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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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 Science and Engineering
January 2025
Nuclear Technology
Fusion Science and Technology
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Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
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Parametric Study of Sloshing Effects in the Primary System of an Isolated Lead-Cooled Fast Reactor
Marti Jeltsov, Walter Villanueva, Pavel Kudinov
Nuclear Technology | Volume 190 | Number 1 | April 2015 | Pages 1-10
Technical Paper | Fission Reactors | doi.org/10.13182/NT14-8
Reactivity Swing as a Function of Burnup for Uranium-Fueled Fast Reactors
Staffan Qvist
Nuclear Technology | Volume 190 | Number 1 | April 2015 | Pages 11-27
Technical Paper | Fission Reactors | doi.org/10.13182/NT14-30
Neutron Multiplicity Measurements With 3He Alternative: Straw Neutron Detectors
Sanjoy Mukhopadhyay, Ronald Wolff, John Meade, Ryan Detweiler, Richard Maurer, Stephen Mitchell, Paul Guss, Jeffrey L. Lacy, Liang Sun, Athanasios Athanasiades
Nuclear Technology | Volume 190 | Number 1 | April 2015 | Pages 28-35
Technical Paper | Fission Reactors | doi.org/10.13182/NT14-12
Irradiation of Minor Actinide–Bearing Uranium-Plutonium-Zirconium Alloys up to ~2.5 at. %, ~7 at. %, and ~10 at. % Burnups
Hirokazu Ohta, Takanari Ogata, Dimitrios Papaioannou, Vincenzo V. Rondinell, Marc Masson, Jean-Luc Paul
Nuclear Technology | Volume 190 | Number 1 | April 2015 | Pages 36-51
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT14-50
Investigation of Effect of Ballooned Fuel Pins on Quenching Behavior: Design of Experiment and Preliminary Analysis
O. S. Gokhale, B. P. Puranik, A. K. Ghosh
Nuclear Technology | Volume 190 | Number 1 | April 2015 | Pages 52-64
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT14-31
Identification of Nonconservative Subregions in Empirical Models Demonstrated Using Critical Heat Flux Models
Joshua Kaizer
Nuclear Technology | Volume 190 | Number 1 | April 2015 | Pages 65-71
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT14-38
Uncertainty Quantification of Concrete Utilized in Dry Cask Storage
Ryan Kelly, Pavel Tsvetkov, Sunil Chirayath, John Poston, Evans Kitcher
Nuclear Technology | Volume 190 | Number 1 | April 2015 | Pages 72-87
Technical Paper | Radiation Transport and Protection | doi.org/10.13182/NT13-155
New Approach for Fatigue Damage Monitoring Based on Actual Operating History of Nuclear Power Plants
Hee-Jin Shim, Chang-Kyun Oh, Hyun-Su Kim, Myung-Hwan Boo, Jong-Jooh Kwon
Nuclear Technology | Volume 190 | Number 1 | April 2015 | Pages 88-96
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT13-150
Probability and Consequences of Nuclear Criticality at a Geologic Repository—I: Conceptual Overview for Screening
Rob P. Rechard
Nuclear Technology | Volume 190 | Number 2 | May 2015 | Pages 97-126
Technical Paper | Reactor Safety | doi.org/10.13182/NT14-40
Probability and Consequences of Nuclear Criticality at a Geologic Repository—II: Potential Repository in Volcanic Tuff as an Example
Nuclear Technology | Volume 190 | Number 2 | May 2015 | Pages 127-160
Technical Paper | Reactor Safety | doi.org/10.13182/NT14-41
A Numerical Solution of the Reeks-Hall Equation for Particulate Concentration in Recirculating Turbulent Fluid Flow
Giang N. Nguyen, Sudarshan K. Loyalka
Nuclear Technology | Volume 190 | Number 2 | May 2015 | Pages 161-173
Technical Paper | Reactor Safety | doi.org/10.13182/NT14-81
Potential Impacts of Modeling Full Reactor Cores Using Combined Fuel Performance and Thermal Hydraulics Codes
Ian Porter, Travis W. Knight, Patrick Raynaud
Nuclear Technology | Volume 190 | Number 2 | May 2015 | Pages 174-182
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT14-100
Gamma-Ray Simulated Spectrum Deconvolution of a LaBr3 1- ×1-in. Scintillator for Nondestructive ATR Fuel Burnup On-Site Predictions
Jorge Navarro, Terry A. Ring, David W. Nigg
Nuclear Technology | Volume 190 | Number 2 | May 2015 | Pages 183-192
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT14-4
Novel Approach to Extracting Transuranic Elements in Molten Salt Electrorefining
