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 Nuclear Energy Conference & Expo (NECX)
August 24–27, 2026
Dallas, TX|Hilton Anatole
Latest Magazine Issues
Jun 2026
Jan 2026
2026
Latest Journal Issues
Nuclear Science and Engineering
July 2026
Nuclear Technology
Fusion Science and Technology
May 2026
Latest News
Breaking ground on a new approach to construction
The drive to Kairos Power’s reactor demonstration site in Oak Ridge, Tenn., is not only scenic—it’s historic. Nearly 85 years ago, roughly 30,000 construction workers transformed orchards and farmland into a key Manhattan Project site. Depending on your route, you may pass by one of the three gatehouses that were once military checkpoints controlling access to Atomic Energy Commission production facilities.
E. Goldberg, L. F. Hansen, T. T. Komoto, B. A. Pohl, R. J. Howerton, R. E. Dye, E. F. Plechaty, W. E. Warren
Nuclear Science and Engineering | Volume 105 | Number 4 | August 1990 | Pages 319-340
Technical Paper | doi.org/10.13182/NSE90-A21468
Articles are hosted by Taylor and Francis Online.
Measurements of the neutron and gamma-ray leakage spectra from 15 spherical target assemblies (carbon, nitrogen, H2O, C2F4, aluminum, silicon, titanium, iron, copper, tantalum, tungsten, gold, lead, 232Th, and 238U) pulsed with 14-MeV neutrons were made using time-of-flight techniques. The spheres were ∼30 g/cm2 thick to maximize the gamma-ray leakage per central source neutron. Among all the materials studied, silicon shows the highest conversion factor (∼2 γMeV/n), and lead the lowest (0.31 γMeV/n). Monte Carlo neutron-photon transport calculations were done using the TART and SANDYL codes, with the ENDL and ENDF/B-V libraries. Comparisons with the neutron measurements confirm earlier results, where both libraries reproduced the leakage spectra for most of these materials reasonably well. The gamma spectra calculated with ENDL give a fair representation of the measurements, with the exception of the initial calculations for 16O(H2O) and 19F(C2F4), where serious discrepancies are found. Improvements were obtained for 16O after a re-evaluation of the neutron-induced cross sections based on more recent microscopic experimental data. This was also the case for 19F, where the calculations now overestimate the measurements by 30%. Calculations with the ENDF/B-V are lower than the experimental measurements for most of the materials.