From the ESR spectra, gamma-ray irradiation induced irradiation defects such as E'-centers, oxygen-hole centers which were expected to be tritium trapping sites. These irradiation defects were annihilated in the temperature range of 500-650 K. From the TDS spectra for Li2TiO3 exposed to D2 gas, the deuterium desorption behavior was found to consist of four stages, corresponding retention as the surface, in E'-center and as hydroxides bound with Ti or Li. In addition, most of deuterium was released as water form around 400, 550 and 650K. By comparison of the amounts of the deuterium retentions with or without the gamma-ray irradiation, the retention of deuterium trapped with the irradiation defects was increased by gamma-ray irradiation, indicating that the irradiation defects like E'-centers induced by gamma-ray irradiation would be one of the tritium trapping sites in tritium breeding materials. The activation energy of hydrogen isotope desorption from the E'-center was estimated to be 0.63 eV for gamma-ray irradiated Li2TiO3, showing good agreement with that of the recombination reaction between the E'-center and the oxygen-hole center. These results indicated that the tritium desorption was governed by the annihilation of the E'-centers.
