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.
S. V. Panno*, P. Soo
Nuclear Technology | Volume 67 | Number 2 | November 1984 | Pages 268-281
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT84-A33516
Articles are hosted by Taylor and Francis Online.
A study was conducted to investigate the possible changes in brine chemistry and alkalinity in a highlevel nuclear waste salt repository caused by the interaction of brine with gamma-irradiated host rock. The technique employed involves measurements of the pH and total base in solution of brines made from rock salt irradiated to doses between 107 and 1010 rad under various environmental conditions. The results show that the pH and total base of the brines increase with increasing irradiation of the parent rock salt. Rock salt samples, irradiated in the dry condition at 40°C, produce brines with pH and total base values that increase from 7.25 pH units and 0.14 microequivalent/gram (µeq/g) to upper limits of 9.25 pH units and 1.2 µeq/g, respectively. Samples, irradiated dry at 125 °C, produce brines with pH and total base values that increase to 9.60 pH units and 35 µeq/g, respectively. The increase in total base in the aforementioned brines is indicative of F-center formation (at 40°C) and sodium-colloid formation (at 125°C) in the salt. Saturated brines irradiated in the presence of rock salt at 125 °C, however, became progressively more acidic while brines made from the adjacent rock salt became increasingly basic. With respect to the high and low pH brines that may be adjacent to waste packages, corrosion resistance of metal containers and the leachability of the waste form may be compromised. Additional data will be required to quantify the behavior of these components under anticipated repository conditions.