ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
Meeting Spotlight
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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
Oct 2024
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
November 2024
Nuclear Technology
Fusion Science and Technology
Latest News
A proactive approach to reactor vessel aging management
Unit 2 at the Prairie Island nuclear power plant near Red Wing, Minn., underwent an outage in fall 2023, which included extensive work on the reactor vessel using a novel approach to replace baffle-former bolts and lower radial clevis insert bolts. The work relied on extensive analysis beforehand to determine which bolts to replace such that only the new bolts were structurally credited for performance of their safety function. This proactive approach eliminated the need for costly contingencies associated with inspections.
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)
