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
Apr 2026
Jan 2026
Latest Journal Issues
Nuclear Science and Engineering
May 2026
Nuclear Technology
February 2026
Fusion Science and Technology
Latest News
Integrating Waste Management for Advanced Reactors: The Universal Canister System and Project UPWARDS
When the Department of Energy’s Advanced Research Projects Agency–Energy launched the Optimizing Nuclear Waste and Advanced Reactor Disposal Systems (ONWARDS) program in 2022, it posed a challenge that the nuclear industry had never seriously confronted before: how to design waste management solutions that anticipate the coming shift to advanced reactors and not merely retrofit existing systems built for an older generation of technology. The program’s objectives were ambitious—reduce disposal footprint, enable scalable pathways for unfamiliar waste streams, and build the technical foundations for future disposal—yet also tightly grounded in the realities of emerging nuclear fuel cycles. For the nuclear community, this was a timely call. Advanced reactors were accelerating toward deployment, but the waste management systems needed to support them had not kept pace.
Eckart Viehl
Nuclear Science and Engineering | Volume 56 | Number 4 | April 1975 | Pages 422-427
Technical Note | doi.org/10.13182/NSE75-A26687
Articles are hosted by Taylor and Francis Online.
Analytical expressions describing the measured auto- and cross-spectral densities of the zero-power noise at the Measuring and Research Reactor Braunschweig (FMRB) were derived from the two-point reactor kinetics equations. By means of this theory, the following properties of the two fission zones of the assembly were obtained from measurements: (a) the shutdown reactivities of the isolated cores, (b) the coupling reactivity, and (c) the power in the fission zones. The efficiencies of the detectors, needed to evaluate the properties mentioned, were obtained from these measurements also. Furthermore, the influence of the delayed neutrons-which were neglected when estimating the properties of the FMRB—on the coherence function is shown. This function was used to detect coupling effects in extended cores.