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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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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
Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
May 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Los Alamos researchers test TRISO transportation
Los Alamos National Laboratory recently performed a series of customized criticality experiments to obtain data that will support the transportation of HALEU TRISO fuel, the Department of Energy announced April 21.
Results 1 to 19 of 19
Organization Participant
Pacific Northwest National Laboratory (PNNL)
2024 ANS Annual Conference
Employer Profile
Paper
Process Intensification for Recovery of Uranium from Spent Fuel Using DEHiBA
Gregg J. Lumetta (PNNL), Gabriel B. Hall (PNNL), Nathan P. Bessen (PNNL), Daria Boglaienko (PNNL), Amy L. Speelman (PNNL)
FCWMD|UNF/SNF Monitoring, Storage and Transportation Advances
Wednesday, June 19, 2024|3:15–5:00PM PDT
Development of a Functions and Requirements Document for a SNF Transportation Package Performance Demonstration
Laura Hay (PNNL), Steven Maheras (PNNL), Miriam Juckett (PNNL), Harold Adkins Jr. (PNNL), Erica Bickford (U.S. Dept. of Energy), Gerard Jackson (U.S. Dept. of Energy), Douglas Ammerman (Sandia), Kevin J. Connolly (ORNL)
Uncertainties for In-Reactor Testing of Tritium Loaded Getters with Temperature Control
Mie Azuma (PNNL), Nathan Carstens (PNNL), Kevin Anderson (PNNL), Robert Gates (PNNL)
THD|General Thermal Hydraulics: I
Monday, June 17, 2024|1:00–2:45PM PDT
3DBF -- A Diffusion Theory Code for Fast Reactor Calculations
Randolph Schwarz (PNNL), David Wootan (PNNL), Dion Sunderland (PNNL), Ron Omberg (PNNL)
RPD|Reactor Analysis Methods
Tuesday, June 18, 2024|3:15–5:00PM PDT
Consequence Uncertainty Quantification in LMP Applications
Matthew Humberstone (U.S. Nuclear Regulatory Commission), Hanh Phan (U.S. Nuclear Regulatory Commission), Steven Unwin (PNNL), Steve Short (PNNL), Garill Coles (PNNL), Jeffery Wood (U.S. Nuclear Regulatory Commission)
Advanced Reactor Safety (ARS)
NISD|Source Term Codes and Insights
Modeling In-Reactor Temperature Gradients in Lithium Aluminate Ceramic Pellets
Nathan Carstens (PNNL), Mie Azuma (PNNL), Robert Gates (PNNL)
2024 International Congress on Advances in Nuclear Power Plants (ICAPP)
Thermal Hydraulics Analysis and Testing|Thermal Hydraulics Analysis and Testing: I
Tuesday, June 18, 2024|1:00–2:45PM PDT
A Method Comparison for Releasing Trapped Radionuclides from Solid Matrices
B.R. Hackett (PNNL), A.M. Whitehill (PNNL), E.K. Mace (PNNL)
MSTD|Actinide Science
Wednesday, June 19, 2024|8:00–9:45AM PDT
Cross-Section Sensitivity Studies on Sodium-Cooled Fast Neutron Reactor Isotopes
A.C. Hellinger (PNNL), C.E. Goodson (PNNL), S.M. Lyons (PNNL)
NCSD|Nuclear Data Needs for Nuclear Criticality Safety and Advanced Reactor Concepts: I
Monte Carlo Graphical User Interface for Accelerator Applications
Randolph Schwarz (PNNL), Mark Murphy (PNNL), David Wootan (PNNL)
RPSD|Second Target Station Development at SNS and Accelerator Facilities
Monday, June 17, 2024|3:15–5:00PM PDT
Custom ORIGEN Libraries for Tritium Production in Discrete Burnable Absorbers
Pavlo Ivanusa (PNNL), Clara Boutros (PNNL)
Reactor Physics and Analysis|Reactor Physics and Analysis
Wednesday, June 19, 2024|10:00–11:45AM PDT
AI/ML-Assisted Design of Phosphate Glass and Ceramic Nuclear Waste Forms
Jincheng Du (Univ. North Texas), Vinay I. Hegde (Citrine Informatics), James Saal (Citrine Informatics), Brian Riley (PNNL), John Vienna (PNNL)
FCWMD|AI/ML, Modeling, Design, and Simulation Approaches for FCWMD Applications
Effect of Grain Structure and Zr Interdiffusion Layer on Gas Bubble Structure in Monolithic UMo Fuels
Shenyang Hu (PNNL), Zirui Mao (PNNL), Benjamin Beeler (NCSU)
MSTD|Accelerating Fuels and Materials Research: II
Mass Spectrometry Analysis of Lithium in FLiBe
Sean R. Scott (PNNL), Johnny Williams (Kairos Power), Sara Mastromarino (Kairos Power)
IRD|Isotopes and Radiation: General
Generation IV International Forum -- Knowledge Management and Knowledge Preservation: An Initiative from the Education and Training Working Group
Patricia Paviet (PNNL)
ETWDD|Training, Human Performance, and Workforce Development
Wednesday, June 19, 2024|1:00–2:45PM PDT
Progress Toward In Situ Tempered, Additively Manufactured Ferritic-Martensitic Steels
C.R. Lear (LANL), T.J. Lienert (Optomec), S.A. Maloy (PNNL)
MSTD|Additive/Advanced Manufacturing: I
Session
Innovations for FCWMD Applications
Technical Session
Harish Reddy Gadey, Junghyun Bae, Praveen Thallapally (PNNL)
FCWMD
Nuclear Fuels: I
Jake Quincey (Oregon State), Kenneth Geelhood (PNNL)
MSTD
Nuclear Fuels: II
Jake R. Quincey (Oregon State), Kenneth J. Geelhood (PNNL)
