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Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
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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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Criticality Safety and Sensitivity Analyses of PWR Spent Nuclear Fuel Repository Facilities
Marko Maucec, Bogdan Glumac
Nuclear Technology | Volume 149 | Number 1 | January 2005 | Pages 1-13
Technical Paper | Reactor Safety | doi.org/10.13182/NT05-A3575
A New Apparatus for Determination of the Free Volume of a Fuel Rod Using the Double Expansion Method
Lionel Desgranges, Marie-Hèlene Faure, Alain Thouroude
Nuclear Technology | Volume 149 | Number 1 | January 2005 | Pages 14-21
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT05-A3576
The Encapsulated Nuclear Heat Source (ENHS) Reactor Core Design
Ser Gi Hong, Ehud Greenspan, Yeong Il Kim
Nuclear Technology | Volume 149 | Number 1 | January 2005 | Pages 22-48
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT05-A3577
Computational Fluid Dynamics Prediction of Grid Spacer Thermal-Hydraulic Performance with Comparison to Experimental Results
Robert L. Campbell, John M. Cimbala, Lawrence E. Hochreiter
Nuclear Technology | Volume 149 | Number 1 | January 2005 | Pages 49-61
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT05-A3578
Numerical Optimization for the Design of a Spacer Grid with Mixing Vanes in a Pressurized Water Reactor Fuel Assembly
Kwang-Yong Kim, Jun-Woo Seo
Nuclear Technology | Volume 149 | Number 1 | January 2005 | Pages 62-70
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT05-A3579
Modeling of Flow Blockage in a Liquid Metal-Cooled Reactor Subassembly with a Subchannel Analysis Code
Hae-Yong Jeong, Kwi-Seok Ha, Won-Pyo Chang, Young-Min Kwon, Yong-Bum Lee
Nuclear Technology | Volume 149 | Number 1 | January 2005 | Pages 71-87
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT05-A3580
Experimental Research on In-Tube Condensation Under Steady-State and Transient Conditions
Ali Tanrikut, Orhan Yesin
Nuclear Technology | Volume 149 | Number 1 | January 2005 | Pages 88-100
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT05-A3581
Monitoring an Experimental Reactor Using the Group Method of Data Handling Approach
Iraci Martinez Gonçalves, Daniel K. S. Ting, Paulo Brasko Ferreira, Belle R. Upadhyaya
Nuclear Technology | Volume 149 | Number 1 | January 2005 | Pages 101-109
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT05-A3582
Performance-Based (Risk-Informed) Regulation: A Regulatory Perspective
N. Prasad Kadambi
Nuclear Technology | Volume 149 | Number 1 | January 2005 | Pages 110-121
Technical Paper | Miscellaneous | doi.org/10.13182/NT05-A3583
Review and Research of the Neutron Source Multiplication Method in Nuclear Critical Safety
Yong-Qian Shi, Qing-Fu Zhu, He Tao
Nuclear Technology | Volume 149 | Number 1 | January 2005 | Pages 122-127
Technical Note | Reactor Safety | doi.org/10.13182/NT05-2
The Impact of Uncertainties on the Performance of Passive Systems
Lorenzo P. Pagani, George E. Apostolakis, Pavel Hejzlar
Nuclear Technology | Volume 149 | Number 2 | February 2005 | Pages 129-140
Technical Paper | Reactor Safety | doi.org/10.13182/NT149-129
Development of a Criticality Evaluation Method Considering the Particulate Behavior of Nuclear Fuel
Mikio Sakai, Toshihiro Yamamoto, Minoru Murazaki, Yoshinori Miyoshi
Nuclear Technology | Volume 149 | Number 2 | February 2005 | Pages 141-149
Technical Paper | Reactor Safety | doi.org/10.13182/NT05-A3586
Dynamics of Critical Dedicated Cores for Minor Actinide Transmutation
S. Massara, J. Tommasi, M. Vanier, O. Köberl
Nuclear Technology | Volume 149 | Number 2 | February 2005 | Pages 150-174
