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Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Nuclear and Emerging Technologies for Space (NETS 2023)
May 7–11, 2023
Idaho Falls, ID|Snake River Event Center
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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Nuclear Science and Engineering
Fusion Science and Technology
Wanted: Information leading to a neutron source for fusion energy R&D
The Department of Energy’s Office of Science published a notice in the March 27 Federal Register calling for input on technological approaches to a Fusion Prototypic Neutron Source (FPNS) for materials irradiation research under DOE-SC’s Fusion Energy Sciences program, as well as partnership models that could accelerate the construction and delivery of the facility. The request for information (RFI) calls for responses by May 11.
Thursday, October 7, 2021|8:30–10:10AM EDT
Bojan Petrovic (Georgia Institute of Technology)
Terry S. Haut (LLNL)
Nicholas Herring (Univ. of Michigan)
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Robust Relaxation-Free Multiphysics Simulations via Power-Iteration-Level-Coupled CMFD Acceleration in MPACT
Qicang Shen (Univ. of Michigan), Sooyoung Choi (Univ. of Michigan), Brendan Kochunas (Univ. of Michigan)
Frequency Transform Method for Transient Analysis of Nuclear Reactors
Miriam A. Kreher (MIT), Samuel Shaner (C-Zero), Benoit Forget (MIT), Kord Smith (MIT)
Reduced-Order Modeling of Coupled Neutronics and Fluid Dynamics in the Zero-Power Molten Salt Fast Reactor
Peter German (Texas A&M Univ.), Mauricio E. Tano (Texas A&M Univ.), Jean C. Ragusa (Texas A&M Univ.)
The NILO-CMFD Method for Iteratively Solving Multiphysics Neutron Transport - Thermal Hydraulic Problems
Nickolas J. Adamowicz (Univ. of Michigan), Annalisa Manera (Univ. of Michigan), Edward W. Larsen (Univ. of Michigan)
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