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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.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
Article considers incorporation of AI into nuclear power plant operations
The potential application of artificial intelligence to the operation of nuclear power plants is explored in an article published in late December in the Washington Examiner. The article, written by energy and environment reporter Callie Patteson, presents the views of a number of experts, including Yavuz Arik, a strategic energy consultant.
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The Characteristics of the RBMK Core
Anna A. Afanasieva, Evgeniy V. Burlakov, Alexander V. Krayushkin, Andre V. Kubarev
Nuclear Technology | Volume 103 | Number 1 | July 1993 | Pages 1-9
Technical Paper | Fission Reactor | doi.org/10.13182/NT93-A34825
Vessel Fluence Assessment with the EFLUVE Code and a Low-Fluence Fuel Management Scheme
François-David Rosset, Henri Schaeffer
Nuclear Technology | Volume 103 | Number 1 | July 1993 | Pages 10-18
Technical Paper | Fission Reactor | doi.org/10.13182/NT93-A34826
Transient Thermal Analysis of a Space Reactor Power System
Michael J. Gaeta, Frederick R. Best
Nuclear Technology | Volume 103 | Number 1 | July 1993 | Pages 19-33
Technical Paper | Fission Reactor | doi.org/10.13182/NT93-A34827
Time Domain Model Sensitivity in Boiling Water Reactor Stability Analysis Using TRAC/BF1
Jeffrey A. Borkowski, Gordon E. Robinson, Anthony J. Baratta, Matthew Kattic
Nuclear Technology | Volume 103 | Number 1 | July 1993 | Pages 34-48
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT93-A34828
Best-Estimate Methodology for Analysis of Anticipated Transients Without Scram in Pressurized Water Reactors
Luis Rebollo
Nuclear Technology | Volume 103 | Number 1 | July 1993 | Pages 49-65
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT93-A34829
Fission Product Transport and Behavior During Two Postulated Loss-of-Flow Transients in the Advanced Test Reactor
James P. Adams, Michael L. Carboneau, Donald L. Hagrman
Nuclear Technology | Volume 103 | Number 1 | July 1993 | Pages 66-78
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT93-A34830
Reactor Dynamics and Stability Analysis of a Burst-Mode Gas Core Reactor, Brayton Cycle Space Power System
Edward T. Dugan, Kiratadas Kutikkad
Nuclear Technology | Volume 103 | Number 1 | July 1993 | Pages 79-92
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT93-A34831
Separation and Concentration of Hydrogen Isotopes by a Palladium Alloy Membrane
Yasuo Suzuki, Shoji Kimura
Nuclear Technology | Volume 103 | Number 1 | July 1993 | Pages 93-100
Technical Paper | Enrichment and Reprocessing System | doi.org/10.13182/NT93-A34832
Corrosion Product Particles in Boiling Water Reactor Condensates
Hans-Peter Hermansson, Göran Persson, Anneli Reinvall
Nuclear Technology | Volume 103 | Number 1 | July 1993 | Pages 101-113
Technical Paper | Reactor Operation | doi.org/10.13182/NT93-A34833
Generation of Spatial Weighting Functions for Ex-Core Detectors by Adjoint Transport Calculation
Joon Gi Ahn, Nam Zin Cho, Jung Eui Kuh
Nuclear Technology | Volume 103 | Number 1 | July 1993 | Pages 114-121
Technical Note | Fission Reactor | doi.org/10.13182/NT93-A34834
A Realistic Anticipated Transient Without Scram Evaluation of the Zorita Nuclear Power Plant
Nuclear Technology | Volume 103 | Number 1 | July 1993 | Pages 122-130
Technical Note | Nuclear Reactor Safety | doi.org/10.13182/NT93-A34835
