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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
G7 pledges support for nuclear at Italy meeting
The Group of Seven (G7) recommitted its support for nuclear energy in the countries that opt to use it at a Ministerial Meeting on Climate in Italy last month.
In a statement following the April meeting, the group committed to support multilateral efforts to strengthen the resilience of nuclear supply chains, referencing the goal set by 25 countries during last year’s COP28 climate conference in Dubai to triple global nuclear generating capacity by 2050.
Hongbin Zhang, Ronaldo Szilard, Ling Zou, Haihua Zhao
Nuclear Technology | Volume 205 | Number 1 | January-February 2019 | Pages 174-187
Technical Paper | doi.org/10.1080/00295450.2018.1496694
Articles are hosted by Taylor and Francis Online.
The U.S. Nuclear Regulatory Commission (NRC) is proposing a new rulemaking on emergency core system/loss-of-coolant accident (LOCA) performance analysis. In the proposed rulemaking, designated as 10 CFR 50.46c, the NRC puts forward an equivalent cladding oxidation criterion as a function of cladding pretransient hydrogen content. The proposed rulemaking imposes more restrictive and burnup-dependent cladding embrittlement criteria; consequently, more fuel rods need to be analyzed under LOCA conditions to maintain the safety margin, in contrast to the current practice for which only one hot rod needs to be analyzed. New multiphysics analysis methods are required to provide a thorough characterization of the reactor core in order to identify the locations of the limiting rods and quantify safety margins under LOCA conditions. The U.S. Department of Energy’s Light Water Reactor Sustainability Program has initiated a project to develop multiphysics analytical capabilities, called LOTUS, to support the industry in the transition to the proposed rule. An approach to uncertainty quantification and sensitivity analysis with LOTUS was developed. A typical four-loop pressurized water reactor plant model was developed for RELAP5-3D simulations with inputs generated from core design and fuel performance analyses, and uncertainty quantification and sensitivity analysis were performed with 17 uncertain input parameters. The maximum equivalent cladding reacted ratio and peak clad temperature ratio were selected as the figures of merit (FOMs). Pearson, Spearman, partial correlation coefficients, and Sobol indices were considered for all of the FOMs in the sensitivity analysis.