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Division Spotlight
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
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!
Latest Magazine Issues
Mar 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
April 2024
Nuclear Technology
Fusion Science and Technology
February 2024
Latest News
Can hydrogen be the transportation fuel in an otherwise nuclear economy?
Let’s face it: The global economy should be powered primarily by nuclear power. And it probably will by the end of this century, with a still-significant assist from renewables and hydro. Once nuclear systems are dominant, the costs come down to where gas is now; and when carbon emissions are reduced to a small portion of their present state, it will become obvious that most other sources are only good in niche settings. I mean, why use small modular reactors to load-follow when they can just produce that power instead of buffering it?
Technical Session
Thursday, May 19, 2022|8:00–9:45AM EDT|Haselton
Session Chair:
Baocheng Zhang (Westinghouse Electric Co.)
Session Organizer:
Alternate Chair:
Petri Guimaraes (Studsvik Scandpower)
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Comparison of CASMO-5, MPACT and Serpent 2 for the Modeling of Advanced BWR Lattices
M. Hursin (Paul Scherrer Institute), P. Mala (Paul Scherrer Institute), A. Vasiliev (Paul Scherrer Institute), H. Ferroukhi (Paul Scherrer Institute), Yuxuan Liu (Univ. Michigan), Sooyoung Choi (Univ. Michigan), Brendan Kochunas (Univ. Michigan)
Paper
Demonstration of an Embedded Diffusion Scheme for Modelling the BEAVRS Benchmark Problem
R. H. Prinsloo (Necsa), S.A. Groenewald (Necsa), C. Jacobs (Necsa), D.I. Tomašević (Necsa)
Presented by Kostadin Ivanov (NCSU)
Development and Validation of the GNF Core Simulator Package LANCR02/PANAC11 for the Evaluation of Boiling Water Reactors with LEU+ and High Burn-up Fuel Characteristics
J. Hannah (Global Nuclear Fuel), K. Bennett (Global Nuclear Fuel), G. Cuevas-Vivas (Global Nuclear Fuel), J. Finch (Global Nuclear Fuel), F. Jones (Global Nuclear Fuel), L. Pogosbekyan (Global Nuclear Fuel), B. Ward (Global Nuclear Fuel)
Fuel Cycle Depletion to Spent Fuel Gamma Facility Dose Rate Validation Studies
D. Chandler (ORNL)
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