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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.
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Nuclear Technology
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Colin Judge: Testing structural materials in Idaho’s newest hot cell facility
Idaho National Laboratory’s newest facility—the Sample Preparation Laboratory (SPL)—sits across the road from the Hot Fuel Examination Facility (HFEF), which started operating in 1975. SPL will host the first new hot cells at INL’s Materials and Fuels Complex (MFC) in 50 years, giving INL researchers and partners new flexibility to test the structural properties of irradiated materials fresh from the Advanced Test Reactor (ATR) or from a partner’s facility.
Materials meant to withstand extreme conditions in fission or fusion power plants must be tested under similar conditions and pushed past their breaking points so performance and limitations can be understood and improved. Once irradiated, materials samples can be cut down to size in SPL and packaged for testing in other facilities at INL or other national laboratories, commercial labs, or universities. But they can also be subjected to extreme thermal or corrosive conditions and mechanical testing right in SPL, explains Colin Judge, who, as INL’s division director for nuclear materials performance, oversees SPL and other facilities at the MFC.
SPL won’t go “hot” until January 2026, but Judge spoke with NN staff writer Susan Gallier about its capabilities as his team was moving instruments into the new facility.
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The Offshore Floating Nuclear Plant Concept
J. Buongiorno, J. Jurewicz, M. Golay, N. Todreas
Nuclear Technology | Volume 194 | Number 1 | April 2016 | Pages 1-14
Technical Paper | doi.org/10.13182/NT15-49
Assembly Design of Pressurized Water Reactors with Fully Ceramic Microencapsulated Fuel
Rachel A. Shapiro, Massimiliano Fratoni
Nuclear Technology | Volume 194 | Number 1 | April 2016 | Pages 15-27
Technical Paper | doi.org/10.13182/NT15-97
FiR 1 TRIGA Activity Inventories for Decommissioning Planning
Antti Räty, Petri Kotiluoto
Nuclear Technology | Volume 194 | Number 1 | April 2016 | Pages 28-38
Technical Paper | doi.org/10.13182/NT15-86
Development of the APSRA+ Methodology for Passive System Reliability Analysis and Its Application to the Passive Isolation Condenser System of an Advanced Reactor
A. Chandrakar, A. K. Nayak, Vinod Gopika
Nuclear Technology | Volume 194 | Number 1 | April 2016 | Pages 39-60
Technical Paper | doi.org/10.13182/NT15-80
Implementing Obliquely Inserted Control Rods Into RELAP5-3D/NESTLE Model for Atucha-2
R. G. Gonzalez, F. D'Auria, O. Mazzantini
Nuclear Technology | Volume 194 | Number 1 | April 2016 | Pages 61-72
Technical Paper | doi.org/10.13182/NT14-155
Human Reliability Modeling of Radiotherapy Procedures by Bayesian Networks and Expert Opinion Elicitation
E. C. Gomes, J. P. Duarte, P. F. Frutuoso e Melo
Nuclear Technology | Volume 194 | Number 1 | April 2016 | Pages 73-96
Technical Paper | doi.org/10.13182/NT15-29
Upgrade and Simulation of the Subcritical Assembly at Missouri University of Science and Technology
Lucas P. Tucker, Shoaib Usman, Ayodeji Alajo
Nuclear Technology | Volume 194 | Number 1 | April 2016 | Pages 97-110
Technical Paper | doi.org/10.13182/NT15-67
X-Ray Residual Stress Measurement of Austenitic Stainless Steel Based on Fourier Analysis
Toshiyuki Miyazaki, Toshihiko Sasaki
Nuclear Technology | Volume 194 | Number 1 | April 2016 | Pages 111-116
Technical Note | doi.org/10.13182/NT15-25
Evaluation of a Modified HPGe Preamplifier for High-Rate Spectroscopy Measurements in a Pulsed Photonuclear Environment
Xianfei Wen, Dante Nakazawa, Mat Kastner, Jason Pavlick, Haori Yang
Nuclear Technology | Volume 194 | Number 1 | April 2016 | Pages 117-125
Technical Note | doi.org/10.13182/NT15-113
Thorium Fuel Cycle Option Screening in the United States
Temitope A. Taiwo, Taek K. Kim, Roald A. Wigeland
Nuclear Technology | Volume 194 | Number 2 | May 2016 | Pages 127-135
Technical Note | doi.org/10.13182/NT15-119
Natural Thorium Resources and Recovery: Options and Impacts
Timothy Ault, Bradley Van Gosen, Steven Krahn, Allen Croff
Nuclear Technology | Volume 194 | Number 2 | May 2016 | Pages 136-151
Technical Paper | doi.org/10.13182/NT15-83
Liquid Fuel Molten Salt Reactors for Thorium Utilization
Jess C. Gehin, Jeffrey J. Powers
Nuclear Technology | Volume 194 | Number 2 | May 2016 | Pages 152-161
Technical Paper | doi.org/10.13182/NT15-124
Analysis of Key Safety Metrics of Thorium Utilization in LWRs
Brian Ade, Andrew Worrall, Jeffrey Powers, Steve Bowman
