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 Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
Meeting Spotlight
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!
Latest Magazine Issues
Jul 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
August 2024
Nuclear Technology
Fusion Science and Technology
Latest News
Four million nuclear jobs by 2050: Who will do them?
Industry leaders from around the globe met this month to discuss the talent development that will be necessary for the long-term success of the nuclear industry.
The International Conference on Nuclear Knowledge Management and Human Resources Development, hosted by the International Atomic Energy Agency, was held in Vienna earlier this month. Discussed there was the agency’s forecast for nuclear capacity to more than double—or hopefully triple—by 2050 and the requirement of more than four million professionals to support the industry.
Jump to:
Effect of Pressurizer Sizing on the Turbine Trip Transient
Douglas A. Brownson, Anthony J. Baratta, Gordon E. Robinson
Nuclear Technology | Volume 75 | Number 1 | October 1986 | Pages 7-14
Technical Paper | Fission Reactor | doi.org/10.13182/NT86-A15972
A Reduced-Order Model of Boiling Water Reactor Linear Dynamics
José March-Leuba
Nuclear Technology | Volume 75 | Number 1 | October 1986 | Pages 15-22
Technical Paper | Fission Reactor | doi.org/10.13182/NT86-A15973
The Influence of Noise on Edge Determination in Radiography
Yossi Bushlin, Dov Ingman, Y. Segal
Nuclear Technology | Volume 75 | Number 1 | October 1986 | Pages 23-33
Technical Paper | Fission Reactor | doi.org/10.13182/NT86-A15974
Subchannel Void Fraction Prediction via Drift-Flux Analysis
Hasna J. Khan, George Kosaly
Nuclear Technology | Volume 75 | Number 1 | October 1986 | Pages 34-45
Technical Paper | Fission Reactor | doi.org/10.13182/NT86-A15975
ARKAS: A Three-Dimensional Finite Element Program for the Core-Wide Mechanical Analysis of Liquid-Metal Fast Breeder Reactor Cores
Masatoshi Nakagawa
Nuclear Technology | Volume 75 | Number 1 | October 1986 | Pages 46-65
Technical Paper | Fission Reactor | doi.org/10.13182/NT86-A15976
A Long-Term Perspective on the Light Water Reactor Fuel Cycle
M. A. Malik
Nuclear Technology | Volume 75 | Number 1 | October 1986 | Pages 66-72
Technical Paper | Fuel Cycle | doi.org/10.13182/NT86-A15977
The Assay of Uranium and Plutonium in Reprocessing Input Solutions by Isotope Dilution Mass Spectrometry: Results of the Isotope Dilution Analysis Measurement Evaluation Programs
Wolfgang Beyrich, Werner Golly, Gert Spannagel, Paul De Bièvre, Werner H. Wolters, Willy Lycke
Nuclear Technology | Volume 75 | Number 1 | October 1986 | Pages 73-81
Technical Paper | Chemical Processing | doi.org/10.13182/NT86-A15978
Behavior of Breached Pressurized Water Reactor Spent-Fuel Rods in an Air Atmosphere Between 250 and 360°C
Robert E. Einziger, Robert V. Strain
Nuclear Technology | Volume 75 | Number 1 | October 1986 | Pages 82-95
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT86-A15979
A Study of Mineral Zeolite as a Nitrogen Oxides Adsorbent for Dissolver Off-Gas Treatment
Hiromichi Fumoto, Shigekazu Sato, Wataru Ito, Takaaki Tamura, Nobuya Yoshiki, Yasutoshi Kobayashi
Nuclear Technology | Volume 75 | Number 1 | October 1986 | Pages 96-108
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT86-A15980
A Driving Device for Activated Wire for Reactor Flux Mapping
Cheng-Hsin Mao, Pao-Shan Weng
Nuclear Technology | Volume 75 | Number 1 | October 1986 | Pages 109-112
Technical Note | Fission Reactor | doi.org/10.13182/NT86-A15981
Sensitivity of Pressurized Water Reactor Source Term Inventory and Decay Power to Core Management Parameters
John K. Wheeler, Alexander Sesonske
Nuclear Technology | Volume 75 | Number 1 | October 1986 | Pages 113-115
Technical Note | Nuclear Safety | doi.org/10.13182/NT86-A15982
The Effect of Boron and Gadolinium Burnable Poisons on the Hot-to-Cold Reactivity Swing of a Pressurized Water Reactor Assembly
Alex Galperin, Meir Segev, Alvin Radkowsky
Nuclear Technology | Volume 75 | Number 2 | November 1986 | Pages 123-126
Technical Paper | Fission Reactor | doi.org/10.13182/NT86-A33854
Substitution of the Soluble Boron Reactivity Control System of a Pressurized Water Reactor by Gadolinium Burnable Poisons
Nuclear Technology | Volume 75 | Number 2 | November 1986 | Pages 127-133
Technical Paper | Fission Reactor | doi.org/10.13182/NT86-A33855
Evaluations and Modifications of the EPRI-1 Correlation on PWR Critical Heat Flux Predictions Under Normal and Abnormal Fuel Conditions
B. S. Pei, Y. B. Chen, Chunkuan Shih, W. S. Lin
Nuclear Technology | Volume 75 | Number 2 | November 1986 | Pages 134-147
Technical Paper | Fission Reactor | doi.org/10.13182/NT86-A33856
Simultaneous Evaluation of the Effects of 232U and 236U on Uranium Recycling in Boiling Water Reactors
Kazuki Hida, Sadao Kusuno, Takeshi Seino
Nuclear Technology | Volume 75 | Number 2 | November 1986 | Pages 148-159
