ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Explore membership for yourself or for your organization.
Conference 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!
Latest Magazine Issues
Aug 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
September 2025
Nuclear Technology
Fusion Science and Technology
August 2025
Latest News
Work advances on X-energy’s TRISO fuel fabrication facility
Small modular reactor developer X-energy, together with its fuel-developing subsidiary TRISO-X, has selected Clark Construction Group to finish the building construction phase of its advanced nuclear fuel fabrication facility, known as TX-1, in Oak Ridge, Tenn. It will be the first of two Oak Ridge facilities built to manufacture the company’s TRISO fuel for use in its Xe-100 SMR. The initial deployment of the Xe-100 will be at Dow Chemical Company’s UCC Seadrift Operations manufacturing site on Texas’s Gulf Coast.
E. Aalto, R. Fräki, K. Malén
Nuclear Science and Engineering | Volume 22 | Number 4 | August 1965 | Pages 443-450
Technical Paper | doi.org/10.13182/NSE65-A20630
Articles are hosted by Taylor and Francis Online.
Recommended values have been experimentally obtained for the angle (defined by its cosine µ0 in center-of-mass system) that determines the boundary between ‘removal’ and ‘nonremoval’ collisions and regulates the deep penetration of neutrons in the NRN method. Measured attenuations in three different, most common, shield materials: water and magnetite and ordinary concrete, give µ0 = 0.6 (± 0.1) for elements with A > 1. For hydrogen, µ0 = 0.45 is recommended. The results indicate, besides, that the neutron flux predictions are not overly sensitive to the changes in the removal source, caused by varying µ0. The usual smoothing effect of the diffusion is material dependent, and the strength of the coupling between removal and diffusion parts is seen to decrease when going from water to magnetite and ordinary concrete.