Yoshiharu Sakamura, Masatoshi Iizuka, Tadafumi Koyama, Shinichi Kitawaki, Akira Nakayoshi
Nuclear Technology | Volume 190 | Number 2 | May 2015 | Pages 193-206
Technical Paper | Reprocessing | doi.org/10.13182/NT14-64
Release of Radioactive Materials from Simulated High-Level Liquid Waste at Boiling Accident in Reprocessing Plant
S. Tashiro, G. Uchiyama, Y. Amano, H. Abe, Y. Yamane, K. Yoshida
Nuclear Technology | Volume 190 | Number 2 | May 2015 | Pages 207-213
Technical Note | Radioactive Waste Management and Disposal | doi.org/10.13182/NT14-57
Experiments on the Effects of a Spacer Grid in Air-Water Two-Phase Flow
Joshua Wheeler, Ted Worosz, Seungjin Kim
Nuclear Technology | Volume 190 | Number 3 | June 2015 | Pages 215-224
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT14-69
Considerations in the Practical Application of the Multisensor Conductivity Probe for Two-Phase Flow
Matt Bernard, Ted Worosz, Seungjin Kim, Chris Hoxie
Nuclear Technology | Volume 190 | Number 3 | June 2015 | Pages 225-235
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT14-70
Thermal Evaluation of Alternate Shipping Cask for Irradiated Experiments
Donna Post Guillen
Nuclear Technology | Volume 190 | Number 3 | June 2015 | Pages 236-244
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT14-62
Thermal Predictions of the AGR-2 Experiment with Variable Gas Gaps
Grant L. Hawkes, James W. Sterbentz, Binh Pham
Nuclear Technology | Volume 190 | Number 3 | June 2015 | Pages 245-253
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT14-73
Natural Circulation in Heat Removal System During Loss-of-Flow Accident Based on Initial Conceptual Design
Si Y. Lee, L. Larry Hamm, Frank G. Smith III
Nuclear Technology | Volume 190 | Number 3 | June 2015 | Pages 254-263
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT14-86
Experiments in Cap-Bubbly Two-Phase Flows for Two-Group IATE Development
Ted Worosz, Seungjin Kim, Chris Hoxie
Nuclear Technology | Volume 190 | Number 3 | June 2015 | Pages 264-273
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT14-71
Estimation of Shear-Induced Lift Force in Laminar and Turbulent Flows
Aaron M. Thomas, Jun Fang, Jinyong Feng, Igor A. Bolotnov
Nuclear Technology | Volume 190 | Number 3 | June 2015 | Pages 274-291
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT14-72
Modification of SCWR Assembly Designs with Coupled MCNP5/SCA Methods to Promote Safer Operation
Christopher R. Hughes, Oswaldo Pelaez, Duwayne Schubring, Kelly A. Jordan
Nuclear Technology | Volume 190 | Number 3 | June 2015 | Pages 292-300
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT14-74
Experimental Investigation of Inverted Annular Film Boiling in a Rod Bundle During Reflood Transient
L. Mohanta, M. P. Riley, F. B. Cheung, S. M. Bajorek, J. M. Kelly, K. Tien, C. L. Hoxie
Nuclear Technology | Volume 190 | Number 3 | June 2015 | Pages 301-312
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT14-77
An Advanced One-Dimensional Finite Element Model for Incompressible Thermally Expandable Flow
Rui Hu
Nuclear Technology | Volume 190 | Number 3 | June 2015 | Pages 313-322
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT14-78
The Modeling of Advanced BWR Fuel Designs with the NRC Fuel Depletion Codes PARCS/PATHS
A. Wysocki, A. Ward, A. Manera, T. Downar, Y. Xu, J. March-Leuba, C. Thurston, N. Hudson, A. Ireland
Nuclear Technology | Volume 190 | Number 3 | June 2015 | Pages 323-335
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT14-79
Experimental Studies of Spacer Grid Thermal Hydraulics in the Dispersed Flow Film Boiling Regime
M. P. Riley, L. Mohanta, F. B. Cheung, S. M. Bajorek, K. Tien, C. L. Hoxie
Nuclear Technology | Volume 190 | Number 3 | June 2015 | Pages 336-344
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT14-80
Effects of SiC and Graphene Oxide Nanoparticle–Coated Surfaces on Quenching Performance
Kyung Mo Kim, Seung Won Lee, In Cheol Bang
Nuclear Technology | Volume 190 | Number 3 | June 2015 | Pages 345-358
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT14-82
On the Steady Mechanical Response of a Heterogeneous Fuel Plate
W. R. Marcum, T. V. Holschuh, T. K. Howard
Nuclear Technology | Volume 190 | Number 3 | June 2015 | Pages 359-375
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT14-61
