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
Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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
Jun 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
July 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
Jump to:
Simulation Experiments on Boiling Noise of Boiling Water Reactors
Zhang Mingchang, Zhou Gouzhen
Nuclear Technology | Volume 54 | Number 1 | July 1981 | Pages 9-18
Technical Paper | Fission Reactor | doi.org/10.13182/NT81-A32749
Simulation Study of a System for Diagnosis of Nuclear Power Plant Operation
Jiro Wakabayashi, Akira Fukumoto
Nuclear Technology | Volume 54 | Number 1 | July 1981 | Pages 19-30
Technical Paper | Fission Reactor | doi.org/10.13182/NT81-A32750
Improvement of Boiling Water Reactor Startup Characteristics by Core Inlet Enthalpy Control
Masayuki Izumi, Renzo Takeda
Nuclear Technology | Volume 54 | Number 1 | July 1981 | Pages 31-37
Technical Paper | Fission Reactor | doi.org/10.13182/NT81-A32751
Application of Differential Sensitivity Theory to a Neutronic/Thermal-Hydraulic Reactor Safety Code
C. V. Parks, P. J. Maudlin
Nuclear Technology | Volume 54 | Number 1 | July 1981 | Pages 38-53
Technical Paper | Fission Reactor | doi.org/10.13182/NT81-A32752
Performance of Containment Sprays for Light Water Reactors and Evaluation of the Heat Transfer
Mitsugu Tanaka, Hironori Watanabe, Kazuichiro Hashimoto, Yasuo Motoki, Mitsuo Naritomi, Gunji Nishio, Susumu Kitani
Nuclear Technology | Volume 54 | Number 1 | July 1981 | Pages 54-67
Technical Paper | Nuclear safety | doi.org/10.13182/NT81-A32753
Containment Spray Model for Predicting Radioiodine Removal in Light Water Reactors
Gunji Nishio, Mitsugu Tanaka, Kazuichiro Hashimoto, Yasuo Motoki, Mitsuo Naritomi, Susumu Kitani
Nuclear Technology | Volume 54 | Number 1 | July 1981 | Pages 68-86
Technical Paper | Nuclear safety | doi.org/10.13182/NT81-A32754
Modifications of the Fuel Rod Analysis Program FRAP-S3 to Account for the Effects of Fuel Initial Density
J. Yaung, N. Ghoniem
Nuclear Technology | Volume 54 | Number 1 | July 1981 | Pages 87-91
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT81-A32755
Gas Generation from Organic Transuranic Wastes. I. Alpha Radiolysis at Atmospheric Pressure
Stanley T. Kosiewicz
Nuclear Technology | Volume 54 | Number 1 | July 1981 | Pages 92-99
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT81-A32756
Hanford Site Sorption Studies for the Control of Radioactive Wastes: a Review
R. C. Routson, G. S. Barney, R. M. Smith
Nuclear Technology | Volume 54 | Number 1 | July 1981 | Pages 100-106
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT81-A32757
Properties of Plutonium(IV) Polymer of Environmental Importance
Dhanpat Rai, J. L. Swanson
Nuclear Technology | Volume 54 | Number 1 | July 1981 | Pages 107-112
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT81-A32758
Quenching and Rewetting of Nuclear Fuel Rods
F. S. Gunnerson, T. R. Yackle
Nuclear Technology | Volume 54 | Number 1 | July 1981 | Pages 113-117
Technical Note | Nuclear Fuel | doi.org/10.13182/NT81-A32759
Hydrothermal Transformations in Candidate Overpack Materials and their Effects on Cesium and Strontium Sorption
Sridhar Komarneni, Rustum Roy
Nuclear Technology | Volume 54 | Number 1 | July 1981 | Pages 118-122
Technical Note | Radioactive Waste Management | doi.org/10.13182/NT81-A32760
Criticality Experiments with Subcritical Clusters of 2.35 and 4.31 wt% 235U-Enriched UO2 Rods in Water with Steel Reflecting Walls
S. R. Bierman, E. D. Clayton
