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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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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!
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Latest News
PNNL seeks high-energy neutrons from SpaceX launch of Polaris Dawn
When a SpaceX rocket lifted off from Kennedy Space Center on September 10 (see video here), sending a crewed commercial mission into low Earth orbit, an experiment designed by Pacific Northwest National Laboratory was onboard. Several high-purity metal samples will orbit Earth and absorb cosmic radiation for five days—including that from the Van Allen radiation belt—to help the lab answer questions about the radiation environment for manned space missions, according to a news release from PNNL.
Dong Li, Rao Hao
Nuclear Science and Engineering | Volume 196 | Number 2 | February 2022 | Pages 209-220
Technical Paper | doi.org/10.1080/00295639.2021.1968760
Articles are hosted by Taylor and Francis Online.
To simulate the complex accident phenomena of a marine reactor, the thermal-hydraulic system code RELAP5 is modified to perform the analysis under ocean conditions. An integrated reactor with a passive residual heat removal system (PRHRS) is modeled by the improved code, and the effects of different ocean motions under a total loss-of-flow accident (LOFA) and a loss-of-heat-sink (LOHS) accident are analyzed with respect to safety characteristics. The results indicate that for LOFA, the primary loop can form an effective natural circulation to cool the core, and for LOHS, the PRHRS can effectively remove the residual heat from the core to ensure the core safety. The results also show that heaving motion accelerates the drop of the first-loop temperature and enhances the heat transfer capacity of the PRHRS. Inclining motion reduces the natural circulation flow in the core. A rolling condition causes fluctuations in the mass flow rate, the variations of which are not strictly sinusoidal, and increasing the rolling period also improves the heat exchange capacity of the PRHRS.