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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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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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Latest News
Oklo completes end-to-end demonstration of advanced fuel recycling
Oklo Inc. has announced that it has completed the first end-to-end demonstration of its advanced fuel recycling process as part of an ongoing $5 million project in collaboration with Argonne and Idaho National Laboratories. Oklo’s goal: scaling up its fuel recycling capabilities to deploy a commercial-scale recycling facility that would increase advanced reactor fuel supplies and enhance fuel cost effectiveness for its planned sodium fast reactors.
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Next-Generation Power Reactor Information System
Emil E. Leitz
Nuclear Technology | Volume 91 | Number 1 | July 1990 | Pages 11-15
Technical Paper | Safety of Next Generation Power Reactor / Fission Reactor | doi.org/10.13182/NT90-A34437
Conceptual Design and Safety Characteristics of a Natural-Circulation Boiling Water reactor
Yoshiyuki Kataoka, Hiroaki Suzuki, Sigeo Hatamiya, Michio Murase, Isao Sumida, Tetsuo Horiuchi, Minoru Miki
Nuclear Technology | Volume 91 | Number 1 | July 1990 | Pages 16-27
Technical Paper | Safety of Next Generation Power Reactor / Fission Reactor | doi.org/10.13182/NT90-A34438
Conceptual Design of the Integrated Reactor with Inherent Safety
Yoshiro Asahi, Ichiro Sugawara, Toshiki Kobayashi
Nuclear Technology | Volume 91 | Number 1 | July 1990 | Pages 28-50
Technical Paper | Safety of Next Generation Power Reactor / Fission Reactor | doi.org/10.13182/NT90-A34439
Decay Heat Removal in the Sodium Advanced Fast Reactor with the MDSNP Code
T. C. Hung, V. K. Dhir
Nuclear Technology | Volume 91 | Number 1 | July 1990 | Pages 51-60
Technical Paper | Safety of Next Generation Power Reactor / Fission Reactor | doi.org/10.13182/NT90-A34440
Role of Feedback Reactivities in the Passive Safety of Nuclear Reactors: The Case of the Fast Flux Test Facility
Dong H. Nguyen
Nuclear Technology | Volume 91 | Number 1 | July 1990 | Pages 61-74
Technical Paper | Safety of Next Generation Power Reactor / Fission Reactor | doi.org/10.13182/NT90-A34441
Passive Containment Cooling for an Advanced Small Pressurized Water Reactor
Brett J. Menaker, Russell E. Allen, Harry E. Painter
Nuclear Technology | Volume 91 | Number 1 | July 1990 | Pages 75-80
Technical Paper | Safety of Next Generation Power Reactor / Nuclear Safety | doi.org/10.13182/NT90-A34442
The PIUS Pressurized Water Reactor: Aspects of Plant Operation and Availability
Kåre Hannerz, Lars Nilsson, Tor Pedersen, Christen Pind
Nuclear Technology | Volume 91 | Number 1 | July 1990 | Pages 81-88
Technical Paper | Safety of Next Generation Power Reactor / Nuclear Safety | doi.org/10.13182/NT90-A34443
Loss-of-Coolant Accident Aspects of the Combustion Engineering Advanced Light Water Reactor—System 80+
Stanley Rosen, Richard D. Ivany, John F. Kapinos, Suk K. Sim
Nuclear Technology | Volume 91 | Number 1 | July 1990 | Pages 89-94
Technical Paper | Safety of Next Generation Power Reactor / Nuclear Safety | doi.org/10.13182/NT90-A34444
Safety: Evolving Technologies for Tomorrow’s Power Reactors
Howard J. Bruschi, Ronald P. Vijuk
Nuclear Technology | Volume 91 | Number 1 | July 1990 | Pages 95-101
Technical Paper | Safety of Next Generation Power Reactor / Nuclear Safety | doi.org/10.13182/NT90-A34445
Probabilistic Analysis for Conceptual Design of the Babcock & Wilcox Advanced Light Water Reactor
Stanley H. Levinson, Robert S. Enzinna, B&W Nuclear Service Company, P.O. Box 10935, Lynchburg, Virginia 24506-0935
Nuclear Technology | Volume 91 | Number 1 | July 1990 | Pages 102-111
Technical Paper | Safety of Next Generation Power Reactor / Nuclear Safety | doi.org/10.13182/NT90-A34446
