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Nuclear Nonproliferation Policy
The mission of the Nuclear Nonproliferation Policy Division (NNPD) is to promote the peaceful use of nuclear technology while simultaneously preventing the diversion and misuse of nuclear material and technology through appropriate safeguards and security, and promotion of nuclear nonproliferation policies. To achieve this mission, the objectives of the NNPD are to: Promote policy that discourages the proliferation of nuclear technology and material to inappropriate entities. Provide information to ANS members, the technical community at large, opinion leaders, and decision makers to improve their understanding of nuclear nonproliferation issues. Become a recognized technical resource on nuclear nonproliferation, safeguards, and security issues. Serve as the integration and coordination body for nuclear nonproliferation activities for the ANS. Work cooperatively with other ANS divisions to achieve these objective nonproliferation policies.
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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!
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Nuclear Science and Engineering
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Nuclear Technology
Fusion Science and Technology
February 2025
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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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First In-Pile Experimental Results of High-Plutonium-Content Oxide Fuel for Plutonium Burning in Fast Reactors
Emmanuelle Picard, Jean Noirot, Raymond L. Moss, Helmut Plitz, Karl Richter, Jacques Rouault
Nuclear Technology | Volume 129 | Number 1 | January 2000 | Pages 1-12
Technical Paper | Fission Reactors | doi.org/10.13182/NT00-2
Code Development and Assessment for Reactor Outage Thermal-Hydraulic and Safety Analysis - Midloop Operation with Loss of Residual Heat Removal
Thomas K. S. Liang, Fu-Kuang Ko
Nuclear Technology | Volume 129 | Number 1 | January 2000 | Pages 13-25
Technical Paper | Reactor Safety | doi.org/10.13182/NT00-A3042
A Nodal Kinetics and Thermohydraulics Analysis (NOKTA) Code for Analyzing Rod-Ejection Accidents and Other Transients in Nuclear Power Reactor Cores
Sadi Kaya, Hasbi Yavuz
Nuclear Technology | Volume 129 | Number 1 | January 2000 | Pages 26-35
Technical Paper | Reactor Safety | doi.org/10.13182/NT00-A3043
An Evaluation of Emergency Operator Actions by an Experimental SGTR Event at the IIST Facility and a Comparison of Mihama-2 SGTR Event Record
Tay-Jian Liu, Chien-Hsiung Lee, Ching-Chuan Yao, Show-Chyuan Chiang
Nuclear Technology | Volume 129 | Number 1 | January 2000 | Pages 36-50
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT00-A3044
Full-Load-Rejection Design Analysis for the Lungmen Advanced Boiling Water Reactor Using RETRAN
Jan-Ru Tang, Lainsu Kao, Jong-Rong Wang, Ruey-Yng Yuann
Nuclear Technology | Volume 129 | Number 1 | January 2000 | Pages 51-68
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT00-A3045
Suppression of Vapor Explosions in a Water-Molten-Tin System by Augmentation of the Void Fraction
Michael K. Meeks, Michael C. Baker, Riccardo Bonazza
Nuclear Technology | Volume 129 | Number 1 | January 2000 | Pages 69-81
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT00-A3046
Simulation of Two Loss-of-Flow Transients in a VVER-1000 Nuclear Power Plant with RELAP5/MOD3.2 System Code
Yassin A. Hassan, Dionisie R. Moscalu
Nuclear Technology | Volume 129 | Number 1 | January 2000 | Pages 82-92
