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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 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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Core Design and Fuel Management Studies of a Thorium-Breeder Pebble Bed High-Temperature Reactor
Frank Wols, Jan Leen Kloosterman, Danny Lathouwers, Tim Van Der Hagen
Nuclear Technology | Volume 186 | Number 1 | April 2014 | Pages 1-16
Technical Paper | Fission Reactors | doi.org/10.13182/NT13-14
High-Utilization Lattices for Thorium-Based Fuels in Heavy Water Reactors
Blair P. Bromley
Nuclear Technology | Volume 186 | Number 1 | April 2014 | Pages 17-32
Technical Paper | Fission Reactors | doi.org/10.13182/NT13-86
A Feasibility Study of Load-Follow Operation Without Boron Adjustment for CPR1000
Li Wang, Yang Liu, Fuyu Zhao
Nuclear Technology | Volume 186 | Number 1 | April 2014 | Pages 33-44
Technical Paper | Fission Reactors | doi.org/10.13182/NT13-15
Graphite Particle Adhesion to Hastelloy X: Measurements of the Adhesive Force with an Atomic Force Microscope
Naphtali M. Mokgalapa, Tushar K. Ghosh, Sudarshan K. Loyalka
Nuclear Technology | Volume 186 | Number 1 | April 2014 | Pages 45-59
Technical Paper | Reactor Safety | doi.org/10.13182/NT13-9
A Neutronic Investigation of the Use of Fully Ceramic Microencapsulated Fuel for Pu/Np Burning in PWRs
Cole Gentry, Ivan Maldonado, Andrew Godfrey, Kurt Terrani, Jess Gehin, Jeffrey Powers
Nuclear Technology | Volume 186 | Number 1 | April 2014 | Pages 60-75
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT13-75
Stochastic Optimization for Nuclear Facility Deployment Scenarios Using VISION
Ross Hays, Paul Turinsky
Nuclear Technology | Volume 186 | Number 1 | April 2014 | Pages 76-89
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT13-68
Partial Defect Evaluation Methodology for Nuclear Safeguards Inspections of Used Nuclear Fuel Using the Digital Cherenkov Viewing Device
Sophie Grape, Staffan Jacobsson Svärd, Bo Lindberg
Nuclear Technology | Volume 186 | Number 1 | April 2014 | Pages 90-98
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT13-12
Modeling of Particulate Behavior in Pinhole Breaches
Andrew M. Casella, Sudarshan K. Loyalka, Brady D. Hanson
Nuclear Technology | Volume 186 | Number 1 | April 2014 | Pages 99-114
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT13-55
The Canary, the Ostrich, and the Black Swan: A Historical Perspective on our Understanding of BWR Severe Accidents and Their Mitigation
Sherrell R. Greene
Nuclear Technology | Volume 186 | Number 2 | May 2014 | Pages 115-138
Technical Paper | Reactor Safety | doi.org/10.13182/NT13-44
NRC's Significance Determination Process: Current Status and Future Trends in Assessing Risks Attributed to External Events
Sunil D. Weerakkody
Nuclear Technology | Volume 186 | Number 2 | May 2014 | Pages 139-144
Technical Paper | Reactor Safety | doi.org/10.13182/NT13-39
Insight From Fukushima Daiichi Unit 3 Investigations Using MELCOR
Kevin R. Robb, Matthew W. Francis, Larry J. Ott
Nuclear Technology | Volume 186 | Number 2 | May 2014 | Pages 145-160
Technical Paper | Reactor Safety | doi.org/10.13182/NT13-43
MELCOR Simulations of the Severe Accident at the Fukushima Daiichi Unit 1 Reactor
Randall Gauntt, Donald Kalinich, Jeffrey Cardoni, Jesse Phillips
Nuclear Technology | Volume 186 | Number 2 | May 2014 | Pages 161-178
Technical Paper | Reactor Safety | doi.org/10.13182/NT13-59
MELCOR Simulations of the Severe Accident at Fukushima Daiichi Unit 3
Jeffrey Cardoni, Randall Gauntt, Donald Kalinich, Jesse Phillips
Nuclear Technology | Volume 186 | Number 2 | May 2014 | Pages 179-197
Technical Paper | Reactor Safety | doi.org/10.13182/NT13-41
A Reassessment of Low Probability Containment Failure Modes and Phenomena in a Long-Term Station Blackout
Acacia Brunett, Richard Denning, Tunc Aldemir
Nuclear Technology | Volume 186 | Number 2 | May 2014 | Pages 198-215
Technical Paper | Reactor Safety | doi.org/10.13182/NT13-40
Estimation of the Depressurization Process of Fukushima Daiichi NPP Unit 1 with SAMPSON
Maolong Liu, Yuki Ishiwatari, Koji Okamoto
