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Division Spotlight
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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
Canada clears Darlington to produce Lu-177 and Y-90
The Canadian Nuclear Safety Commission has amended Ontario Power Generation’s power reactor operating license for Darlington nuclear power plant to authorize the production of the medical radioisotopes lutetium-177 and yttrium-90.
Scott M. Richards (Univ of Tennessee), Brandon R. Grogan (ORNL)
Proceedings | 16th International High-Level Radioactive Waste Management Conference (IHLRWM 2017) | Charlotte, NC, April 9-13, 2017 | Pages 899-905
The Inverse Depletion Theory (INDEPTH) code is one of the tools being used to analyze the traditional nondestructive assay (NDA) measurements and verify the initial enrichment, burnup, and cooling time values of spent nuclear fuel (SNF) declared by facilities. The INDEPTH code attempts to reconstruct the initial enrichment and operating history by using the Oak Ridge Isotope Generation (ORIGEN) code to simulate irradiation and cooling of the fuel. This work examined the sensitivity of INDEPTH results to variations in irradiation conditions. Three types of measured data were simulated to identify possible sources of systematic error. An absolute gamma measurement with a gross neutron count produced more accurate answers than either the relative gamma measurement or the absolute gamma measurement by itself in most cases. However, long shutdown times between irradiation cycles were found to greatly affect the accuracy, with the absolute gamma plus gross neutron counts case losing the most accuracy. In these cases, the added neutron data either did not significantly improve the results or made them worse.