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Division Spotlight
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.
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
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Ding She, Ang Zhu, Kan Wang
Nuclear Science and Engineering | Volume 175 | Number 3 | November 2013 | Pages 259-265
Technical Paper | doi.org/10.13182/NSE12-48
Articles are hosted by Taylor and Francis Online.
Burnup calculations consider the time dependence of the material composition or isotope inventory, which has important influence on the neutronic properties of a nuclear reactor. An essential part of burnup calculations is to solve the burnup equations, which can be approximately treated as a first-order linear system and can be solved by means of matrix exponential methods. However, because of the large decay constants of short-lived nuclides, the coefficient matrix of the burnup equations has a large norm and a vast range of spectra. Consequently, it is quite difficult to directly compute the matrix exponential using conventional methods such as the truncated Taylor expansion and the Pade approximation. Recently, the Chebyshev rational approximation method (CRAM), which is based on rational functions on the complex plane, has shown the capability to deal with this problem. In this paper an alternative method based on the generalized Laguerre polynomials is proposed to compute the exponential of the burnup matrix. Against CRAM, the Laguerre polynomial approximation method (LPAM) has simple recursions for obtaining the coefficients in any order, and all the computations are real arithmetic. A point burnup case and a pin-cell burnup case are calculated for validation, and results show that LPAM is promising for burnup calculations.