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:
Evolution of Sodium Technology R&D Actions Supporting French Liquid-Metal Fast Breeder Reactors
G. Rodriguez, F. Baque, J. C. Astegiano
Nuclear Technology | Volume 150 | Number 1 | April 2005 | Pages 3-15
Technical Paper | Sodium Technology | doi.org/10.13182/NT05-A3601
Distinguished Achievements of a Quarter-Century Operation and a Promising Project Named MK-III in JOYO
Yukimoto Maeda, Takafumi Aoyama, Toshihiro Odo, Satoru Nakai, Soju Suzuki
Nuclear Technology | Volume 150 | Number 1 | April 2005 | Pages 16-36
Technical Paper | Sodium Technology | doi.org/10.13182/NT05-A3602
Lifetime Extension of the Phénix Plant
J. Guidez, P. Le Coz, L. Martin, P. Mariteau, R. Dupraz
Nuclear Technology | Volume 150 | Number 1 | April 2005 | Pages 37-43
Technical Paper | Sodium Technology | doi.org/10.13182/NT05-A3603
The Dounreay PFR Liquid-Metal Disposal Project
D. V. Sherwood, A. Comline, J. Small, J. Blyth
Nuclear Technology | Volume 150 | Number 1 | April 2005 | Pages 44-55
Technical Paper | Sodium Technology | doi.org/10.13182/NT05-A3604
Upgrade of Cooling System Heat Removal Capacity of the Experimental Fast Reactor JOYO
Kazunori Isozaki, Takashi Ashida, Kouzou Sumino, Satoru Nakai
Nuclear Technology | Volume 150 | Number 1 | April 2005 | Pages 56-66
Technical Paper | Sodium Technology | doi.org/10.13182/NT05-A3605
Review of In-Service Inspection and Repair Technique Developments for French Liquid Metal Fast Reactors
F. Baque
Nuclear Technology | Volume 150 | Number 1 | April 2005 | Pages 67-78
Technical Paper | Sodium Technology | doi.org/10.13182/NT05-A3606
Cleaning Cesium Radionuclides from BN-350 Primary Sodium
O. G. Romanenko, K. J. Allen, D. M. Wachs, H. P. Planchon, P. B. Wells, J. A. Michelbacher, P. Nazarenko, I. Dumchev, V. Maev, B. Zemtzev, L. Tikhomirov, V. Yakovlev, A. Synkov
Nuclear Technology | Volume 150 | Number 1 | April 2005 | Pages 79-99
Technical Paper | Sodium Technology | doi.org/10.13182/NT05-A3607
Recent Sodium Technology Development for the Decommissioning of the Rapsodie and Superphénix Reactors and the Management of Sodium Wastes
G. Rodriguez, O. Gastaldi, F. Baque
Nuclear Technology | Volume 150 | Number 1 | April 2005 | Pages 100-110
Technical Paper | Sodium Technology | doi.org/10.13182/NT05-A3608
A Reliable Steam Generator That Will Allow the Elimination of the Secondary Sodium Circuit in an LMFBR
D. V. Sherwood, Y. Chikazawa
Nuclear Technology | Volume 150 | Number 1 | April 2005 | Pages 111-119
Technical Paper | Sodium Technology | doi.org/10.13182/NT05-A3609
Nuclear Fuel Leasing, Recycling, and Proliferation: Modeling a Global View
Victor H. Reis, Matthew P. Crozat, Jor-Shan Choi, Robert Hill
Nuclear Technology | Volume 150 | Number 2 | May 2005 | Pages 121-131
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT05-A3610
Analysis of Fluid Flow and Solute Transport in a Fracture Intersecting a Canister with Variable Aperture Fractures and Arbitrary Intersection Angles
Longcheng Liu, Ivars Neretnieks
Nuclear Technology | Volume 150 | Number 2 | May 2005 | Pages 132-144
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT05-A3611
Comparison of Severe Accident Results Among SCDAP/RELAP5, MAAP, and MELCOR Codes
Te-Chuan Wang, Shih-Jen Wang, Jyh-Tong Teng
Nuclear Technology | Volume 150 | Number 2 | May 2005 | Pages 145-152
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT05-A3612
Pyroprocessing of Light Water Reactor Spent Fuels Based on an Electrochemical Reduction Technology
Hirokazu Ohta, Tadashi Inoue, Yoshiharu Sakamura, Kensuke Kinoshita
Nuclear Technology | Volume 150 | Number 2 | May 2005 | Pages 153-161
