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Division Spotlight
Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
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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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.
Arsalan Razani, H. E. Hungerford
Nuclear Science and Engineering | Volume 46 | Number 1 | October 1971 | Pages 1-11
Technical Paper | doi.org/10.13182/NSE71-A22330
Articles are hosted by Taylor and Francis Online.
This paper examines a new probabilistic formulation and development of a model for the investigation of three-dimensional gamma-ray transport problems. This model assumes that gamma-ray motion may be sampled at predetermined points. A medium is considered to be filled with a cubic lattice whose unit distance between lattice points may be some fraction of the mean-free-path. The random walk of gamma rays from one point to another is constructed using the lattice framework as reference points. Using this model, a new type of stochastic gamma-ray transport code, PUGT I (Purdue University Gamma Ray Transport I), has been developed based on direct simulation of physical transport process. In another version of the code (PUGT II), capture of gamma rays is taken into account analytically by associating a weight factor to the gamma rays. The codes are used to calculate the transmission and reflection characteristics of gamma rays for different thicknesses of slabs of aluminum and iron. The contribution of annihilation radiation to reflection and transmission is investigated. The results of our calculations are in good agreement with other similar calculations and with experimental results. Gamma-ray streaming through two-legged rectangular concrete ducts was investigated. Results of these studies are in very good agreement with experimental results and demonstrate the ability of the codes and the power of the lattice model to calculate quickly and efficiently the transmission of gamma rays in three-dimensional complex shielding geometries. The method is several times faster than ordinary Monte Carlo.