Technical Paper | Fuel Cycle | doi.org/10.13182/NT86-A33857
PUMA — A New Mathematical Model for the Rapid Calculation of Steady- State Concentration Profiles in Mixer-Settler Extraction, Partitioning, and Stripping Contactors Using the Purex Process
John F. Geldard, Adolph L. Beyerlein, Houn-Lin Chiu
Nuclear Technology | Volume 75 | Number 2 | November 1986 | Pages 160-167
Technical Paper | Chemical Processing | doi.org/10.13182/NT86-A33858
Waste Package Component Interactions with Savannah River Defense Waste Glass in a Low-Magnesium Salt Brine
B. P. McGrail
Nuclear Technology | Volume 75 | Number 2 | November 1986 | Pages 168-186
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT86-A33859
Decomposition of Ion Exchange Resins by Pyrolysis
Masami Matsuda, Kiyomi Funabashi, Takashi Nishi, Hideo Yusa, Makoto Kikuchi
Nuclear Technology | Volume 75 | Number 2 | November 1986 | Pages 187-192
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT86-A33860
On the Dynamics of Fuel Vapor Pressure Buildup in Voided Liquid-Metal Fast Breeder Reactor Cores During Transient Heating
P. Bhaskar Rao, Om Pal Singh
Nuclear Technology | Volume 75 | Number 2 | November 1986 | Pages 193-195
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT86-A33861
A Radiation Heat Transfer Model for the SCDAP Code
Manohar S. Sohal
Nuclear Technology | Volume 75 | Number 2 | November 1986 | Pages 196-204
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT86-A33862
Three-Dimensional Two-Fluid Code for U-Tube Steam Generator Thermal Design Analysis
Jae Young Lee, Hee Cheon No
Nuclear Technology | Volume 75 | Number 2 | November 1986 | Pages 205-214
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT86-A33863
Characteristics of a Foil-Type Electret Dosimeter for a Surface Alpha Contamination Monitor
Tatsuhiko Uda, Hisao Otsuka, Yoshihiro Ozawa
Nuclear Technology | Volume 75 | Number 2 | November 1986 | Pages 215-221
Technical Paper | Technique | doi.org/10.13182/NT86-A33864
Comparative Study on the Hydrocyclone and the Centrifuge as Emulsion Separators in the HNO3-H2O-TBP-Mepasine System
Romuald Sulima*
Nuclear Technology | Volume 75 | Number 2 | November 1986 | Pages 222-224
Technical Note | Chemical Processing | doi.org/10.13182/NT86-A33865
Basis for Extending Limits in ANSI Standard for Mixed Oxides to Heterogeneous Systems
Eugene D. Clayton, Hugh K. Clark, Gordon Walker, Richard A. Libby
Nuclear Technology | Volume 75 | Number 2 | November 1986 | Pages 225-229
Technical Note | Criticality Safety | doi.org/10.13182/NT86-A33866
CANDU-600 Heat Transport System Flow Stability
William J. Garland, Simon H. Pang
Nuclear Technology | Volume 75 | Number 3 | December 1986 | Pages 239-260
Technical Paper | Fission Reactor | doi.org/10.13182/NT86-A33840
A Dynamic Reliability Model for Damage Accumulation Processes
Dov Ingman, Leib Reznik
Nuclear Technology | Volume 75 | Number 3 | December 1986 | Pages 261-282
Technical Paper | Fission Reactor | doi.org/10.13182/NT86-A33841
A Transient Two-Phase Velocity Difference Model for Drift Calculation in CANDU Thermohydraulic Codes
Samir M. Sami
Nuclear Technology | Volume 75 | Number 3 | December 1986 | Pages 283-297
Technical Paper | Fission Reactor | doi.org/10.13182/NT86-A33842
Accelerated Two-Phase Flow Through Perforated Plates
Mario Dalle Donne*, Giacinto P. Tartaglia†
Nuclear Technology | Volume 75 | Number 3 | December 1986 | Pages 298-325
Technical Paper | Fission Reactor | doi.org/10.13182/NT86-A33843
Gaseous Fission Product Retention by Solid Surfaces: Its Role in the Source Term Reduction
Shlomo Ron, Zeev B. Alfassi, Michael Baer
Nuclear Technology | Volume 75 | Number 3 | December 1986 | Pages 326-331
Technical Paper | Nuclear Safety | doi.org/10.13182/NT86-A33844
Crud Formation in the Purex and Thorex Processes
Erich Zimmer, Joachim Borchardt
Nuclear Technology | Volume 75 | Number 3 | December 1986 | Pages 332-337
Technical Paper | Chemical Processing | doi.org/10.13182/NT86-A33845
Probabilistic Modeling of Radionuclide Release at the Waste Package Subsystem Boundary of a Repository in Basalt
Budhi Sagar, Paul W. Eslinger, Robert G. Baca
Nuclear Technology | Volume 75 | Number 3 | December 1986 | Pages 338-349
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT86-A33846
Americium Concentrations in Solutions Contacting Americium-Doped Glass
Dhanpat Rai, Janet A. Schramke, Dean A. Moore, Gary L. McVay
Nuclear Technology | Volume 75 | Number 3 | December 1986 | Pages 350-355
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT86-A33847
Four Nondestructive Electrochemical Tests for Detecting Sensitization in Type 304 and 304L Stainless Steels
Azar P. Majidi, Michael A. Streicher
Nuclear Technology | Volume 75 | Number 3 | December 1986 | Pages 356-369
Technical Paper | Material | doi.org/10.13182/NT86-A33848
Behavior of Alloy A-286 Reactor Vessel Internals Bolting Material
R. S. Piascik*, K. E. Moore
Nuclear Technology | Volume 75 | Number 3 | December 1986 | Pages 370-377
Technical Paper | Material | doi.org/10.13182/NT86-A33849