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT00-A3047
Nonphosphate Degradation Products of Tributyl Phosphate and Their Reactivities in Purex Media Under Extreme Conditions
Yoshikazu Tashiro, Ryuji Kodama, Hiroshi Sugai, Katsuhiko Suzuki, Shingo Matsuoka
Nuclear Technology | Volume 129 | Number 1 | January 2000 | Pages 93-100
Technical Paper | Reprocessing | doi.org/10.13182/NT00-A3048
Long-Term Leaching Experiments of Full-Scale Cemented Waste Forms: Experiments and Modeling
Bernhard Kienzler, Peter Vejmelka, Horst-Jürgen Herbert, Herbert Meyer, Corinna Altenhein-Haese
Nuclear Technology | Volume 129 | Number 1 | January 2000 | Pages 101-118
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT00-A3049
Radiation Chemical Effects in the Near Field of a Final Disposal Site - I: Radiolytic Products Formed in Concentrated NaCl Solutions
M. Kelm, E. Bohnert
Nuclear Technology | Volume 129 | Number 1 | January 2000 | Pages 119-122
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT00-A3050
Radiation Chemical Effects in the Near Field of a Final Disposal Site - II: Simulation of the Radiolytic Processes in Concentrated NaCl Solutions
Nuclear Technology | Volume 129 | Number 1 | January 2000 | Pages 123-130
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT00-A3051
The Self-Ignition Temperatures of Bitumen Mixtures Containing Transition Metal Nitrates
Ken Okada, Masao Nomura, Yasuhiko Fujii
Nuclear Technology | Volume 129 | Number 1 | January 2000 | Pages 131-139
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT00-A3052
Boiling Water Reactor Fuel Behavior Under Reactivity-Initiated-Accident Conditions at Burnup of 41 to 45 GWd/tonne U
Takehiko Nakamura, Makio Yoshinaga, Masato Takahashi, Kazunari Okonogi, Kiyomi Ishijima
Nuclear Technology | Volume 129 | Number 2 | February 2000 | Pages 141-151
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT00-A3053
Process Modeling of Plutonium Conversion and Mixed-Oxide Fuel Fabrication for Plutonium Disposition
Kenneth L. Schwartz, Carl A. Beard
Nuclear Technology | Volume 129 | Number 2 | February 2000 | Pages 152-174
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT00-A3054
A Personal Computer-Based Simulator for Nuclear-Heating Reactors
Jie Liu, Zuoyi Zhang, Dongsen Lu, Zhengang Shi, Xiaoming Chen, Yujie Dong
Nuclear Technology | Volume 129 | Number 2 | February 2000 | Pages 175-186
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT00-A3055
Experimental Investigation of Early Initiation of Primary Cooldown by Secondary-Side Depressurization in a PWR Inadequate Core-Cooling Accident
Tay-Jian Liu, Yea-Kuang Chan, Yuh-Ming Ferng, Chien-Yeh Chang
Nuclear Technology | Volume 129 | Number 2 | February 2000 | Pages 187-200
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT00-A3056
Validation of the VITAMIN-B6 and BUGLE-96 Cross-Section Libraries for Moderate-Energy Neutron and Photon Transport Calculations
Charles O. Slater, Hamilton T. Hunter
Nuclear Technology | Volume 129 | Number 2 | February 2000 | Pages 201-217
Technical Paper | Radiation Protection | doi.org/10.13182/NT00-A3057
Formulas to Correct Excess Pressure and Pressure Shift to be Used in Volume Measurement for Plutonium Nitrate Solution
Takashi Hosoma, Masanori Aritomi, Tsunemichi Kawa
Nuclear Technology | Volume 129 | Number 2 | February 2000 | Pages 218-235
Technical Paper | Reprocessing | doi.org/10.13182/NT00-A3058
Effect of Solution Concentration on the Properties of a Cementitious Grout Wasteform for Low-Level Nuclear Waste
Amnon Katz, Adrian R. Brough, R. James Kirkpatrick, Leslie J. Struble, J. Francis Young
