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Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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.
A. Labarile, C. Mesado, R. Miró, G. Verdú
Nuclear Technology | Volume 205 | Number 12 | December 2019 | Pages 1675-1684
Technical Paper | doi.org/10.1080/00295450.2019.1631051
Articles are hosted by Taylor and Francis Online.
One of the challenges of studying the neutronics of reactors is to generate reliable parameterized libraries that contain information to simulate the core in all possible operational and transient conditions. These libraries must include tables of cross sections and other neutronic and kinetic parameters and are obtained by simulating all the segments in a transport code. At the lattice level, one can use branch calculations to change “instantaneously” the feedback parameters as a function of burnup. When using random sampling for the lattice calculations, one can obtain statistical information about the output parameters and use it in a core simulation to characterize the accuracy of data estimating uncertainties when simulating a heterogeneous system at different scales of detail.
This work presents the methodology to generate NEMTAB libraries from data obtained in the SCALE code system to be used in PARCS simulations. The code TXT2NTAB is used to reorder the cross-section tables in NEMTAB format and generate another NEMTAB of standard deviation. With these libraries, the authors perform a steady-state calculation for a light water reactor to propagate several uncertainties at the core level. The methodology allows obtaining statistical information of the most important output parameters: multiplication factor keff, axial power peak Pz, and axial peak node Nz.