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
Jul 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
September 2025
Nuclear Technology
August 2025
Fusion Science and Technology
Latest News
Joint NEA project performs high-burnup test
An article in the OECD Nuclear Energy Agency’s July news bulletin noted that a first test has been completed for the High Burnup Experiments in Reactivity Initiated Accident (HERA) project. The project aim is to understand the performance of light water reactor fuel at high burnup under reactivity-initiated accidents (RIA).
W. P. Poenitz
Nuclear Science and Engineering | Volume 57 | Number 4 | August 1975 | Pages 300-308
Technical Paper | doi.org/10.13182/NSE75-A15422
Articles are hosted by Taylor and Francis Online.
Absolute measurements of the capture cross section of197Au were carried out in the 400- to 3500-keV energy range. Ratios of the capture cross sections of 238U to 197Au were measured from 20 to 1200 keV. Values for σn,y(238U) were derived by utilizing evaluated and present data for σ n,γ(197Au). The time-of-flight technique and a large liquid scintillator were used for the detection of the prompt capture gamma rays, and the Grey Neutron Detector, the Black Neutron Detector, and a 6Li-glass detector were used for the measurement and monitoring of the neutron flux. The present results support previous measurements of the 238U capture cross section and resolve some existing discrepancies. The absolute values for the capture cross section of 197Au agree well with evaluated data and measurements reported relative to the 235U fission cross section.