Probabilistic Risk Assessment Insights from New Westinghouse Pressurized Water Reactor Designs Studied in 1982–1987
Selim Sancaktar, T. van de Venne
Nuclear Technology | Volume 91 | Number 1 | July 1990 | Pages 112-117
Technical Paper | Safety of Next Generation Power Reactor / Nuclear Safety | doi.org/10.13182/NT90-A34447
Loss-of-Coolant Accident Performance of the Westinghouse 600-MW(electric) Advanced Pressurized Water Reactor
Robert M. Kemper, Christine M. Vertes
Nuclear Technology | Volume 91 | Number 1 | July 1990 | Pages 118-128
Technical Paper | Safety of Next Generation Power Reactor / Nuclear Safety | doi.org/10.13182/NT90-A34448
Nuclear Power — A Path to the Future
John J. Taylor, Karl E. Stahlkopf, Electric Power Research Institute, 3412 Hillview Avenue, P.O. Box 10412, Palo Alto, California 94303
Nuclear Technology | Volume 91 | Number 1 | July 1990 | Pages 129-132
Technical Paper | Safety of Next Generation Power Reactor / Economic | doi.org/10.13182/NT90-A34449
Reactivity Feedback Components of a Homogeneous U10Zr-Fueled 900-MW(thermal) Liquid-Metal Reactor
David Meneghetti, Dwight A. Kucera
Nuclear Technology | Volume 91 | Number 2 | August 1990 | Pages 139-145
Technical Paper | Safety of Next Generation Power Reactor / Fission Reactor | doi.org/10.13182/NT90-A34423
Failed Fuel Surveillance During in-Vessel Fuel Storage in Fast Breeder Reactors
Siegfried Jacobi
Nuclear Technology | Volume 91 | Number 2 | August 1990 | Pages 146-153
Technical Paper | Safety of Next Generation Power Reactor / Fission Reactor | doi.org/10.13182/NT90-A34424
Technology and Safety Aspects of the German High-Temperature Gas-Cooled Reactor
Wolfgang Kröger, Rudolf Schulten
Nuclear Technology | Volume 91 | Number 2 | August 1990 | Pages 154-164
Technical Paper | Safety of Next Generation Power Reactor / Fission Reactor | doi.org/10.13182/NT90-A34425
Analyses of Unscrammed Events Postulated for the Prism Design
Gregory J. Van Tuyle, Gregory C. Slovik, Robert J. Kennett, Bing C. Chan, Arnold L. Aronson
Nuclear Technology | Volume 91 | Number 2 | August 1990 | Pages 165-184
Technical Paper | Safety of Next Generation Power Reactor / Nuclear Saftey | doi.org/10.13182/NT90-A34426
Examining the Inherent Safety of Prism, Safr, and the Mhtgr
Gregory J. Van Tuyle, Peter Kroeger, Gregory C. Slovik, Bing C. Chan, Robert J. Kennett, Arnold L. Aronson
Nuclear Technology | Volume 91 | Number 2 | August 1990 | Pages 185-202
Technical Paper | Safety of Next Generation Power Reactor / Nuclear Saftey | doi.org/10.13182/NT90-A34427
Safety and Licensing of Safr-An Advanced Liquid-Metal Reactor
Robert T. Lancet, Robert Z. Litwin, Ravnesh C. Amar, Robert D. Rogers, Alan V. von Arx
Nuclear Technology | Volume 91 | Number 2 | August 1990 | Pages 203-214
Technical Paper | Safety of Next Generation Power Reactor / Nuclear Saftey | doi.org/10.13182/NT90-A34428
Probabilistic Evaluation of Successful Inherent Shutdown in Unprotected Accidents in Innovative Liquid-Metal Reactors
Charles J. Mueller, David C. Wade
Nuclear Technology | Volume 91 | Number 2 | August 1990 | Pages 215-225
Technical Paper | Safety of Next Generation Power Reactor / Nuclear Saftey | doi.org/10.13182/NT90-A34429
Risk Characterization of Safety Research Areas for Integral Fast Reactor Program Planning
Charles J. Mueller, James E. Cahalan, David J. Hill, John M. Kramer, John F. Marchaterre, Dean R. Pedersen, Roger W. Tilbrook, T. Y. C. Wei, Arthur E. Wright
Nuclear Technology | Volume 91 | Number 2 | August 1990 | Pages 226-234
Technical Paper | Safety of Next Generation Power Reactor / Nuclear Saftey | doi.org/10.13182/NT90-A34430
Passive Safety Characteristics of Fuel for a Modular High-Temperature Reactor and Fuel Performance Modeling Under Accident Conditions
Karl Verfondern, Werner Schenk, Heinz Nabielek
Nuclear Technology | Volume 91 | Number 2 | August 1990 | Pages 235-246
