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
2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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
Nov 2025
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
December 2025
Nuclear Technology
Fusion Science and Technology
November 2025
Latest News
X-energy raises $700M in latest funding round
Advanced reactor developer X-energy has announced that it has closed an oversubscribed Series D financing round of approximately $700 million. The funding proceeds are expected to be used to help continue the expansion of its supply chain and the commercial pipeline for its Xe-100 advanced small modular reactor and TRISO-X fuel, according the company.
Harry J. Reilly, Lawrence E. Peters, Jr.
Nuclear Technology | Volume 11 | Number 1 | May 1971 | Pages 89-95
Technical Paper | Shielding | doi.org/10.13182/NT71-A30905
Articles are hosted by Taylor and Francis Online.
A calorimeter was made to determine the relative amount of gamma heating in watts per gram in different materials as a function of thickness and atomic number. The experiment was performed in the NASA Plum Brook Mockup Reactor, which has a typical light-water test reactor gamma-source spectrum. Carbon, aluminum, zirconium, tin, and lead specimens in slab geometry were irradiated. The results showed no significant difference in the gamma heating in carbon and aluminum, but the heating in the other materials was greater than that in aluminum and carbon. The smaller thicknesses had the greater heating. The calorimeter was also used to determine the gamma-heating effect in an irradiation experiment mockup having cylindrical geometry. The result showed good agreement with an expected value obtained from the slab geometry data. A theoretical analysis of the relative gamma heating was made using a one-dimensional multigroup transport program. It was concluded that the analysis and measurements agreed qualitatively and that quantitative differences were attributable mostly to geometrical effects. The results of this study are believed to be applicable to both nuclear reactor experiment designs and other reactor problems.