Nuclear Technology | Volume 194 | Number 2 | May 2016 | Pages 162-177
Technical Paper | doi.org/10.13182/NT15-100
Simulations of a Pressure-Tube Heavy Water Reactor Operating on Near-Breeding Thorium Cycles
Sourena Golesorkhi, Blair P. Bromley, Matthew H. Kaye
Nuclear Technology | Volume 194 | Number 2 | May 2016 | Pages 178-191
Technical Paper | doi.org/10.13182/NT15-30
Multiregion Annular Heterogeneous Core Concepts for Plutonium-Thorium Fuels in Pressure-Tube Heavy Water Reactors
Blair P. Bromley
Nuclear Technology | Volume 194 | Number 2 | May 2016 | Pages 192-203
Technical Paper | doi.org/10.13182/NT14-101
Steady State and Accident Transient Analysis Burning Weapons-Grade Plutonium in Thorium and Uranium with Silicon Carbide Cladding
Nathan Andrews, Koroush Shirvan, Edward E. Pilat, Mujid S. Kazimi
Nuclear Technology | Volume 194 | Number 2 | May 2016 | Pages 204-216
Technical Paper | doi.org/10.13182/NT15-41
A Core Physics Study of Advanced Sodium-Cooled TRU Burners with Thorium- and Uranium-Based Metallic Fuels
Wuseung You, Ser Gi Hong
Nuclear Technology | Volume 194 | Number 2 | May 2016 | Pages 217-232
Technical Paper | doi.org/10.13182/NT15-85
Thorium Fuel Cycles with Externally Driven Systems
Nicholas R. Brown, Jeffrey J. Powers, Michael Todosow, Massimiliano Fratoni, Hans Ludewig, Eva E. Sunny, Gilad Raitses, Arnold Aronson
Nuclear Technology | Volume 194 | Number 2 | May 2016 | Pages 233-251
Technical Paper | doi.org/10.13182/NT15-40
ORNL Experience and Perspectives Related to Processing of Thorium and 233U for Nuclear Fuel
Allen G. Croff, Emory D. Collins, G. D. Del Cul, R. G. Wymer, Alan M. Krichinsky, B. B. Spencer, Brad D. Patton
Nuclear Technology | Volume 194 | Number 2 | May 2016 | Pages 252-270
Technical Paper | doi.org/10.13182/NT15-59
Comparative Assessment of Thorium Fuel Cycle Radiotoxicity
Allen G. Croff, Steven L. Krahn
Nuclear Technology | Volume 194 | Number 2 | May 2016 | Pages 271-280
Technical Paper | doi.org/10.13182/NT15-46
Safeguards Considerations for Thorium Fuel Cycles
Louise G. Worrall, Andrew Worrall, George F. Flanagan, Stephen Croft, Alan M. Krichinsky, Chris A. Pickett, Robert D. McElroy, Jr., Steven L. Cleveland, Donald N. Kovacic, J. Michael Whitaker, and Jessica L. White-Horton
Nuclear Technology | Volume 194 | Number 2 | May 2016 | Pages 281-293
Technical Paper | doi.org/10.13182/NT15-103
Understanding and Pathways to Avoid Major Fuel Failures and Radionuclide Releases in Fluoride Salt–Cooled High-Temperature Reactor Severe Accidents
C. W. Forsberg, J. D. Stempien, M. J. Minck, R. G. Ballinger
Nuclear Technology | Volume 194 | Number 3 | June 2016 | Pages 295-313
Technical Paper | doi.org/10.13182/NT15-87
Partial Loading of Thorium-Plutonium Fuel in a Pressurized Water Reactor
M. Yousif Alhaj, Alya Badawi, Hanaa H. Abou-Gabal, Nader M. A. Mohamed
Nuclear Technology | Volume 194 | Number 3 | June 2016 | Pages 314-323
Technical Paper | doi.org/10.13182/NT15-78
Neutronic Analysis of the PSBR Using a Burnup-Coupled MCNP Simulation with MURE
Dağıstan Şahin, Kenan Ünlü, Kostadin Ivanov
Nuclear Technology | Volume 194 | Number 3 | June 2016 | Pages 324-339
Technical Paper | doi.org/10.13182/NT15-110
Impact of Rare Earth Recovery Fraction on Core Physics Parameters of the Korean SFR for TRU Transmutation
Sang Ji Kim, Pham Nhu Viet Ha, Jae Yong Lim
Nuclear Technology | Volume 194 | Number 3 | June 2016 | Pages 340-352
Technical Paper | doi.org/10.13182/NT15-53
Adhesion Force Between a Silver Particle and Haynes 230: Role of Surface Conditions
Naphtali M. Mokgalapa, Tushar K. Ghosh, Robert V. Tompson, Sudarshan K. Loyalka
Nuclear Technology | Volume 194 | Number 3 | June 2016 | Pages 353-368
Technical Paper | doi.org/10.13182/NT15-106
Gamma Radiation Thermal Stability of Two-Phase Mixtures of Nitric Acid with Degraded TBP in a Closed Vessel
E. R. Nazin, G. M. Zachinyaev, A. V. Rodin, E. V. Belova, G. P. Thorzhnitsky, B. F. Myasoedov
Nuclear Technology | Volume 194 | Number 3 | June 2016 | Pages 369-378
Technical Paper | doi.org/10.13182/NT15-77
Filtering of Low-Level Radioactive Wastewater by Means of Vacuum Membrane Distillation
Xia Wen, Fuzhi Li, Xuan Zhao
Nuclear Technology | Volume 194 | Number 3 | June 2016 | Pages 379-386
Technical Paper | doi.org/10.13182/NT15-74
Effects of Gas Rarefaction on Used Nuclear Fuel Cladding Temperatures During Vacuum Drying
M. Hadj-Nacer, T. Manzo, M. T. Ho, I. Graur, M. Greiner
Nuclear Technology | Volume 194 | Number 3 | June 2016 | Pages 387-399
Technical Paper | doi.org/10.13182/NT15-82
MCNP Airport Investigation Room Design Based on Neutron-Gamma Technique
A. M. Reda
Nuclear Technology | Volume 194 | Number 3 | June 2016 | Pages 400-405
Technical Note | doi.org/10.13182/NT15-92
