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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.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
State lawmakers across the country push for more nuclear
From lifting moratoriums to launching studies to labeling it as clean, state lawmakers are exploring ways to give nuclear energy a boost in 2025. Here’s a look at some of the pronuclear legislation under review.
Jun Wang, Michael L. Corradini, Hangjin Jo (Univ of Wisconsin, Madison)
Proceedings | Advances in Thermal Hydraulics 2018 | Orlando, FL, November 11-15, 2018 | Pages 1015-1021
Following the Fukushima accident, research of accident tolerant fuel (ATF) and cladding materials began in order to improve the nuclear power plant safety following a Beyond Design Basis Accident (BDBA). National laboratories, industry, and universities are involved in this activity. Researchers at the University of Wisconsin are simulating BDBA’s to examine the effect of ATF cladding material using MELCOR. Use of alternate cladding materials (FeCrAl) and potential operator recovery actions have been previously studied. In this work, we examine the effect of FeCrAl coating on Zircaloy using a special version of MELCOR-1.8.6 (YU) developed by Idaho National Laboratory. This MELCOR version allows one to examine the effect of cladding coatings (Cr, FeCrAl) assuming appropriate thermo-physical data are available. FeCrAl is used as a first application of this modeling approach for clad coatings. Using a Short- Term Station Blackout (STSBO accident sequence shows that overall accident progression is quite similar to events without a coating, except for the start rapid core heatup, degradation and significant hydrogen generation. These events are delayed for more than an hour compared to nominal conditions.