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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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!
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Latest News
High temperature fission chambers engineered for AMR/SMR safety and performance
As the global energy landscape shifts towards safer, smaller, and more flexible nuclear power, Small Modular Reactors (SMRs) and Gen. IV* technologies are at the forefront of innovation. These advanced designs pose new challenges in size, efficiency, and operating environment that traditional instrumentation and control solutions aren’t always designed to handle.
Alberto D. Mendoza España, Daniel Wojtaszek, Ashlea V. Colton, Blair P. Bromley
Nuclear Technology | Volume 203 | Number 3 | September 2018 | Pages 232-243
Technical Paper | doi.org/10.1080/00295450.2018.1447209
Articles are hosted by Taylor and Francis Online.
This study assesses the resource throughput and utilization of various thorium-based fuel concepts for near-term deployment in a pressure-tube heavy water reactor (PT-HWR). Such fuel concepts may be of interest to nations with thorium reserves that are interested in exploiting PT-HWRs. Given that nations with abundant thorium reserves and relatively small uranium reserves have an interest in reducing their dependence on natural uranium (NU) imports, the thorium-based fuel concepts are assessed in terms of their ability to conserve uranium resources and their impact on national income using an economic multiplier analysis. It is found that there are some thorium-augmented and thorium-based fuel concepts that are capable of both conserving resources and reducing reliance on importing NU, which would reduce the negative impact on national income from importing NU. A PT-HWR fuel bundle concept of 1.2 wt% 235U/U + Th (in a central fuel element and small amounts mixed into the outer 36 fuel elements) was found to be the most advantageous and attractive for implementation to improve nuclear fuel resource utilization.