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Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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
First astatine-labeled compound shipped in the U.S.
The Department of Energy’s National Isotope Development Center (NIDC) on March 31 announced the successful long-distance shipment in the United States of a biologically active compound labeled with the medical radioisotope astatine-211 (At-211). Because previous shipments have included only the “bare” isotope, the NIDC has described the development as “unleashing medical innovation.”
Y. Y. Chang, S. K. Loyalka
Nuclear Science and Engineering | Volume 77 | Number 2 | February 1981 | Pages 235-250
Technical Note | doi.org/10.13182/NSE81-A21357
Articles are hosted by Taylor and Francis Online.
A computer code TWOLASER has been developed for neutronic calculations of square lattice cells in nuclear power reactors. The computer code, which uses new methods for solutions of the integral transport equation and burnup equations, has been used to assess the accuracy and speed of the LASER code. The new code considers actual two-dimensional geometry of the cell as compared to the one-dimensional approximation used by LASER. Calculations have been performed on a sample problem for a burnup of 10.6 MWd/kg fissile. Results from these calculations show that the one-dimensional approximation used by LASER is good for the sample problem. However, the method used by LASER for the solution of burnup equations is not efficient. A modified version, MLASER, of the LASER code has also been developed in this research. This version uses the one-dimensional approximation of LASER and the new method for the solution of burnup equations, and it also provides good results as compared to the results given by the two-dimensional code. However, for the same accuracy, MLASER is computationally much faster (a factor of 4) than the original LASER program. The code TWOLASER can be used to provide data for benchmarking, and MLASER can be used for the replacement of the original LASER.