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Meeting Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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Jun 2025
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Nuclear Science and Engineering
August 2025
Nuclear Technology
Fusion Science and Technology
July 2025
Latest News
The U.S. Million Person Study of Low-Dose-Rate Health Effects
There is a critical knowledge gap regarding the health consequences of exposure to radiation received gradually over time. While there is a plethora of studies on the risks of adverse outcomes from both acute and high-dose exposures, including the landmark study of atomic bomb survivors, these are not characteristic of the chronic exposure to low-dose radiation encountered in occupational and public settings. In addition, smaller cohorts have limited numbers leading to reduced statistical power.
Armando C. Souza, Flavio Aristone, Marco A. A. Cortez, Munique S. de Lima, Duilio R. Porto, Rafaela M. da Silva, Jesualdo L. Rossi
Nuclear Technology | Volume 211 | Number 8 | August 2025 | Pages 1609-1618
Rapid Communication | doi.org/10.1080/00295450.2024.2428912
Articles are hosted by Taylor and Francis Online.
This study investigates the potential of a W8Ni3Cu alloy as a gamma radiation shielding material for transporting highly radioactive substances. The alloy, composed of tungsten (W), nickel (Ni), and copper (Cu), was characterized using X-ray diffraction after sintering, revealing a body-centered-cubic crystal structure with an α-tungsten phase and a secondary γ-nickel-tungsten (Ni17W3) phase. The gamma radiation attenuation coefficients of the alloy were measured using a 60Co source. The results showed linear attenuation coefficients of 0.688 cm-1 for the alloy sintered at 1200°C and 0.488 cm-1 for the alloy sintered at 1300°C. These values are 34% and 53% lower than the reference value of pure tungsten (1.044 cm-1), but they still demonstrate adequate shielding properties for practical use. The findings suggest that the W8Ni3Cu alloy is a promising candidate for fabricating containers for the safe transport of radioactive material.
