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.
Explore membership for yourself or for your organization.
Conference Spotlight
2026 ANS Winter Conference & Expo
November 15–18, 2026
Phoenix, AZ|Arizona Grand Resort & Spa
Latest Magazine Issues
Aug 2026
Jan 2026
2026
Latest Journal Issues
Nuclear Science and Engineering
October 2026
Nuclear Technology
September 2026
Fusion Science and Technology
August 2026
Latest News
LLNL, Ampera partner to develop thorium-based TRISO fuel
Lawrence Livermore National Laboratory has formed a strategic partnership with Ampera to develop the company’s nuclear fuel concept through a project named THUNDER, for Thorium Unimodal Droplet Ejection for Reactors.
The focus of THUNDER is fabricating TRISO made with kernels of thorium rather than the usual uranium. LLNL and Ampera will evaluate and optimize liquid metal–jetting technology to produce highly uniform, spherical kernels of thorium-232 for later processing into TRISO fuel.
J. F. Bates, M. K. Korenko
Nuclear Technology | Volume 48 | Number 3 | May 1980 | Pages 303-314
Technical Paper | Material | doi.org/10.13182/NT80-A32477
Articles are hosted by Taylor and Francis Online.
Irradiation-induced swelling in 20% cold-worked Type 316 stainless steel can be described by the use of a bilinear equation with three governing parameters. These parameters are R, a steady-state or linear swelling rate, τ, an incubation parameter denoting a fluence beyond which the linear, or high swelling, portion of the curve is attained, and a, a curvature parameter designating the degree of sharpness by which the equation curves from a region of low swelling to a region of higher swelling. This equation is intended for inclusion in the Nuclear Systems Materials Handbook and was developed with data extending to fluences around 16 × 1022 n/cm2(E> 0.1 MeV). The data set utilized includes first core Fast Flux Test Facility (FFTF) cladding specimens and specimens from several non-FFTF lots of cladding, in addition to supplemental data from an air-melted heat of steel. Heat-to-heat variations in swelling are significant in this material, and separate incubation parameters were developed for different lots of cladding.