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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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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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Enhanced Simmer Neutronics Tool for Studying Fast Reactor Distorted Core Configurations
Sandra Poumerouly, Gérald Rimpault
Nuclear Technology | Volume 174 | Number 1 | April 2011 | Pages 1-17
Technical Paper | Accident Analysis and Consequences | doi.org/10.13182/NT11-A11675
Numerical Modeling of Flow in the Condensate Polisher Vessel of a Nuclear Reactor, with Applications to PVNGS
Ashish Sharma, Jeffrey Brown, Harindra J. S. Fernando
Nuclear Technology | Volume 174 | Number 1 | April 2011 | Pages 18-28
Technical Paper | One-Phase Fluid Flow | doi.org/10.13182/NT11-A11676
Safety Analysis for Hot Gas Duct Vessel in HTR-PM
Xiaotian Li, Xiaowei Li, Li Shi, Zhengming Zhang, Shuyan He
Nuclear Technology | Volume 174 | Number 1 | April 2011 | Pages 29-40
Technical Paper | One-Phase Fluid Flow | doi.org/10.13182/NT11-A11677
Improved Simulations of Heat Transfer in Liquid-Metal Flows
Constantine P. Tzanos
Nuclear Technology | Volume 174 | Number 1 | April 2011 | Pages 41-50
Technical Paper | Heat Transfer | doi.org/10.13182/NT11-A11678
Qualification of the RELAP5/PARCS Code for BWR Stability Events Prediction
Tomasz Kozlowski, Joanna Peltonen
Nuclear Technology | Volume 174 | Number 1 | April 2011 | Pages 51-63
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT11-A11679
Observation of the Dynamics of Nuclear Systems Using Sliding Mode Observers
Günyaz Ablay, Tunc Aldemir
Nuclear Technology | Volume 174 | Number 1 | April 2011 | Pages 64-76
Technical Paper | Instrumentation and Control Systems | doi.org/10.13182/NT11-A11680
Enhancement of Decontamination Performance of Impurities for Uranyl Nitrate Hexahydrate Crystalline Particles by Crystal Purification Operation
Masaumi Nakahara, Tsutomu Koizumi, Kazunori Nomura
Nuclear Technology | Volume 174 | Number 1 | April 2011 | Pages 77-84
Technical Paper | Chemical Reprocessing | doi.org/10.13182/NT11-A11681
Diffusion Model for Electrolytic Reduction of Uranium Oxides in a Molten LiCl-Li2O Salt
Supathorn Phongikaroon, Steven D. Herrmann, Michael F. Simpson
Nuclear Technology | Volume 174 | Number 1 | April 2011 | Pages 85-93
Technical Paper | Reprocessing | doi.org/10.13182/NT174-85
Impacts of Elevated Temperatures on Bentonite Extrusion and Cesium Transport in the Excavated Damaged Zone
R. A. Borrelli, Olivier Thivent, Joonhong Ahn
Nuclear Technology | Volume 174 | Number 1 | April 2011 | Pages 94-108
Technical Paper | Geochemistry and Ground Transport of RW | doi.org/10.13182/NT11-A11683
Behavior of Actinide Elements and Fission Products in Recovery of Uranyl Nitrate Hexahydrate Crystal by Cooling Crystallization Method
Nuclear Technology | Volume 174 | Number 1 | April 2011 | Pages 109-118
Technical Paper | Radiochemistry | doi.org/10.13182/NT11-A11684
Development and Testing of a Nanotech Nuclear Battery for Powering MEMS Devices
Eric V. Steinfelds, James S. Tulenko
Nuclear Technology | Volume 174 | Number 1 | April 2011 | Pages 119-123
Technical Paper | Energy Conversion Systems Using Radioisotopes | doi.org/10.13182/NT11-A11685
Foreword: Special Issue on the SCALE Nuclear Analysis Code System
John C. Wagner
Nuclear Technology | Volume 174 | Number 2 | May 2011 | Page 125
doi.org/10.13182/NT11-A11716
SCALE 6: Comprehensive Nuclear Safety Analysis Code System
S. M. Bowman
Nuclear Technology | Volume 174 | Number 2 | May 2011 | Pages 126-148
Technical Paper | Special Issue on the SCALE Nuclear Analysis Code System / Reactor Safety | doi.org/10.13182/NT10-163
Resonance Self-Shielding Methodologies in SCALE 6
Mark L. Williams
Nuclear Technology | Volume 174 | Number 2 | May 2011 | Pages 149-168
Technical Paper | Special Issue on the SCALE Nuclear Analysis Code System / Reactor Physics | doi.org/10.13182/NT09-104
Isotopic Depletion and Decay Methods and Analysis Capabilities in SCALE
Ian C. Gauld, Georgeta Radulescu, Germina Ilas, Brian D. Murphy, Mark L. Williams, Dorothea Wiarda
Nuclear Technology | Volume 174 | Number 2 | May 2011 | Pages 169-195
Technical Paper | Special Issue on the SCALE Nuclear Analysis Code System / Fuel Cycle and Management | doi.org/10.13182/NT11-3
Reactor Physics Methods and Analysis Capabilities in SCALE
Mark D. DeHart, Stephen M. Bowman
Nuclear Technology | Volume 174 | Number 2 | May 2011 | Pages 196-213
Technical Paper | Special Issue on the SCALE Nuclear Analysis Code System / Reactor Physics | doi.org/10.13182/NT174-196
Monte Carlo Criticality Methods and Analysis Capabilities in SCALE