Nuclear Technology | Volume 129 | Number 2 | February 2000 | Pages 236-245
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT00-A3059
Vitrification of Polyvinyl Chloride Waste from Korean Nuclear Power Plants
Jiawei Sheng, Kwansik Choi, Kyung-Hwa Yang, Myung-Chan Lee, Myung-Jae Song
Nuclear Technology | Volume 129 | Number 2 | February 2000 | Pages 246-256
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT00-A3060
Neutron Beam Optimization for Boron Neutron Capture Therapy Using the D-D and D-T High-Energy Neutron Sources
Jérôme M. Verbeke, Jasmina L. Vujic, Ka-Ngo Leung
Nuclear Technology | Volume 129 | Number 2 | February 2000 | Pages 257-278
Technical Paper | Radiation Biology and Medicine | doi.org/10.13182/NT00-A3061
Salt Effect Model for Aqueous Solubility of TBP in a 5 to 100% TBP/n-Dodecane-Nitric Acid-Water Biphasic System at 298.2 K
Shekhar Kumar, Sudhir Babu Koganti
Nuclear Technology | Volume 129 | Number 2 | February 2000 | Pages 279-283
Technical Note | Reprocessing | doi.org/10.13182/NT00-A3062
Neutron Fluence, Dosimetry and Damage Response Determination in In-Core/Ex-Core Components of the VENUS CEN/SCK LWR Using 3-D Monte Carlo Simulations: NEA's VENUS-3 Benchmark
J. Manuel Perlado, Jaime Marian, Jesús García Sanz
Nuclear Technology | Volume 129 | Number 3 | March 2000 | Pages 285-296
Technical Paper | Fission Reactors | doi.org/10.13182/NT00-A3063
The Chemistry of Iodine in Containment
Jungsook Clara Wren, Joanne M. Ball, Glenn A. Glowa
Nuclear Technology | Volume 129 | Number 3 | March 2000 | Pages 297-325
Technical Paper | Reactor Safety | doi.org/10.13182/NT129-297
Depletion Analysis of Mixed-Oxide Fuel Pins in Light Water Reactors and the Advanced Test Reactor
Gray S. Chang, John M. Ryskamp
Nuclear Technology | Volume 129 | Number 3 | March 2000 | Pages 326-337
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT00-A3065
Numerical Simulation of Accumulated Steam Generator Tube Sheet Damage and Loose Part Impact Distributions
Liang Shi, J. Michael Doster, Charles W. Mayo
Nuclear Technology | Volume 129 | Number 3 | March 2000 | Pages 338-355
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT00-A3066
Testing a Passive Autocatalytic Recombiner in the Surtsey Facility
Thomas K. Blanchat, Asimios C. Malliakos
Nuclear Technology | Volume 129 | Number 3 | March 2000 | Pages 356-373
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT00-A3067
Development of the INSPECT Model for the Prediction of Iodine Volatility from Irradiated Solutions
Shirley Dickinson, Howard E. Sims
Nuclear Technology | Volume 129 | Number 3 | March 2000 | Pages 374-386
Technical Paper | Reactor Operations and Control | doi.org/10.13182/NT00-A3068
Measurements of the Radiolytic Oxidation of Aqueous CsI Using a Sparging Apparatus
C. B. Ashmore, D. Brown, S. Dickinson, H. E. Sims
Nuclear Technology | Volume 129 | Number 3 | March 2000 | Pages 387-397
Technical Paper | Reactor Operations and Control | doi.org/10.13182/NT00-A3069
Estimating the Impurity Concentration Factor on the Boiling Heat Transfer Surface of a Simulated Steam-Generator Tube-Support-Plate Crevice Using an In Situ High-Temperature Conductivity Measurement Technique
Hirotaka Kawamura, Hideo Hirano
Nuclear Technology | Volume 129 | Number 3 | March 2000 | Pages 398-406
Technical Paper | Reactor Operations and Control | doi.org/10.13182/NT00-A3070
A Novel Method for Energy Production Using 242mAm as a Nuclear Fuel
Yigal Ronen, Menashe Aboudy, Dror Regev
Nuclear Technology | Volume 129 | Number 3 | March 2000 | Pages 407-417
Technical Note | Fission Reactors | doi.org/10.13182/NT00-A3071
