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.
Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
October 2024
Nuclear Technology
Fusion Science and Technology
August 2024
Latest News
New laws offer nuclear industry incentives for existing power plant uprates
This year, the U.S. nuclear industry received a much-needed economic boost that could help preserve operating nuclear power plants and incentivize upgrades that extend their lifespan and power output.
Signed into law in 2022, the Inflation Reduction Act offers production tax credits (PTCs) for existing nuclear power plants and either PTCs or investment tax credits (ITCs) for new carbon-free generation. These credits could make power uprates—increasing the maximum power level at which a commercial plant may operate—a much more appealing option for utilities.
N. D. Dudey, D. Meneghetti, R. R. Heinrich, R. H. Rempert
Nuclear Science and Engineering | Volume 53 | Number 1 | January 1974 | Pages 9-26
Technical Paper | doi.org/10.13182/NSE74-A23327
Articles are hosted by Taylor and Francis Online.
Measurements of integral neutron capture-to-fission cross-section ratios and neutron capture rates of 233U, 235U, 238U, 239 Pu, 240 Pu, and 242Pu at 15 radial and axial positions in EBR-n are reported. Fission rates were determined by measurement of the fission product 137Cs and capture rates were determined by mass-spectrometric and alpha-spectrometric analysis. Capture-to-fission ratios at all sample locations and central fission and capture ratios were calculated by two-dimensional RZ and XY geometries using multigroup analyses. Details of geometry and reactor composition changes during the course of the irradiations are considered and found to be significant for the fertile isotopes. A detailed comparison between measurement and calculation is presented and discussed in terms of the calculational model, cross-section data, and experimental uncertainties. Calculations were made using both Versions I and HI of ENDF/B.