ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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!
Latest Magazine Issues
Feb 2025
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
March 2025
Nuclear Technology
Fusion Science and Technology
February 2025
Latest News
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.
Jump to:
Passive System Reliability Analysis: A Study on the Isolation Condenser
Luciano Burgazzi
Nuclear Technology | Volume 139 | Number 1 | July 2002 | Pages 3-9
Technical Paper | doi.org/10.13182/NT139-3-9
Severe Accident Related Research and Development at Forschungszentrum Karlsruhe for Present and Future Needs
Werner Scholtyssek, Gerhard Heusener, Fritz Hofmann, Helmut Plitz
Nuclear Technology | Volume 139 | Number 1 | July 2002 | Pages 10-20
Technical Paper | doi.org/10.13182/NT02-A3298
The Model of the IBR-2 Pulsed Reactor Dynamics and Investigation of Pulse Energy Stabilization
Alexander K. Popov, Juri N. Pepyolyshev, Eugene A. Bondarchenko
Nuclear Technology | Volume 139 | Number 1 | July 2002 | Pages 21-29
Technical Paper | doi.org/10.13182/NT02-A3299
Regulatory Concerns on the In-Containment Water Storage System of the Korean Next Generation Reactor
Hyung-Joon Ahn, Jae-Hun Lee, Young-Seok Bang, Hho-Jung Kim
Nuclear Technology | Volume 139 | Number 1 | July 2002 | Pages 30-35
Technical Note | doi.org/10.13182/NT02-A3300
General Safety Criteria for the Korean Next Generation Reactor
Jae-Hun Lee, Woong-Sik Kim, Young Gill Yune, Jae-Seong Lee
Nuclear Technology | Volume 139 | Number 1 | July 2002 | Pages 36-41
Technical Note | doi.org/10.13182/NT02-A3301
Korean Standard Nuclear Power Plant Response to Common Mode Failure of the Digital Plant Protection System
Cheol Shin Lee, Chan Eok Park, Chul Jin Choi, Jong Tae Seo
Nuclear Technology | Volume 139 | Number 1 | July 2002 | Pages 42-49
Technical Note | doi.org/10.13182/NT02-A3302
Definition and Analysis of an Experimental Benchmark on Shutdown Rod Worths in LEU-HTR Configurations
Rakesh Chawla, Om Parkash Joneja, Marc Rosselet, Tony Williams
Nuclear Technology | Volume 139 | Number 1 | July 2002 | Pages 50-60
Technical Paper | Reactor Safety | doi.org/10.13182/NT02-A3303
A Methodology for Selecting High Thermal-Hydraulic Performance Fuel Configurations for Tightly Packed Epithermal Core Designs
Antonino Romano, Neil E. Todreas
Nuclear Technology | Volume 139 | Number 1 | July 2002 | Pages 61-71
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT02-A3304
Empirical and Computational Pressure Drop Correlations for Pressurized Water Reactor Fuel Spacer Grids
Wang Kee In, Dong Seok Oh, Tae Hyun Chun
Nuclear Technology | Volume 139 | Number 1 | July 2002 | Pages 72-79
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT02-A3305
Criticality Analysis of MOX and LEU Assemblies for Transport and Storage at the Balakovo Nuclear Power Plant
Sedat Goluoglu, R. T. Primm III
Nuclear Technology | Volume 139 | Number 1 | July 2002 | Pages 80-88
Technical Note | Criticality of Nuclear Materials | doi.org/10.13182/NT02-A3306
Investigation of the Effect of Fixed Absorbers on the Reactivity of PWR Spent Nuclear Fuel for Burnup Credit
John C. Wagner, Charlotta E. Sanders
Nuclear Technology | Volume 139 | Number 2 | August 2002 | Pages 91-126
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT02-A3307
Fuel-Coolant Interactions: Visualization and Mixing Measurements
Eric P. Loewen, Riccardo Bonazza, Michael L. Corradini, Robert E. Johannesen
Nuclear Technology | Volume 139 | Number 2 | August 2002 | Pages 127-144
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT02-A3308
Transport Characteristics of Selected Pressurized Water Reactor LOCA-Generated Debris
Arup K. Maji, Daseri V. Rao, Bruce Letellier, Luke Bartlein, Brooke Marshall
Nuclear Technology | Volume 139 | Number 2 | August 2002 | Pages 145-155
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT02-A3309
Building Up an On-Line Plant Information System for the Emergency Response Center of the Hungarian Nuclear Safety Directorate
János Végh, Csaba Major, Csaba Horváth, Zoltán Hózer, Ferenc Adorján, Iván Lux, Kristóf Horváth
Nuclear Technology | Volume 139 | Number 2 | August 2002 | Pages 156-166
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT02-A3310
Test of Actinide-Lanthanide Separation in an Aluminum-Based Pyrochemical System
Laurence Rault, Murielle Heusch, Michel Allibert, Florent Lemort, Xavier Deschanel, Roger Boen
Nuclear Technology | Volume 139 | Number 2 | August 2002 | Pages 167-174
Technical Paper | Reprocessing | doi.org/10.13182/NT02-A3311
Startup of the Fission Converter Epithermal Neutron Irradiation Facility at the MIT Reactor
Thomas H. Newton, Jr., Kent J. Riley, Peter J. Binns, Gordon E. Kohse, Lin-Wen Hu, Otto K. Harling
Nuclear Technology | Volume 139 | Number 2 | August 2002 | Pages 175-183
Technical Paper | Radiation Biology and Medicine | doi.org/10.13182/NT02-A3312
Simulation and Analysis of Experimental Blowdown and Small-Break Loss-of-Coolant Scenarios with RETRAN-3D
Rafael Macian, Paul Coddington
Nuclear Technology | Volume 139 | Number 3 | September 2002 | Pages 185-204
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT02-A3313
Visualization and Measurement of Subcooled Water Jet Injection into High-Temperature Melt by Using High-Frame-Rate Neutron Radiography
Yasuteru Sibamoto, Yutaka Kukita, Hideo Nakamura
Nuclear Technology | Volume 139 | Number 3 | September 2002 | Pages 205-220
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT02-A3314
Adequacy of the Heat-Mass Transfer Analogy to Simulate Containment Atmospheric Cooling in the New Generation of Advanced Nuclear Reactors: Experimental Confirmation
Luis E. Herranz, Antonio Campo
Nuclear Technology | Volume 139 | Number 3 | September 2002 | Pages 221-232
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT02-A3315
Development and Assessment of the Appendix K Version of RELAP5-3D for LOCA Licensing Analysis
Thomas K. S. Liang, Chin-Jang Chang, Huan-Jen Hung
Nuclear Technology | Volume 139 | Number 3 | September 2002 | Pages 233-252
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT02-A3316
Development of the Diamex Process for Treating PHWR High-Level Liquid Waste
L. B. Kumbhare, D. R. Prabhu, G. R. Mahajan, S. Sriram, V. K. Manchanda, L. P. Badheka
Nuclear Technology | Volume 139 | Number 3 | September 2002 | Pages 253-262
Technical Paper | Reprocessing | doi.org/10.13182/NT02-A3317
A Real-Time Graphic Simulator to Monitor Spent Nuclear Fuel Dismantlement Devices
Soon-Hyuk Hong, Jae Wook Jeon, Tai Gil Song, Jong Youl Lee, Sung Hyun Kim, Ji Sup Yoon
Nuclear Technology | Volume 139 | Number 3 | September 2002 | Pages 263-273
Technical Note | Radioactive Waste Management and Disposal | doi.org/10.13182/NT02-A3318
