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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.
Nuclear and Emerging Technologies for Space (NETS 2023)
May 7–11, 2023
Idaho Falls, ID|Snake River Event Center
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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Nuclear Science and Engineering
Fusion Science and Technology
Wanted: Information leading to a neutron source for fusion energy R&D
The Department of Energy’s Office of Science published a notice in the March 27 Federal Register calling for input on technological approaches to a Fusion Prototypic Neutron Source (FPNS) for materials irradiation research under DOE-SC’s Fusion Energy Sciences program, as well as partnership models that could accelerate the construction and delivery of the facility. The request for information (RFI) calls for responses by May 11.
Monday, October 4, 2021|5:30–7:00PM EDT
William Wieselquist (ORNL)
Todd J. Urbatsch (LANL)
Thomas Folk (Univ. of Michigan)
This will probably be the best set of lightning talks, ever. We will adhere strictly to the schedule. Everyone's mics will sound great. Speakers will start with their conclusions so you may have everything you need in the first minute! The chat will be overflowing with questions and answers. You may think this sounds stressful, but we will not panic and get overwhelmed. We'll enjoy learning about so many colleagues activities in such a short amount of time (the efficiency!) and revel in the technical diversity that is computational tools for reactor physics applications.
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Benchmarking a Pronghorn Model of the Natural Convection Shutdown Heat Removal Test Facility Against STAR-CCM+
Sebastian Schunert (INL), Ramiro Freile (Texas A&M Univ.), Logan Harbour (Texas A&M Univ.), Paolo Balestra (INL)
Reference — Poster
Control Rod History Effect Assessment in a Soluble Boron-Free S-PWR
P. Devaux (CEA), M. Guyot (CEA), J.-F. Vidal (CEA)
PARAGON2/ANC Analysis of BEAVRS Benchmark Reactor Core
Mohamed Ouisloumen (Westinghouse Electric Co.), Ho Q. Lam (Westinghouse Electric Co.), Jie P. Lu (Westinghouse Electric Co.)
Reference — poster
Validation of the High-Resolution Code nTRACER Against VVER-1000 Hot Zero Power Measurements
Marianna Papadionysiou (Paul Scherrer Institut), Seongchan Kim (Seoul Nat'l Univ.), Mathieu Hursin (Paul Scherrer Institut), Alexander Vasiliev (Paul Scherrer Institut), Hakim Ferroukhi (Paul Scherrer Institut), Han Gyu Joo (Seoul Nat'l Univ.), Andreas Pautz (Paul Scherrer Institut)
FRENDY/MG: A Multi-Group Cross Section Generation Module Using ACE Pointwise Cross Sections
Akio Yamamoto (Nagoya Univ.), Tomohiro Endo (Nagoya Univ.), Basma Fouad (Nagoya Univ.), Go Chiba (Hokkaido Univ.), Kenichi Tada (Japan Atomic Energy Agency)
Reference — Poster presentation - FRENDY/MG
Towards an Efficient and Stable Hybrid Transport-Depletion Sequence Using Reduced-Order Solutions at Substeps
Andrew Johnson (Georgia Institute of Technology), Dan Kotlyar (Georgia Institute of Technology)
Comparative Study for Load-Follow Operations of the Holos Microreactor
Sooyoung Choi (Univ. of Michigan), Shai Kinast (Univ. of Michigan), Claudio Filippone (HolosGen), Brendan Kochunas (Univ. of Michigan)
Validation of the GeN-Foam Model of the CROCUS Experimental Reactor
Tom Mager (Ecole Polytechnique Federale de Lausanne), Carlo Fiorina (Ecole Polytechnique Federale de Lausanne), Mathieu Hursin (Paul Scherrer Institute), Andreas Pautz (Paul Scherrer Institute)
Development of a Syntactic Validation Capability for the Use of MCNP
Peter J. Kowal (Rensselaer Polytechnic Institute), Jonathan A. Eugenio (Rensselaer Polytechnic Institute), Kurt A. Dominesey (Rensselaer Polytechnic Institute), Wei Ji (Rensselaer Polytechnic Institute), Robert A. Lefebvre (ORNL), Forrest B. Brown (LANL)
Monte Carlo Analysis of Sub-Pin Resolved Power Behaviour in Modern BWR Assembly Designs
Mathieu Hursin (Paul Scherrer Institut), Alexander Vasiliev (Paul Scherrer Institut), Dimitri Rochman (Paul Scherrer Institut), Abdelhamid Dokhane (Paul Scherrer Institut), Hakim Ferroukhi (Paul Scherrer Institut)
Operational Characteristics of Low-Enriched Moderated and Unmoderated Space Nuclear Propulsion Reactors
Matt Krecicki (Georgia Institute of Technology), Dan Kotlyar (Georgia Institute of Technology)
Development of a Griffin Reactor Physics Analysis Code Model for the Versatile Test Reactor
Nicolas Martin (INL), Ryan Stewart (INL), Zhiwen Xu (INL), Sam Bays (INL)
Numerical Investigation of Solidification of Corium in an Initially Emptied Vertical Pipe
Alex Pegarkov (Carleton Univ.), Shawn Somers-Neal (Carleton Univ.), Abubaker Alatrash (Carleton Univ.), Edgar Matida (Carleton Univ.), Vinh Tang (Carleton Univ.), Tarik Kaya (Carleton Univ.)
Validation of the Resonant Scattering Treatment in the Different APOLLO3 Self-Shielding Models
Jean-François Vidal (CEA), Madeleine Gilly (CEA)
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