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. Russell Hawthorne
Nuclear Technology | Volume 59 | Number 3 | December 1982 | Pages 440-455
Technical PaperTechnical Paper | The Backfill as an Engineered Barrier for Radioactive Waste Management / Material | doi.org/10.13182/NT82-A33002
Articles are hosted by Taylor and Francis Online.
The effects of three levels of copper content and phosphorus content and two levels of sulfur content on radiation sensitivity and postirradiation heat treatment response were explored for a reactor pressure vessel steel, Type A302-B. Test plates for the investigation were produced from 182-kg (400-lb) laboratory melts. The contributions of individual elements were assessed from Charpy-V (CV) notch ductility changes with 288°C (550°F) irradiation and with a 343°C (650°F), 168-h postirradiation heat treatment. Limited studies of properties recovery by postirradiation 399°C (750°F) heat treatment were also made. Radiation embrittlement sensitivity, as shown by CV transition temperature elevation and CV upper shelf reduction, generally increased with increased copper and phosphorus content and with decreased sulfur content. Certain ranges of phosphorus and copper content were found to be more critical than others. Response to 343°C (650°F) postirradiation heat treatment, as evidenced by transition temperature recovery in degrees Celsius, appeared to be independent of copper, phosphorus, and sulfur content for the ranges investigated. Response to heat treatment also appeared to be independent of the magnitude of the prior transition temperature elevation by irradiation. On the other hand, a dependence of percentage recovery on impurity element content was observed. A dependence of upper shelf recovery on copper content was also found. Six of the eight plate compositions exhibited full upper shelf recovery but only small transition temperature recovery after 343°C (650°F) heat treatment.