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
May 2026
Jan 2026
2026
Latest Journal Issues
Nuclear Science and Engineering
June 2026
Nuclear Technology
Fusion Science and Technology
Latest News
Savannah River marks the closure of another legacy waste tank
The Department of Energy’s Office of Environmental Management has received concurrence from regulators that Tank 14 at the Savannah River Site has reached preliminary cease waste removal (PCWR) status after radioactive liquid waste was successfully removed from the tank. PCWR is a regulatory milestone in the closure of SRS’s old-style waste tanks, which were built in the 1950s to store waste generated by the chemical separations of plutonium and uranium.
D. Mandelli, C. Smith, T. Riley, J. Nielsen, A. Alfonsi, J. Cogliati, C. Rabiti, J. Schroeder
Nuclear Technology | Volume 193 | Number 1 | January 2016 | Pages 161-174
Technical Paper | Special Issue on the RELAP5-3D Computer Code | doi.org/10.13182/NT14-142
Articles are hosted by Taylor and Francis Online.
The existing fleet of nuclear power plants is in the process of having its lifetime extended and having the power generated from these plants increased via power uprates and improved operations. In order to evaluate the impact of these factors on the safety of the plant, the Risk-Informed Safety Margin Characterization (RISMC) pathway aims to provide insights to decision makers through a series of simulations of the plant dynamics for different initial conditions and accident scenarios. This paper presents a case study in order to show the capabilities of the RISMC methodology to assess the impact of power uprate of a boiling water reactor system during a station blackout accident scenario. We employ a system simulator code, RELAP5-3D, coupled with RAVEN, which performs the stochastic analysis. Our analysis is performed by (a) sampling values from a set of parameters from the uncertainty space of interest, (b) simulating the system behavior for that specific set of parameter values, and (c) analyzing the outcomes from the set of simulation runs.