Nuclear Technology | Volume 186 | Number 2 | May 2014 | Pages 216-228
Technical Paper | Fission Reactors | doi.org/10.13182/NT13-57
Material Effect in the Nuclear Fuel–Coolant Interaction: Analyses of Prototypic Melt Fragmentation and Solidification in the KROTOS Facility
Vaclav Tyrpekl, Pascal Piluso, Snejana Bakardjieva, Olivier Dugne
Nuclear Technology | Volume 186 | Number 2 | May 2014 | Pages 229-240
Technical Paper | Reactor Safety | doi.org/10.13182/NT13-63
Early Phase Accident Progression Analysis of Fukushima Daiichi Unit 3 by the SAMPSON Code
Marco Pellegrini, Hiroaki Suzuki, Hideo Mizouchi, Masanori Naitoh
Nuclear Technology | Volume 186 | Number 2 | May 2014 | Pages 241-254
Technical Paper | Reactor Safety | doi.org/10.13182/NT13-107
Analysis of Accident Progression with the SAMPSON Code in Fukushima Daiichi Nuclear Power Plant Unit 2
Hiroaki Suzuki, Masanori Naitoh, Atsuo Takahashi, Marco Pellegrini, Hidetoshi Okada
Nuclear Technology | Volume 186 | Number 2 | May 2014 | Pages 255-262
Technical Paper | Reactor Safety | doi.org/10.13182/NT13-42
Update of the First TEPCO MAAP Accident Analysis of Units 1, 2, and 3 at Fukushima Daiichi Nuclear Power Station
Yasunori Yamanaka, Shinya Mizokami, Manabu Watanabe, Takeshi Honda
Nuclear Technology | Volume 186 | Number 2 | May 2014 | Pages 263-279
Technical Paper | Reactor Safety | doi.org/10.13182/NT13-46
Successful Cold Shutdown of Onagawa: The Closest Nuclear Power Station to the March 11, 2011, Epicenter
Akiyoshi Obonai, Takao Watanabe, Kazuo Hirata
Nuclear Technology | Volume 186 | Number 2 | May 2014 | Pages 280-294
Technical Paper | Reactor Safety | doi.org/10.13182/NT13-61
KAERI's Development of LWR Accident-Tolerant Fuel
Yang-Hyun Koo, Jae-Ho Yang, Jeong-Yong Park, Keon-Sik Kim, Hyun-Gil Kim, Dong-Joo Kim, Yang-Il Jung, Kun-Woo Song
Nuclear Technology | Volume 186 | Number 2 | May 2014 | Pages 295-304
Technical Note | Reactor Safety | doi.org/10.13182/NT13-89
Assessment of MICROX-2 Code with New ENDF/B-VII Release 0 Master Libraries
Jia (Jason) Hou, Hangbok Choi, Kostadin Ivanov
Nuclear Technology | Volume 186 | Number 3 | June 2014 | Pages 305-316
Technical Paper | Fission Reactors | doi.org/10.13182/NT12-137
Heterogeneous Cores for Implementation of Thorium-Based Fuels in Heavy Water Reactors
Blair P. Bromley, Bronwyn Hyland
Nuclear Technology | Volume 186 | Number 3 | June 2014 | Pages 317-339
Technical Paper | Fission Reactors | doi.org/10.13182/NT13-85
A Study of the Containment Venting Strategy for the Fukushima Daiichi Accident
Yu-Huai Shih, Shih-Jen Wang, Kai-Cheng Chuang, Tzu-En Huang
Nuclear Technology | Volume 186 | Number 3 | June 2014 | Pages 340-352
Technical Paper | Reactor Safety | doi.org/10.13182/NT12-145
Fuel Management of PWR Cores with Silicon Carbide Cladding
Jacob Dobisesky, Joshua Richard, Edward E. Pilat, Mujid S. Kazimi, David M. Carpenter
Nuclear Technology | Volume 186 | Number 3 | June 2014 | Pages 353-377
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT12-131
Uranium Startup Fast Reactors with Metal Fuel Using Once-Through Fuel Cycle
T. Fei, M. J. Driscoll, E. Shwageraus
Nuclear Technology | Volume 186 | Number 3 | June 2014 | Pages 378-389
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT13-21
A Core Design Study on the Fuel Displacement Options for an Effective Transition Between Breakeven and TRU Burning Sodium-Cooled Fast Reactors
Sang Ji Kim, Pham Nhu Viet Ha, Jae Yong Lim, Won Sik Yang
Nuclear Technology | Volume 186 | Number 3 | June 2014 | Pages 390-402
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT13-90
Quantitative NDA Measurements of Multiactinide Oxide Fuels
Braden Goddard, William Charlton, Paolo Peerani
Nuclear Technology | Volume 186 | Number 3 | June 2014 | Pages 403-414
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT13-18
Predicting Concrete Roadway Contribution to Gamma-Ray Background in Radiation Portal Monitor Systems
Christopher M. Ryan, Craig M. Marianno, William S. Charlton, Alexander A. Solodov, Ronald J. Livesay, Braden Goddard
Nuclear Technology | Volume 186 | Number 3 | June 2014 | Pages 415-426
Technical Paper | Radiation Transport and Protection | doi.org/10.13182/NT13-98