Analysis of a Turbine Trip Transient with the Chinshan Plant Analyzer
Shih-Jen Wang, Chun-Sheng Chien, Jung-Yuh Jang
Nuclear Technology | Volume 103 | Number 1 | July 1993 | Pages 131-137
Technical Note | Reactor Operation | doi.org/10.13182/NT93-A34836
Static and Dynamic Neutronic Analysis of a Burst-Mode, Multiple-Cavity Gas Core Reactor, Rankine Cycle Space Power System
Edward T. Dugan, Samer D. Kahook
Nuclear Technology | Volume 103 | Number 2 | August 1993 | Pages 139-156
Technical Paper | Fission Reactor | doi.org/10.13182/NT93-A34839
An Efficient Nodal Method for Transient Calculations in Light Water Reactors
Jae-Woong Song, Jong-Kyung Kim
Nuclear Technology | Volume 103 | Number 2 | August 1993 | Pages 157-167
Technical Paper | Fission Reactor | doi.org/10.13182/NT93-A34840
The Case for Endurance Testing of Sodium-Heated Steam Generators
A. T. Onesto, H. R. Zweig, D. C. Gibbs, R. D. Carlson, E. Rodwell, C. R. Kakarala
Nuclear Technology | Volume 103 | Number 2 | August 1993 | Pages 168-186
Technical Paper | Fission Reactor | doi.org/10.13182/NT93-A34841
Preliminary Neutronics Calculations for Conversion of the Tehran Research Reactor Core from Heu to Leu Fuel
Seyed Mohammad R. Nejat
Nuclear Technology | Volume 103 | Number 2 | August 1993 | Pages 187-198
Technical Paper | Fission Reactor | doi.org/10.13182/NT93-A34842
Effect of System Pressure on Reactor Power Limits Criteria
Kuo-Fu Chen
Nuclear Technology | Volume 103 | Number 2 | August 1993 | Pages 199-205
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT93-A34843
Modeling Condensation Steam Quenching Effects in an MSIV Closure Transient Using RETRAN-02-MOD002 With and Without Nonequilibrium Pressurizer Model Option and TRAC-BF1
B.D. Boyer, J. W. Hartzell,† S. Lider, G. E. Robinson, A. J. Baratta, A. J. Roscioli
Nuclear Technology | Volume 103 | Number 2 | August 1993 | Pages 206-219
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT93-A34844
Fuel Performance and Fission Product Release Studies for Defected Fuel Elements
Brent J. Lewis, Roderick D. MacDonald, Nicholas V. Ivanoff, Fernando C. Iglesias
Nuclear Technology | Volume 103 | Number 2 | August 1993 | Pages 220-245
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT93-A34845
Radiological Safety Experience in the Fabrication of Alloy Plate Fuels Bearing 233U/Pu
A. M. Bhagwat, K. V. Kamath, K. N. Kutty, G. R. Naik, K. K. Narayan, P. R. Pillai, G. J. Prasad, C. Ganguly
Nuclear Technology | Volume 103 | Number 2 | August 1993 | Pages 246-256
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT93-A34846
Estimation of Hydrogen Peroxide Decomposition Rates in the Boiling Water Reactor Primary Coolant Circuit
Chien C. Lin
Nuclear Technology | Volume 103 | Number 2 | August 1993 | Pages 257-261
Technical Paper | Material | doi.org/10.13182/NT93-A34847
Evaluation of an Exponential Model for Germanium Detector Efficiencies
Willard G. Winn
Nuclear Technology | Volume 103 | Number 2 | August 1993 | Pages 262-273
Technical Paper | Radiation Application | doi.org/10.13182/NT93-A34848
Optimization of Monte Carlo Calculations for Photon Sources from Actinides
L. L. Carter
Nuclear Technology | Volume 103 | Number 2 | August 1993 | Pages 274-287
Technical Paper | Radiation Protection | doi.org/10.13182/NT93-A34849
The Influence of Optimum Power Level Change on Boration and Dilution Operations
Aquilino Senra Martinez, Eugenio De Andrade Oliveira
Nuclear Technology | Volume 103 | Number 2 | August 1993 | Pages 288-293
Technical Note | Reactor Operation | doi.org/10.13182/NT93-A34850