Sedat Goluoglu, Lester M. Petrie, Jr., Michael E. Dunn, Daniel F. Hollenbach, Bradley T. Rearden
Nuclear Technology | Volume 174 | Number 2 | May 2011 | Pages 214-235
Technical Paper | Special Issue on the SCALE Nuclear Analysis Code System / Reactor Safety | doi.org/10.13182/NT10-124
Sensitivity and Uncertainty Analysis Capabilities and Data in SCALE
B. T. Rearden, M. L. Williams, M. A. Jessee, D. E. Mueller, D. A. Wiarda
Nuclear Technology | Volume 174 | Number 2 | May 2011 | Pages 236-288
Technical Paper | Special Issue on the SCALE Nuclear Analysis Code System / Radiation Protection | doi.org/10.13182/NT174-236
Monte Carlo Shielding Analysis Capabilities with MAVRIC
Douglas E. Peplow
Nuclear Technology | Volume 174 | Number 2 | May 2011 | Pages 289-313
Technical Paper | Special Issue on the SCALE Nuclear Analysis Code System / Radiation Protection | doi.org/10.13182/NT174-289
Foreword: Special Issue on the 2009 TOUGH2 Symposium
George J. Moridis
Nuclear Technology | Volume 174 | Number 3 | June 2011 | Pages 315-316
doi.org/10.13182/NT11-A11741
Estimation of Humidity During Tunnel Ventilation - Supported by TOUGH2 Calculations of Liquid, Vapor, and Heat Transport
Joachim Poppei, Gerhard Mayer, Nicolas Hubschwerlen, Guillaume Pépin, Jacques Wendling
Nuclear Technology | Volume 174 | Number 3 | June 2011 | Pages 317-326
Technical Note | TOUGH2 Symposium / Thermal Hydraulics | doi.org/10.13182/NT11-A11742
Natural Convection in Tunnels at Yucca Mountain and Impact on Drift Seepage
N. Halecky, J. Birkholzer, P. Peterson
Nuclear Technology | Volume 174 | Number 3 | June 2011 | Pages 327-341
Technical Paper | TOUGH2 Symposium / Radioactive Waste Management and Disposal | doi.org/10.13182/NT11-A11743
Chemical Evolution of Bentonite Buffer in a Final Repository of Spent Nuclear Fuel During the Thermal Phase
Aku Itälä, Markus Olin
Nuclear Technology | Volume 174 | Number 3 | June 2011 | Pages 342-352
Technical Paper | TOUGH2 Symposium / Radioactive Waste Management and Disposal | doi.org/10.13182/NT11-A11744
Simulation of Gas Transfer at the Scale of a Disposal Cell in the Context of High-Level and Long-Lived Radwaste Disposal in a Deep Clay Formation During the Operating Phase
E. Treille, J. Wendling, F. Plas
Nuclear Technology | Volume 174 | Number 3 | June 2011 | Pages 353-363
Technical Paper | TOUGH2 Symposium / Radioactive Waste Management and Disposal | doi.org/10.13182/NT11-A11745
Computation of the Couplex-Gaz Exercise with TOUGH2-MP: Hydrogen Flow and Transport in the Pore Water of a Low-Permeability Clay Rock Hosting a Nuclear Waste Repository
Keni Zhang, Jean Croisé, Gerhard Mayer
Nuclear Technology | Volume 174 | Number 3 | June 2011 | Pages 364-374
Technical Paper | TOUGH2 Symposium / Radioactive Waste Management and Disposal | doi.org/10.13182/NT11-A11746
A Turbulent Transport Network Model in MULTIFLUX Coupled with TOUGH2
G. Danko, D. Bahrami, J. Birkholzer
Nuclear Technology | Volume 174 | Number 3 | June 2011 | Pages 375-400
Technical Paper | TOUGH2 Symposium / Thermal Hydraulics | doi.org/10.13182/NT11-A11747
Thermohydraulic Analysis of Gas Generation in a Disposal Facility for Vitrified High-Level Radioactive Waste in Boom Clay
Janez Perko, Eef Weetjens
Nuclear Technology | Volume 174 | Number 3 | June 2011 | Pages 401-410
Technical Paper | TOUGH2 Symposium / Radioactive Waste Management and Disposal | doi.org/10.13182/NT11-A11748
Comparison of Numerical Tools Through Thermo-Hydro-Gas Transport Modeling for a Geological Repository in Boom Clay
L. Yu, E. Weetjens, J. Perko, D. Mallants
Nuclear Technology | Volume 174 | Number 3 | June 2011 | Pages 411-423
Technical Paper | TOUGH2 Symposium / Radioactive Waste Management and Disposal | doi.org/10.13182/NT11-A11749
Numerical Simulation of Atmospheric Carbonation of Concrete Components in a Deep Geological Radwaste Disposal Site During Operating Period
L. Trotignon, P. Thouvenot, I. Munier, B. Cochepin, E. Piault, E. Treille, X. Bourbon, S. Mimid
Nuclear Technology | Volume 174 | Number 3 | June 2011 | Pages 424-437
Technical Paper | TOUGH2 Symposium / Radioactive Waste Management and Disposal | doi.org/10.13182/NT11-A11750
Bentonite Alteration Due to Thermal-Hydro-Chemical Processes During the Early Thermal Period in a Nuclear Waste Repository
Tianfu Xu, Rainer Senger, Stefan Finsterle
Nuclear Technology | Volume 174 | Number 3 | June 2011 | Pages 438-451
Technical Paper | TOUGH2 Symposium / Radioactive Waste Management and Disposal | doi.org/10.13182/NT11-A11751
Injection of Nuclear Rocket Exhaust and Water into a Deep Unsaturated Zone
Clay A. Cooper, David L. Decker
Nuclear Technology | Volume 174 | Number 3 | June 2011 | Pages 452-459
Technical Paper | TOUGH2 Symposium / Radioactive Waste Management and Disposal | doi.org/10.13182/NT11-A11752
