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 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
Latest Magazine Issues
Feb 2026
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
March 2026
Nuclear Technology
February 2026
Fusion Science and Technology
January 2026
Latest News
Project Omega emerges from stealth mode with plans to recycle U.S. spent fuel
Nuclear technology start-up Project Omega announced on February 11 that it has emerged from stealth mode with hopes of processing and recycling spent nuclear fuel into “long-duration, high-density power sources and critical materials for the nuclear industry.”
John D. Bess
Nuclear Technology | Volume 177 | Number 1 | January 2012 | Pages 29-35
Technical Paper | Reactor Safety | doi.org/10.13182/NT12-A13325
Articles are hosted by Taylor and Francis Online.
A series of 15 critical experiments performed at the Rocky Flats Critical Mass Laboratory in the late 1960s was evaluated and then determined to represent acceptable benchmark experiments for the validation of calculational methods. This series of experiments was part of a larger set of experiments performed to evaluate operational safety margins at the Rocky Flats Plant. The experiments consisted of bare plutonium metal hemishells reflected by steel hemishells of increasing thickness and motor oil. The hemishell assembly was suspended within dual aluminum tanks. Criticality was achieved by pumping oil into the tanks such that effectively infinite reflection was achieved in all directions except directly above the assembly; then the critical oil height was recorded. The results of these experiments had been initially ignored because early computational methods had been inadequate to analyze partially reflected configurations. The dominant uncertainties include the uncertainty in the average plutonium density and the composition of materials in the gaps between the plutonium hemishells. Simple and detailed benchmark models were developed. Eigenvalue calculations using MCNP5 and ENDF/B-VII.0 were within 2 of the benchmark values. This benchmark evaluation has been added to the International Handbook of Evaluated Criticality Safety Benchmark Experiments.