Technical Paper | Safety of Next Generation Power Reactor / Fuel Cycle | doi.org/10.13182/NT90-A34431
Modular High-Temperature Gas-Cooled Reactor Short-Term Thermal Response to Flow and Reactivity Transients
John Cleveland
Nuclear Technology | Volume 91 | Number 2 | August 1990 | Pages 247-258
Technical Paper | Safety of Next Generation Power Reactor / Heat Transfer and Fluid Flow | doi.org/10.13182/NT90-A34432
Liquid-Metal Reactor Applications of the Contain Code
Daniel E. Carroll, Kenneth D. Bergeron, Werner Scholtyssek, Greg D. Valdez, Richard Gido+
Nuclear Technology | Volume 91 | Number 2 | August 1990 | Pages 259-267
Technical Paper | Safety of Next Generation Power Reactor / Technique | doi.org/10.13182/NT90-A34433
Two-Dimensional Thermal-Hydraulic Calculations for the Mol 7C Experiments with the Computer Code BACCHUS
Christoph Homann, Maurizio Bottoni, Burkhardt Dorr, Dankward Struwe
Nuclear Technology | Volume 91 | Number 3 | September 1990 | Pages 275-286
Technical Paper | Fission Reactor | doi.org/10.13182/NT90-A34452
A Study on Hydrogen Generation, Burning, and Their Impact on Fission Product Release Under a Postulated Large-Break LOCA
Tien-Ko Wang, Jun Hsin, Min Lee
Nuclear Technology | Volume 91 | Number 3 | September 1990 | Pages 287-296
Technical Paper | Nuclear Safety | doi.org/10.13182/NT90-A34453
A Best-Estimate Paradigm for Diagnosis of Multiple Failure Transients in Nuclear Power Plants Using Artificial Intelligence
Robert P. Martin, Bahram Nassersharif
Nuclear Technology | Volume 91 | Number 3 | September 1990 | Pages 297-310
Technical Paper | Nuclear Safety | doi.org/10.13182/NT90-A34454
Evaluation of Depletion and Production of Uranium, Plutonium, Transplutonium Nuclides, and Fission Products in JPDR-1 Fuel
Hideo Ezure
Nuclear Technology | Volume 91 | Number 3 | September 1990 | Pages 311-344
Technical Paper | Fuel Cycle | doi.org/10.13182/NT90-A34455
Étoile: A Three-Dimensional Finite Element Code for LMFBR Fuel Bundle Analysis
Masatoshi Nakagawa, Yasusi Tsuboi
Nuclear Technology | Volume 91 | Number 3 | September 1990 | Pages 345-360
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT90-A34456
Material Characterization and Flaw Detection, Sizing, and Location by the Differential Gamma Scattering Spectroscopy Technique. Part I: Development of Theoretical Basis
Samim Anghaie, Larry L. Humphries, Nils J. Diaz
Nuclear Technology | Volume 91 | Number 3 | September 1990 | Pages 361-375
Technical Paper | Material | doi.org/10.13182/NT90-A34457
Material Characterization and Flaw Detection, Sizing, and Location by the Differential Gamma Scattering Spectroscopy Technique. Part II: Experiment
Nuclear Technology | Volume 91 | Number 3 | September 1990 | Pages 376-387
Technical Paper | Material | doi.org/10.13182/NT90-A34458
Oxidation Behavior of Carbide Fuels
V. S. Iyer, S. K. Mukerjee, R. V. Kamat, K. T. Pillai, N. Kumar, V. N. Vaidya, D. D. Sood
Nuclear Technology | Volume 91 | Number 3 | September 1990 | Pages 388-393
Technical Paper | Material | doi.org/10.13182/NT90-A34459
Effect of Antioxidants on Radiation Stability of Polymers Used for Electric Cable Insulation
Jeffrey W. Ray, Albert B. Reynolds
Nuclear Technology | Volume 91 | Number 3 | September 1990 | Pages 394-403
Technical Paper | Material | doi.org/10.13182/NT90-A34460
A Neutronic Study of an Accelerator-Based Neutron Irradiation Facility for the Treatment of Superficial Melanoma by Boron Neutron Capture Therapy
T. X. Bruce Qu, Thomas E. Blue, C. K. Chris Wang, Reinhard A. Gahbauer
Nuclear Technology | Volume 91 | Number 3 | September 1990 | Pages 404-412
Technical Paper | Radioisotopes and Isotope Separation | doi.org/10.13182/NT90-A34461
Fuel Burnup Determination Based on the Measurement of a Short-Lived Fission Product
Tien-Ko Wang, Liang-Chen Shiao, Chia-Lian Tseng
Nuclear Technology | Volume 91 | Number 3 | September 1990 | Pages 413-418
Technical Paper | Technique | doi.org/10.13182/NT90-A34462
