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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!
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Nuclear Technology
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Latest News
Judge temporarily blocks DOE’s move to slash university research funding
A group of universities led by the American Association of Universities (AAU) acted swiftly to oppose a policy action by the Department of Energy that would cut the funds it pays to universities for the indirect costs of research under DOE grants. The group filed suit Monday, April 14, challenging a what it termed a “flagrantly unlawful action” that could “devastate scientific research at America’s universities.”
By Wednesday, the U.S. District Court judge hearing the case issued a temporary restraining order effective nationwide, preventing the DOE from implementing the policy or terminating any existing grants.
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Verification of a Three-Dimensional Nodal Transient Neutronics Routine for the TRAC-PF1/MOD3 Thermal-Hydraulic System Analysis Code
Bernard R. Bandini, Kostadin N. Ivanov, Anthony J. Baratta, Robert G. Steinke
Nuclear Technology | Volume 123 | Number 1 | July 1998 | Pages 1-20
Technical Paper | Reactor Safety | doi.org/10.13182/NT98-A2875
Basic Properties of a Zirconia-Based Fuel Material for Light Water Reactors
Claude Degueldre, Jean-Marie Paratte
Nuclear Technology | Volume 123 | Number 1 | July 1998 | Pages 21-29
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT98-A2876
Conceptual Design of a Steam-Water Power Reactor Core
Yasunori Bessho, Takashi Nakayama, Michiro Yokomi, Katsuma Nakayama, Hiroki Sano, Nobuhiro Kanazawa
Nuclear Technology | Volume 123 | Number 1 | July 1998 | Pages 30-43
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT98-A2877
Biosphere Modeling in Waste Disposal Safety Assessments - An Example Using the Terrestrial-Aquatic Model of the Environment
Richard A. Klos
Nuclear Technology | Volume 123 | Number 1 | July 1998 | Pages 44-59
Technical Paper | Criticality of Nuclear Materials | doi.org/10.13182/NT98-A2878
Vitrification of Cesium-Laden Organic Ion-Exchange Resin in a Stirred Melter
Thomas N. Sargent, Jr., Thomas J. Overcamp, Dennis F. Bickford, Connie A. Cicero-Herman
Nuclear Technology | Volume 123 | Number 1 | July 1998 | Pages 60-66
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT98-A2879
Estimating the Alteration Kinetics of the French Vitrified High-Level Waste Package in a Geologic Repository
Patrick Jollivet, Michèle Nicolas, Etienne Vernaz
Nuclear Technology | Volume 123 | Number 1 | July 1998 | Pages 67-81
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT98-A2880
Analytical Solutions for Diffusive Mass Transport from a Sphere, Considering a Surface Flux Boundary Condition
B. Peter McGrail
Nuclear Technology | Volume 123 | Number 1 | July 1998 | Pages 82-89
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT98-A2881
Numerically Investigating the Influence of Local Flow Behaviors on Flow-Accelerated Corrosion Using Two-Fluid Equations
Kuo-Tong Ma, Yuh-Ming Ferng, Yin-Pang Ma
Nuclear Technology | Volume 123 | Number 1 | July 1998 | Pages 90-102
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT98-A2882
Detection Limits of a Laboratory Pulsed Gamma Neutron Activation Analysis System for the Nondestructive Assay of Mercury, Cadmium, and Lead
Abdul R. Dulloo, Frank H. Ruddy, Thomas V. Congedo, John G. Seidel, Robert J. Gehrke
Nuclear Technology | Volume 123 | Number 1 | July 1998 | Pages 103-112
Technical Paper | Radiation Measurements and Instrumentation | doi.org/10.13182/NT98-A2883
An Approach to Archiving Software-Related Quality Assurance Project Record Files
Lance J. Agee, Robert J. Breen
Nuclear Technology | Volume 123 | Number 1 | July 1998 | Pages 113-115
Technical Note | Reactor Operations and Control | doi.org/10.13182/NT98-A2884
Empirical Modeling of U(IV) Distribution in a Nitric Acid-Water-30% TBP/n-Dodecane Biphasic System in the Presence of U(VI), Pu(III), and Hydrazine Nitrate
Shekhar Kumar, Sudhir B. Koganti
Nuclear Technology | Volume 123 | Number 1 | July 1998 | Pages 116-119
Technical Note | Radioactive Waste Management and Disposal | doi.org/10.13182/NT98-A2885
Improved Axial Flux Shape Generator for a Quick Departure from Nucleate Boiling Test
Atul A. Karve, Chae Han, Rizwan-uddin
Nuclear Technology | Volume 123 | Number 2 | August 1998 | Pages 121-129
Technical Paper | Fission Reactors | doi.org/10.13182/NT98-A2886
MACSIS: A Metallic Fuel Performance Analysis Code for Simulating In-Reactor Behavior Under Steady-State Conditions
Woan Hwang, Cheol Nam, Thak Sang Byun, Young Cheol Kim
Nuclear Technology | Volume 123 | Number 2 | August 1998 | Pages 130-141
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT98-A2887
Investigation of the Premixing Phase of a Steam Explosion with Hot Spheres