Concept and Design of a Supercritical-Pressure, Direct-Cycle Light Water Reactor
Yoshiaki Oka, Sei-Ichi Koshizuka
Nuclear Technology | Volume 103 | Number 3 | September 1993 | Pages 295-302
Technical Paper | Fission Reactor | doi.org/10.13182/NT93-A34852
On Chaotic Dynamics in Nuclear Engineering Systems
Dan Gabriel Cacuci
Nuclear Technology | Volume 103 | Number 3 | September 1993 | Pages 303-309
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT93-A34853
Simulation of Loss of RHR During Midloop Operations and the Role of Steam Generators in Decay Heat Removal Using the RELAP5/MOD3 Code
Yassin A. Hassan, Laxminarayan L. Raja
Nuclear Technology | Volume 103 | Number 3 | September 1993 | Pages 310-319
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT93-A34854
Gadolinium Neutron Capture Therapy
George A. Miller, Jr., Nolan E. Hertel, Bernard W. Wehring, John L. Horton
Nuclear Technology | Volume 103 | Number 3 | September 1993 | Pages 320-331
Technical Paper | Radiation Biology and Medicine | doi.org/10.13182/NT93-A34855
A Theoretical Critical Heat Flux Model for Low-Pressure, Low-Mass-Flux, and Low-Steam-Quality Conditions
Wei-Hsiao Ho, Kuan-Chywan Tu, Bau-Shei Pei, Chin-Jang Chang
Nuclear Technology | Volume 103 | Number 3 | September 1993 | Pages 332-345
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT93-A34856
Subcriticality of Two Uranyl Nitrate Flat Cylindrical Tanks Spaced in Air by 252Cf-Source-Driven Noise Analysis
J. T. Mihalczo, E. D. Blakeman, V. K. Paré, T. E. Valentine, D. J. Auslander
Nuclear Technology | Volume 103 | Number 3 | September 1993 | Pages 346-379
Technical Paper | Nuclear Criticality Safety | doi.org/10.13182/NT93-3
A Geometric Buckling Expression for Regular Polygons: I. Measurements in Low-Enriched UO2-H2O Lattices
Yoshinori Miyoshi, Masafumi Itagaki, Masanori Akai, Hideyuki Hirose, Masao Hashimoto
Nuclear Technology | Volume 103 | Number 3 | September 1993 | Pages 380-391
Technical Paper | Nuclear Criticality Safety | doi.org/10.13182/NT93-A34858
A Geometric Buckling Expression for Regular Polygons: II. Analyses Based on the Multiple Reciprocity Boundary Element Method
Masafumi Itagaki, Yoshinori Miyoshi, Hideyuki Hirose
Nuclear Technology | Volume 103 | Number 3 | September 1993 | Pages 392-402
Technical Paper | Nuclear Criticality Safety | doi.org/10.13182/NT93-A34859
Optimizing Feedwater Control System Performance with the Chinshan Plant Analyzer
Shih-Jen Wang, Chun-Sheng Chien
Nuclear Technology | Volume 103 | Number 3 | September 1993 | Pages 403-409
Technical Paper | Reactor Operation | doi.org/10.13182/NT93-A34860
The Dynamics of a Turbine-Driven Reactor Feedwater Pump and Identification of Related Parameters in the Kuosheng Power Station
Shih-Jen Wang, Chun-Sheng Chien, Suh-Chyn Jeng
Nuclear Technology | Volume 103 | Number 3 | September 1993 | Pages 410-416
Technical Paper | Reactor Operation | doi.org/10.13182/NT93-A34861
A Hybrid Sn-Diffusion Theory Computational Scheme for Efficient Neutronic Calculations of Externally Moderated Gas Core Reactors
Edward T. Dugan, Mohammed K. Alfakhar
Nuclear Technology | Volume 103 | Number 3 | September 1993 | Pages 417-425
Technical Note | Fission Reactor | doi.org/10.13182/NT93-A34862
Potential Application of Zircaloy Chemical Embrittlement to Volume Reduction of Spent-Fuel Cladding
Masafumi Nakatsuka
Nuclear Technology | Volume 103 | Number 3 | September 1993 | Pages 426-433
Technical Note | Nuclear Fuel Cycle | doi.org/10.13182/NT93-A34863
