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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
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
Digital control system installed at China’s Linglong One
Earlier this month, the first digital control system was put in place at Linglong One, a small modular reactor demonstration project being built at the Changjiang nuclear power plant in Hainan Province. This is the world’s first land-based commercial SMR and is controlled by China National Nuclear Power Co. Ltd., a subsidiary of the China National Nuclear Corporation (CNNC).
Sayed A. El-Mongy, Kh. A. Allam
Nuclear Technology | Volume 205 | Number 11 | November 2019 | Pages 1474-1479
Technical Paper | doi.org/10.1080/00295450.2019.1593012
Articles are hosted by Taylor and Francis Online.
Precise assay of uranium enrichment without time-consuming analysis is a crucial factor in nuclear safeguards process. This paper aims at a computational development using innovative Monte Carlo (MC) method for 235U mass enrichment (%E) verification for the UF6 cylinder. This new approach focuses mainly on using different UF6 physical properties (effective volume and density) and extra 235U gamma- and X-ray transitions as input parameters for efficient calculations of %E assay. In this work, we used the measured values of the dose rate (μSv/h) due to the emitted gamma- and X-rays of 235U content at the cylinder external surface for enrichment calculations. The attenuation of the main 235U gamma- and X-energies due to the cylinder wall (5B-Type Ni Inconel alloy) was also estimated to wide range of energies using XCOM: Photon Cross Sections Database software. Using this suggested model for 235U enrichment calculation, the calculated value of 19.46 ± 1.28% is within one standard deviation of the certified value of 19.75 ± 0.40%. The mass of 235U was also estimated and found to be 2.6814 kg. Based on this improved approach, the total uranium activity of the investigated UF6 cylinder was calculated and found to be (5.52 GBq), which is 98.6% from the declared activity value (5.6 GBq). These accurate and confident calculated values are direct functions in the improved parameters and the developed MC code.