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.
T. M. Krishnamoorthy, S. N. Joshi, G. R. Doshi, R. N. Nair
Nuclear Technology | Volume 104 | Number 3 | December 1993 | Pages 351-357
Technical Paper | Special Issue on Waste Management / Radioactive Waste Management | doi.org/10.13182/NT93-A34896
Articles are hosted by Taylor and Francis Online.
Leach characteristics of some typical nuclides such as cesium, strontium, cobalt, I−, and CO3−2 from ordinary portland cement waste forms have been studied using the ISO test method and radiotracers of the respective nuclides, i.e., 134Cs, 85Sr, 60Co, 131I, and 14C. The leach studies suggest a rapid release of radioactivity in the beginning (fast component) followed by slow release for long periods of time (slow component). A mathematical model has been simulated to describe the leaching kinetics of these nuclides from the cement matrix. The effective diffusion coefficient Deff is computed from the two componental diffusion coefficients, and the retardation factor (α) for a nuclide is evaluated from a knowledge of the radioactivity distribution in the aqueous and solid phase at equilibrium. The product αDeff for all the nuclides studied has been found to be approximately constant and is equal to the intrinsic diffusion coefficient in the cement matrix. The net fractional release of different radionuclides from cement waste form showed a decreasing pattern, i.e., 134Cs > 131I > 85Sr > 14Cr > 60Co indicating the largest diffusion coefficient for cesium as 10−2 cm2/day and the least for 14C as 3 × 10−8 cm2/day.