Leonhard Meyer, Gustav Schumacher, Helmut Jacobs, Kalman Thurnay
Nuclear Technology | Volume 123 | Number 2 | August 1998 | Pages 142-155
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT98-A2888
Effects of Spacer Grids with Mixing Promoters on Reflood Heat Transfer in a PWR LOCA
Zbigniew Koszela
Nuclear Technology | Volume 123 | Number 2 | August 1998 | Pages 156-165
Technical Paper | Reprocessing | doi.org/10.13182/NT98-A2889
Modeling and Control of a Sodium Conversion Process Applied to Nuclear Decommissioning Activities
Humberto E. Garcia
Nuclear Technology | Volume 123 | Number 2 | August 1998 | Pages 166-183
Technical Paper | Decontamination/Decommissioning | doi.org/10.13182/NT98-A2890
Radionuclide Mass Transfer Rates from a Pinhole in a Waste Container for an Inventory-Limited and Constant Concentration Source
Dennis M. LeNeveu
Nuclear Technology | Volume 123 | Number 2 | August 1998 | Pages 184-192
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT98-A2891
A Numerical Investigation of Natural Convection Heat Transfer Within Horizontal Spent-Fuel Assemblies
Robert E. Canaan, Dale E. Klein
Nuclear Technology | Volume 123 | Number 2 | August 1998 | Pages 193-208
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT98-A2892
Stresses in an Oxidized Zircaloy Cladding Under Quench Conditions: Recalculation of Single-Rod Quench Tests
Helmut Steiner, Monika Heck
Nuclear Technology | Volume 123 | Number 2 | August 1998 | Pages 209-221
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT98-A2893
A New Fuel Management Plan for The Pennsylvania State University TRIGA Reactor Including Supporting Experiments and Calculations
Patrick G. Boyle, Daniel E. Hughes, Samuel H. Levine
Nuclear Technology | Volume 123 | Number 2 | August 1998 | Pages 222-230
Technical Note | Fission Reactors | doi.org/10.13182/NT98-A2894
Pressure- and Flow-Induced Accident and Transient Analyses of a Direct-Cycle, Supercritical-Pressure, Light-Water-Cooled Fast Reactor
Kazuaki Kitoh, Seiichi Koshizuka, Yoshiaki Oka
Nuclear Technology | Volume 123 | Number 3 | September 1998 | Pages 233-244
Technical Paper | Reactor Safety | doi.org/10.13182/NT98-A2895
Conceptual Design of a 50-MW Severe-Accident-Free HTR and the Related Test Program of the HTTR
Kazuhiko Kunitomi, Yukio Tachibana, Akio Saikusa, Kazuhiro Sawa, Lawrence M. Lidsky
Nuclear Technology | Volume 123 | Number 3 | September 1998 | Pages 245-258
Technical Paper | Reactor Safety | doi.org/10.13182/NT98-A2896
Comparison Between MCNP and Critical Experiments - A Determination of Bias Values to Be Utilized in Licensing Calculations for High-Level Radioactive Waste Disposal
Kenneth D. Wright, James S. Tulenko, Edward T. Dugan
Nuclear Technology | Volume 123 | Number 3 | September 1998 | Pages 259-267
Technical Paper | Reactor Safety | doi.org/10.13182/NT98-A2897
Use of Weapons-Grade Plutonium in Existing PWRs - Supported by German MOX Recycling Experience
Friedrich Burtak, Gerhard J. Schlosser
Nuclear Technology | Volume 123 | Number 3 | September 1998 | Pages 268-277
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT98-A2898
Determination of PWR Control Rod Position by Core Physics and Neural Network Methods
Ninos S. Garis, Imre Pázsit, Urban Sandberg, Tell Andersson
Nuclear Technology | Volume 123 | Number 3 | September 1998 | Pages 278-295
Technical Paper | Reactor Operations and Control | doi.org/10.13182/NT98-A2899
Temperature Effects on the Leaching Behavior of a High-Level Waste Glass Form
Jiawei Sheng, Shanggeng Luo, Baolong Tang
Nuclear Technology | Volume 123 | Number 3 | September 1998 | Pages 296-303
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT98-A2900
Vitrified Waste Form Performance Modeling Applied to the Treatment and Disposal of a Mixed-Waste Sludge at the Savannah River Site
A. Ryan Whited, Robert A. Fjeld, James R. Cook
Nuclear Technology | Volume 123 | Number 3 | September 1998 | Pages 304-319
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT98-A2901
Evaluation of Moderator Assemblies for Use in an Accelerator-Based Neutron Source for Boron Neutron Capture Therapy
Jeffrey E. Woollard, Thomas E. Blue, Nilendu Gupta, Reinhard A. Gahbauer
Nuclear Technology | Volume 123 | Number 3 | September 1998 | Pages 320-334
Technical Paper | Radiation Biology and Medicine | doi.org/10.13182/NT98-A2902
Prediction of Liquid Mixture Viscosity for Dry and Water-Saturated TBP/[italic]n[roman]-Dodecane Solutions
Shekhar Kumar, S. B. Koganti
Nuclear Technology | Volume 123 | Number 3 | September 1998 | Pages 335-340
Technical Note | Enrichment | doi.org/10.13182/NT98-A2903
Recovery of Fissile Materials from Wastes and Conversion of the Residual Wastes to Glass
Charles W. Forsberg, Edward C. Beahm
Nuclear Technology | Volume 123 | Number 3 | September 1998 | Pages 341-349
Technical Note | Reprocessing | doi.org/10.13182/NT98-A2904
