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 Nuclear Energy Conference & Expo (NECX)
August 24–27, 2026
Dallas, TX|Hilton Anatole
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
Second round of Launch Pad selections includes eight newcomers
The National Reactor Innovation Center at Idaho National Laboratory has announced 13 project selections across 12 companies for the Nuclear Energy Launch Pad, a Department of Energy–led program that integrates reactor and fuel facility authorization, testing, and deployment support for private nuclear developers.
The Launch Pad emerged from the Reactor Pilot Program and Fuel Line Pilot Program.
According to INL, projects selected include reactor development and nuclear fuel cycle advancements, including fabrication, enrichment, and conversion technologies.
M. Z. Youssef, A. Kumar, M. A. Abdou, Y. Watanabe, M. Nakagawa, K. Kosako, T. Mori, Y. Oyama, C. Konno, Y. Ikeda, H. Maekawa, T. Nakamura
Fusion Science and Technology | Volume 28 | Number 2 | September 1995 | Pages 243-272
Technical Paper | Fusion Neutronics Integral Experiments — Part II / Blanket Engineering | doi.org/10.13182/FST95-A30645
Articles are hosted by Taylor and Francis Online.
The integral experiments and postanalyses performed in Phase IIC of the U.S. Department of Energy (U.S. DOE)/Japan Atomic Energy Research Institute (JAERI) collaborative program on fusion neutronics focused on test blankets that include the actual heterogeneities found in several blanket designs. In one arrangement, multi-layers of Li2O and beryllium were placed in an edge-on, horizontally alternating configuration, and in the second arrangement, vertical water coolant channels were deployed. The main objective has been to examine the accuracy of predicting key parameters such as tritium production rate (TPR), in-system spectrum, and other reaction rates around these heterogeneities and to experimentally verify the enhancement in TPR by beryllium in the first experiment. The prediction accuracy was examined in terms of calculated-to-experimental values (c/e)i of the neutronics parameters at several spatial locations. Average local (c/e)i values were statistically calculated for TPR from Li-6 (T6) and from Li-7 (T7) in addition to quantifying the prediction uncertainties in the line-integrated TPR. A relationship was developed between the prediction uncertainty in the integrated TPR and the corresponding values in the total breeding zone. This relationship enabled us to identify which subzone contributes the most to the prediction uncertainty in the overall integrated TPR.