Nuclear Technology | Volume 54 | Number 2 | August 1981 | Pages 131-144
Technical Paper | Fission Reactor | doi.org/10.13182/NT81-A32730
Effect of Inoperable in-Core Detectors on Core Monitoring System Accuracy
R. K. Endter, R. G. Foster
Nuclear Technology | Volume 54 | Number 2 | August 1981 | Pages 145-154
Technical Paper | Fission Reactor | doi.org/10.13182/NT81-A32731
Three Mile Island Accident Technical Support
R. L. Long, T. M. Crimmins, W. W. Lowe
Nuclear Technology | Volume 54 | Number 2 | August 1981 | Pages 155-173
Technical Paper | Fission Reactor | doi.org/10.13182/NT81-A32732
An Analytical Model for Transient Gas Flow in Nuclear Fuel Rods
D. S. Rowe, R. N. Oehlberg
Nuclear Technology | Volume 54 | Number 2 | August 1981 | Pages 174-179
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT81-A32733
Calculation of Neutron Source Strength in Fast Flux Test Facility Fuel as a Function of Irradiation
Paride A. Ombrellaro, David L. Johnson
Nuclear Technology | Volume 54 | Number 2 | August 1981 | Pages 180-200
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT81-A32734
Corrosion of Structural Alloys in Liquid Rubidium
T. R. Pinchback, J. R. Winkel, D. K. Matlock, D. L. Olson
Nuclear Technology | Volume 54 | Number 2 | August 1981 | Pages 201-207
Technical Paper | Material | doi.org/10.13182/NT81-A32735
Electrolytic Decontamination of Stainless Steel Using a Basic Electrolyte
E. L. Childs, J. L. Long
Nuclear Technology | Volume 54 | Number 2 | August 1981 | Pages 208-214
Technical Paper | Material | doi.org/10.13182/NT81-A32736
Chemical Compatibility of uranium Carbides with Cr-Fe-Ni Alloys
Edward C. Beahm, Charles A. Culpepper
Nuclear Technology | Volume 54 | Number 2 | August 1981 | Pages 215-222
Technical Paper | Material | doi.org/10.13182/NT81-A32737
Behavior of Metallic Inclusions in Uranium Dioxide
Rosa L. Yang, D. R. Olander
Nuclear Technology | Volume 54 | Number 2 | August 1981 | Pages 223-233
Technical Paper | Material | doi.org/10.13182/NT81-A32738
The Interaction of High Temperature Core Debris with Concrete and Refractory Material
E. Sowa, J. Pavlik
Nuclear Technology | Volume 54 | Number 2 | August 1981 | Pages 234-238
Technical Note | Nuclear Safety | doi.org/10.13182/NT81-A32739
A Mathematical Model of Corrosion Product Transport in the Boiling Water Reactor Primary System
C. C. Lin, C. R. Pao, J. S. Wiley, W. R. DeHollander
Nuclear Technology | Volume 54 | Number 3 | September 1981 | Pages 253-265
Technical Paper | Fission Reactor | doi.org/10.13182/NT81-A32770
Radionuclide Chain Transport Through Heterogeneous Media
J. Hadermann, J. Patry
Nuclear Technology | Volume 54 | Number 3 | September 1981 | Pages 266-277
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT81-A32771
Regeneration of a Large Cold Trap
Katsuro Takahashi, Yoshiaki Himeno, Nobutomo Takahashi, June Takahashi, Tatsuro Iguchi
Nuclear Technology | Volume 54 | Number 3 | September 1981 | Pages 278-285
Technical Paper | Material | doi.org/10.13182/NT81-A32772
RETRAN Dynamic Slip Model
J. H. McFadden, M. P. Paulsen, G. C. Gose
Nuclear Technology | Volume 54 | Number 3 | September 1981 | Pages 287-297
First International Retran Meeting | Heat Transfer and Fluid Flow | doi.org/10.13182/NT81-A32774
A One-Dimensional Reactor Kinetics Model for RETRAN
G. C. Gose, C. E. Peterson, N. L. Ellis, J. A. McClure
Nuclear Technology | Volume 54 | Number 3 | September 1981 | Pages 298-310
First International Retran Meeting | Heat Transfer and Fluid Flow | doi.org/10.13182/NT81-A32775
Analysis of Pressurized Water Reactor Anticipated Transient Without Scram Transients with RETRAN-02
