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Division Spotlight
Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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
ANS designates Armour Research Foundation Reactor as Nuclear Historic Landmark
The American Nuclear Society presented the Illinois Institute of Technology with a plaque last week to officially designate the Armour Research Foundation Reactor a Nuclear Historic Landmark, following the Society’s decision to confer the status onto the reactor in September 2024.
J. Stepenek, C.E. Higgs, S. Pelloni, J.W. Davidson, D.J. Dudziak
Fusion Science and Technology | Volume 10 | Number 3 | November 1986 | Pages 940-951
Lithium Blanket Module Program at the LOTUS Neutron Source Facility | Proceedings of the Seveth Topical Meeting on the Technology of Fusion Energy (Reno, Nevada, June 15–19, 1986) | doi.org/10.13182/FST86-A24856
Articles are hosted by Taylor and Francis Online.
The irradiation of the LBM at the LOTUS facility is analysed using a three-dimensional model with the Monte Carlo code MCNP and a two-dimensional r-z model with the deterministic transport code TRISM. A sensitivity and uncertainty analysis based on the 2-D model was performed using the sensitivity code SENSIT-2D. The JEF-1/EFF and ENDF/B-V libraries were used for transport calculations. The COVFILS-2 covariance and uncertainty library based on ENDF/B-V was used for sensitivity and uncertainty analyses. A good agreement between JEF-1/EFF and ENDF/B-V libraries was achieved. The uncertainty in the calculated tritium breeding ratio by the indirect term of the overall cross-section uncertainties varies in the dependence on the position in the LBM from 1.4% (front) to 35.8% (back).