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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.
Materials in Nuclear Energy Systems (MiNES 2023)
December 10–14, 2023
New Orleans, LA|New Orleans Marriott
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
ENEC inks deal with Kazatomprom, MOUs with TerraPower, GEH
On the margins of the COP28 climate conference in Dubai, UAE, this week, Barakah nuclear plant owner Emirates Nuclear Energy Corporation (ENEC) signed its first commercial uranium fuel supply contract with Kazatomprom, in addition to memorandums of understanding with two U.S.-based advanced reactor developers—TerraPower and GE Hitachi Nuclear Energy (GEH).
Technical Session|Sponsored by RPD
Friday, December 3, 2021|3:05–4:50PM EST |Columbia 4
Zeyun Wu (VCU)
K. Lisa Reed
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Revisit of the Dancoff-Based Wigner-Seitz Approximation for Pointwise and Multigroup Resonance Self-Shielding Calculations in SCALE
Kang Seog Kim (ORNL), Andrew M. Holcomb (ORNL), Matthew A. Jessee (ORNL), William A. Wieselquist (ORNL)
Serpent/PARCS Calculation for VVER-1000 Core with TriPEN-9 Method
Muhammad Rizki Oktavian (Purdue Univ.), Oscar Lastres (Purdue Univ.), Yunlin Xu (Purdue Univ.)
In-situ APEC Leakage Correction Based on 2x2 Nodal Analysis for 2-D Macroscopic Depletion Calculation
Seongdong Jang (KAIST), Yonghee Kim (KAIST)
An Introduction to REX: A Fuel-Clad Thermo-Mechanical Analysis Tool for Advanced Reactor Concepts
Nicholas J. Fassino (Georgia Institute of Technology), Anna Erickson (Georgia Institute of Technology)
A Feasibility Study of SPH Factors for a Heterogeneous Geometry Problem
Zhaopeng Zhong (ANL), Changho Lee (ANL)
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