Joseph A. Naser, Bal Raj Sehgal, Lance J. Agee
Nuclear Technology | Volume 54 | Number 3 | September 1981 | Pages 311-321
First International Retran Meeting | Heat Transfer and Fluid Flow | doi.org/10.13182/NT81-A32776
Modeling Loss-of-Fluid Test Small-Break Experiments with RETRAN
James R. White, Charles E. Hendrix
Nuclear Technology | Volume 54 | Number 3 | September 1981 | Pages 322-331
First International Retran Meeting | Heat Transfer and Fluid Flow | doi.org/10.13182/NT81-A32777
A RETRAN Analysis of the Crystal River Unit 3 Incident of February 26, 1980
V. K. Chexal, W. H. Layman, W. W. Brown, G. B. Caldwell
Nuclear Technology | Volume 54 | Number 3 | September 1981 | Pages 332-341
First International Retran Meeting | Heat Transfer and Fluid Flow | doi.org/10.13182/NT81-A32778
RETRAN Pressurized Water Reactor Applications at General Public Utilities
T. G. Broughton, N. G. Trikouros
Nuclear Technology | Volume 54 | Number 3 | September 1981 | Pages 342-357
First International Retran Meeting | Heat Transfer and Fluid Flow | doi.org/10.13182/NT81-A32779
RETRAN Simulation of Three Mile Island Unit 2 Startup Overfeed Incident
L. C. Pwu, T. G. Broughton
Nuclear Technology | Volume 54 | Number 3 | September 1981 | Pages 358-363
First International Retran Meeting | Heat Transfer and Fluid Flow | doi.org/10.13182/NT81-A32780
Oconee RETRAN Model Comparisons with Plant Transient Data
Gregg B. Swindlehurst
Nuclear Technology | Volume 54 | Number 3 | September 1981 | Pages 364-372
First International Retran Meeting | Heat Transfer and Fluid Flow | doi.org/10.13182/NT81-A32781
RETRAN Analysis of the Peach Bottom Turbine Trip Tests
Joseph A. Naser
Nuclear Technology | Volume 54 | Number 3 | September 1981 | Pages 373-379
First International Retran Meeting | Heat Transfer and Fluid Flow | doi.org/10.13182/NT81-A32782
Analysis of Chinshan Unit 1 Full Load Rejection Transient Using RETRAN
E. Lin, Y. H. Cheng, J. K. Hsiue
Nuclear Technology | Volume 54 | Number 3 | September 1981 | Pages 380-384
First International Retran Meeting | Heat Transfer and Fluid Flow | doi.org/10.13182/NT81-A32783
RETRAN Simulation of Peach Bottom 2 Beginning of Cycle 5 Main Steam Relief Valve Discharge Test
H. J. Diamond, W. G. Lee
Nuclear Technology | Volume 54 | Number 3 | September 1981 | Pages 385-392
First International Retran Meeting | Heat Transfer and Fluid Flow | doi.org/10.13182/NT81-A32784
Simulation of a Simultaneous Closure of All Main Steam Isolation Valves Without Scram for a Boiling Water Reactor/4 Using RETRAN-01
James T. Cronin, Bruce C. Slifer
Nuclear Technology | Volume 54 | Number 3 | September 1981 | Pages 393-397
First International Retran Meeting | Heat Transfer and Fluid Flow | doi.org/10.13182/NT81-A32785
RETRAN Calculation of Loss of Feedwater Transients at Connecticut Yankee
D. P. Griggs, T. J. Honan
Nuclear Technology | Volume 54 | Number 3 | September 1981 | Pages 398-409
First International Retran Meeting | Heat Transfer and Fluid Flow | doi.org/10.13182/NT81-A32786
A Drift-Flux Model of Two-Phase Flow for RETRAN
E. D. Hughes, M. P. Paulsen, L. J. Agee
Nuclear Technology | Volume 54 | Number 3 | September 1981 | Pages 410-421
First International Retran Meeting | Heat Transfer and Fluid Flow | doi.org/10.13182/NT81-A32787
High Void Fraction Measurements in Full-Scale Heat Transfer Tests
Gian Piero Celata, Franco Vittorio Frazzoli
Nuclear Technology | Volume 54 | Number 3 | September 1981 | Pages 422-425
Technical Note | Heat Transfer and Fluid Flow | doi.org/10.13182/NT81-A32788
