ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
Xiaohua Cao, Benfu Yang, Huajin Tan, Jingping Wan, Changyong Jiang
Fusion Science and Technology | Volume 41 | Number 3 | May 2002 | Pages 892-896
Material Interaction and Permeation | Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001 | doi.org/10.13182/FST02-A22713
Articles are hosted by Taylor and Francis Online.
The adsorption and desorption behaviors of tritium on the surfaces of stainless steel, copper, molybdenum and Kovar were studied. After the exposure in tritium gas ( 9 kPa gaseous tritium, 2 minutes exposure at 873 K and 40 minutes cooling ), the tritium desorbed at room temperature and during heating up to 1123 K and total sorbed tritium of the samples were measured. The results showed that the desorbed tritium at room temperature was only 1∼6% of total sorbed tritium and its amount order was: Kovar >copper > stainless steel > molybdenum. The total desorbed tritium was ranging from 2 to 22 MBq/cm2, the largest is for Kovar and the smallest is for stainless steel. The tritium released from these materials at room temperature and during heating was mostly in the form of HTO. The thermo-desorption spectra of these materials were obtained. It was found that at least 5, 3, 3, 4 sorption states of tritium exist in the exposed Kovar, molybdenum, copper and stainless steel samples respectively. Doping 1% hydrogen in the carrying gas of helium during the thermo-desorption had rather effect on this process.