Technical Paper | Reprocessing | doi.org/10.13182/NT05-A3613
A Subcritical, Gas-Cooled Fast Transmutation Reactor with a Fusion Neutron Source
W. M. Stacey, V. L. Beavers, W. A. Casino, J. R. Cheatham, Z. W. Friis, R. D. Green, W. R. Hamilton, K. W. Haufler, J. D. Hutchinson, W. J. Lackey, R. A. Lorio, J. W. Maddox, J. Mandrekas, A. A. Manzoor, C. A. Noelke, C. de Oliveira, M. Park, D. W. Tedder, M. R. Terry, E. A. Hoffman
Nuclear Technology | Volume 150 | Number 2 | May 2005 | Pages 162-188
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT05-A3614
Incidence of High Nitrogen in Sintered Uranium Dioxide: A Case Study
Palanki Balakrishna, B. Narasimha Murty, M. Anuradha, R. B. Yadav, R. N. Jayaraj
Nuclear Technology | Volume 150 | Number 2 | May 2005 | Pages 189-195
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT05-A3615
Detection and Localization of Money Bills Concealed Behind Wooden Walls Using Compton Scattering
Jason A. Van Wart, Esam M. A. Hussein, Edward J. Waller
Nuclear Technology | Volume 150 | Number 2 | May 2005 | Pages 196-202
Technical Paper | Radioisotopes | doi.org/10.13182/NT05-A3616
Development of a Fissile Materials Irradiation Capability for Advanced Fuel Testing at the MIT Research Reactor
Lin-Wen Hu, John A. Bernard, Pavel Hejzlar, Gordon Kohse
Nuclear Technology | Volume 150 | Number 2 | May 2005 | Pages 203-208
Technical Note | Materials for Nuclear Systems | doi.org/10.13182/NT05-A3617
The Economics of Reprocessing Versus Direct Disposal of Spent Nuclear Fuel
Matthew Bunn, John P. Holdren, Steve Fetter, Bob Van Der Zwaan
Nuclear Technology | Volume 150 | Number 3 | June 2005 | Pages 209-230
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT05-A3618
Assessment of the RANS Turbulence Models for a Turbulent Flow and Heat Transfer in a Rod Bundle
Wang-Kee In, Tae-Hyun Chun
Nuclear Technology | Volume 150 | Number 3 | June 2005 | Pages 231-250
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT05-A3619
Investigation of Containment Flooding Strategy for Mark-III Nuclear Power Plant with MAAP4
Wei-Nian Su, Shih-Jen Wang, Show-Chyuan Chiang
Nuclear Technology | Volume 150 | Number 3 | June 2005 | Pages 251-262
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT05-A3620
Hydrogen Mitigation Strategy of the APR1400 Nuclear Power Plant for a Hypothetical Station Blackout Accident
Jongtae Kim, Seong-Wan Hong, Sang-Baik Kim, Hee-Dong Kim
Nuclear Technology | Volume 150 | Number 3 | June 2005 | Pages 263-282
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT05-A3621
Improvements in Predicting Void Fraction in Subcooled Boiling
Kwi Seok Ha, Yong Bum Lee, Hee Cheon No
Nuclear Technology | Volume 150 | Number 3 | June 2005 | Pages 283-292
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT05-A3622
Design of a Software Sensor for Feedwater Flow Measurement Using a Fuzzy Inference System
Man Gyun Na, Sun Ho Shin, Dong Won Jung
Nuclear Technology | Volume 150 | Number 3 | June 2005 | Pages 293-302
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT05-A3623
On the Radiolytic Decomposition of Colloidal Silver Iodide in Aqueous Suspension
Salih Güntay, Robin C. Cripps, Bernd Jäckel, Horst Bruchertseifer
Nuclear Technology | Volume 150 | Number 3 | June 2005 | Pages 303-314
Technical Paper | Radioisotopes | doi.org/10.13182/NT05-A3624
A Numerical Model Without Truncation Error for a Steady-State Analysis of a Once-Through Steam Generator
Yoon Sub Sim, Eui Kwang Kim, Jae Hyuk Eoh
Nuclear Technology | Volume 150 | Number 3 | June 2005 | Pages 315-324
Technical Note | Thermal Hydraulics | doi.org/10.13182/NT05-A3625