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT05-A3587
Impact of Pin-by-Pin Thermal-Hydraulic Feedback Modeling on Steady-State Core Characteristics
Akio Yamamoto, Tsutomu Ikeno
Nuclear Technology | Volume 149 | Number 2 | February 2005 | Pages 175-188
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT05-A3588
Thermal Interaction Between Molten Metal Jet and Sodium Pool: Effect of Principal Factors Governing Fragmentation of the Jet
Satoshi Nishimura, Izumi Kinoshita, Ken-Ichiro Sugiyama, Nobuyuki Ueda
Nuclear Technology | Volume 149 | Number 2 | February 2005 | Pages 189-199
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT05-A3589
Integral Test and Engineering Analysis of Coolant Depletion During a Large-Break Loss-of-Coolant Accident
Yong Soo Kim, Chang Hwan Park, Byoung Uhn Bae, Goon Cherl Park, Kune Yull Suh, Un Chul Lee
Nuclear Technology | Volume 149 | Number 2 | February 2005 | Pages 200-216
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT05-A3590
Development of a New Aqueous Process for Nuclear Fuel Reprocessing: Hot Tests on the Recovery of U and Pu from a Nitric Acid Solution of Spent LWR Fuel
Yuezhou Wei, Tsuyoshi Arai, Harutaka Hoshi, Mikio Kumagai, Aimé Bruggeman, Patrick Goethals
Nuclear Technology | Volume 149 | Number 2 | February 2005 | Pages 217-231
Technical Paper | Reprocessing | doi.org/10.13182/NT05-A3591
Chlorine Release from Hypalon Cable Insulation During Severe Nuclear Reactor Accidents
Ari Auvinen, Riitta Zilliacus, Jorma Jokiniemi
Nuclear Technology | Volume 149 | Number 2 | February 2005 | Pages 232-241
Technical Paper | Radioisotopes | doi.org/10.13182/NT05-A3592
Assessment on Integrity of BWR Internals Against Impact Load by Water Hammer Under Conditions of Reactivity Initiated Accidents
Mie Azuma, Atsushi Taniguchi, Akitoshi Hotta, Takeshi Ohta
Nuclear Technology | Volume 149 | Number 3 | March 2005 | Pages 243-252
Technical Paper | Fission Reactors | doi.org/10.13182/NT05-A3593
Assessments of Water Ingress Accidents in a Modular High-Temperature Gas-Cooled Reactor
Zuoyi Zhang, Yujie Dong, Winfried Scherer
Nuclear Technology | Volume 149 | Number 3 | March 2005 | Pages 253-264
Technical Paper | Fission Reactors | doi.org/10.13182/NT05-A3594
Peach Bottom Turbine Trip Simulations with RETRAN Using INER/TPC BWR Transient Analysis Method
Lainsu Kao, Show-Chyuan Chiang
Nuclear Technology | Volume 149 | Number 3 | March 2005 | Pages 265-280
Technical Paper | Reactor Safety | doi.org/10.13182/NT05-A3595
A Combined Nonfertile and UO2 PWR Fuel Assembly for Actinide Waste Minimization
Eugene Shwageraus, Pavel Hejzlar, Mujid S. Kazimi
Nuclear Technology | Volume 149 | Number 3 | March 2005 | Pages 281-303
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT05-A3596
VVER-1000 Model Assessment Using RELAP5-3D
Emilian L. Popov, Graydon L. Yoder, Valeri Velichkov
Nuclear Technology | Volume 149 | Number 3 | March 2005 | Pages 304-308
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT05-A3597
The Effect of the UO2/ZrO2 Composition on Fuel/Coolant Interaction
Jin Ho Song, Jong Hwan Kim
Nuclear Technology | Volume 149 | Number 3 | March 2005 | Pages 309-323
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT05-A3598
Brayton Cycle for High-Temperature Gas-Cooled Reactors
Chang H. Oh, Richard L. Moore
Nuclear Technology | Volume 149 | Number 3 | March 2005 | Pages 324-336
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT05-A3599
Screening Experiments for Removal of Low-Level Tritiated Water
Yun Mi Kim, Ronald Baney, Kevin Powers, Ben Koopman, James Tulenko
Nuclear Technology | Volume 149 | Number 3 | March 2005 | Pages 337-342
Technical Note | Nuclear Plant Operations and Control | doi.org/10.13182/NT05-A3600
