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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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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Uranium spot price closes out 2024 at $72.63/lb
The uranium market closed out 2024 with a spot price of $72.63 per pound and a long-term price of $80.50 per pound, according to global uranium provider Cameco.
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An Innovative Concept of the Sodium-Cooled Reactor to Pursue High Economic Competitiveness
Yoshio Shimakawa, Shigeo Kasai, Mamoru Konomura, Mikio Toda
Nuclear Technology | Volume 140 | Number 1 | October 2002 | Pages 1-17
Technical Paper | Fission Reactors | doi.org/10.13182/NT02-A3319
Critical Heat Flux During Reflood Transients in Small-Hydraulic-Diameter Geometries
Mark J. Holowach, Lawrence E. Hochreiter, Fan-Bill Cheung, David L. Aumiller
Nuclear Technology | Volume 140 | Number 1 | October 2002 | Pages 18-27
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT02-A3320
Emergency Decay Heat Removal by Reactor Vessel Auxiliary Cooling System from an Accelerator-Driven System
Johan Carlsson, Hartmut Wider
Nuclear Technology | Volume 140 | Number 1 | October 2002 | Pages 28-40
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT02-A3321
Electrotransport of Uranium from a Liquid Cadmium Anode to a Solid Cathode
Rajesh K. Ahluwalia, Thanh Q. Hua
Nuclear Technology | Volume 140 | Number 1 | October 2002 | Pages 41-50
Technical Paper | Reprocessing | doi.org/10.13182/NT02-A3322
Experimental Determination of the Spent Graphite Radioactive Contamination at Plutonium-Production Reactors of the Siberian Group of Chemical Enterprises (TOMSK-7)
Anatoly Y. Bushuev, Yury M. Verzilov, Viktor N. Zubarev, Alexander E. Kachanovsky, Igor M. Proshin, Ekaterina V. Petrova, Tatiana B. Aleeva, Alexander M. Dmitriev, Elena V. Zakharova, Sergei I. Ushakov, Andrey G. Nikolaev, Igor I. Baranov, Yury I. Kabanov, Ella N. Kolobova
Nuclear Technology | Volume 140 | Number 1 | October 2002 | Pages 51-62
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT02-A3323
Experimental and Modeling Indications for Self-Sealing of a Cementitious Low- and Intermediate-Level Waste Repository by Calcite Precipitation
Wilfried Pfingsten
Nuclear Technology | Volume 140 | Number 1 | October 2002 | Pages 63-82
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT02-A3324
Transport of a Two-Member Decay Chain of Radionuclides Through a Discrete Fracture in a Porous Rock Matrix in the Presence of Colloids
Neng-Chuan Tien, Shih-Hai Li
Nuclear Technology | Volume 140 | Number 1 | October 2002 | Pages 83-93
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT02-A3325
Relationship Among Performance of Geologic Repositories, Canister-Array Configuration, and Radionuclide Mass in Waste
Joonhong Ahn, Daisuke Kawasaki, Paul L. Chambré
Nuclear Technology | Volume 140 | Number 1 | October 2002 | Pages 94-112
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT02-A3326
Determination of Long-Lived Neutron Activation Products in Reactor Shielding Concrete Samples
Tomaz Zagar, Matjaz Ravnik
Nuclear Technology | Volume 140 | Number 1 | October 2002 | Pages 113-126
Technical Paper | Radioisotopes | doi.org/10.13182/NT02-A3327
A Robust Multivariable Feedforward/Feedback Controller Design for Integrated Power Control of Boiling Water Reactor Power Plants
Shian-Shing Shyu, Robert M. Edwards
Nuclear Technology | Volume 140 | Number 2 | November 2002 | Pages 129-146
Technical Paper | Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies | doi.org/10.13182/NT02-A3328
Evaluation of the Boron Dilution Method for Moderator Temperature Coefficient Measurements
Christophe Demazière, Imre Pázsit, Gabor Pór
Nuclear Technology | Volume 140 | Number 2 | November 2002 | Pages 147-163
Technical Paper | Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies | doi.org/10.13182/NT02-A3329
Study on Mass Estimation of Loose Parts in Pressurized Water Reactors Using K-L Transform and Neural Network in the Frequency Domain
Jinhui Liu, Fangyu Gu
Nuclear Technology | Volume 140 | Number 2 | November 2002 | Pages 164-168
Technical Paper | Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies | doi.org/10.13182/NT02-A3330
On-Site Electromagnetic Compatibility of a Digital Wide-Range Neutron Monitor to Electric Fast Transients
Hsun-Hua Tseng, Jen-Fu Huang, Jinn-Yih Wu
Nuclear Technology | Volume 140 | Number 2 | November 2002 | Pages 169-177
Technical Paper | Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies | doi.org/10.13182/NT02-A3331
A Neuro-Fuzzy Inference System Combining Wavelet Denoising, Principal Component Analysis, and Sequential Probability Ratio Test for Sensor Monitoring
Man Gyun Na, Seungrohk Oh
Nuclear Technology | Volume 140 | Number 2 | November 2002 | Pages 178-197
Technical Paper | Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies | doi.org/10.13182/NT02-A3332
Nuclear Reactor Power Monitoring Using Silicon Carbide Semiconductor Radiation Detectors
Frank H. Ruddy, Abdul R. Dulloo, John G. Seidel, Frederick W. Hantz, Louis R. Grobmyer
Nuclear Technology | Volume 140 | Number 2 | November 2002 | Pages 198-208
Technical Paper | Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies | doi.org/10.13182/NT02-A3333
Modeling and Optimization of a Constant-Temperature In-Core Power Sensor
Thomas D. Radcliff, Shu-Pei Liu, Don W. Miller
Nuclear Technology | Volume 140 | Number 2 | November 2002 | Pages 209-221
Technical Paper | Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies | doi.org/10.13182/NT02-A3334
High-Temperature Test Facility for Reactor In-Core Sensor Testing
Andrew C. Kauffman, Don W. Miller, Thomas D. Radcliff, Keith W. Maupin, Daniel J. Mills, V. Matthew Penrod
Nuclear Technology | Volume 140 | Number 2 | November 2002 | Pages 222-232
Technical Paper | Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies | doi.org/10.13182/NT02-A3335
An Integral Lead Reactor Concept for Developing Countries
Adimir dos Santos, Jamil Alves do Nascimento
Nuclear Technology | Volume 140 | Number 3 | December 2002 | Pages 233-254
Technical Paper | Fission Reactors | doi.org/10.13182/NT02-A3336
Burnup Importance Function Introduced to Give an Insight into the End Effect
Hiroshi Okuno, Tomohiro Sakai
Nuclear Technology | Volume 140 | Number 3 | December 2002 | Pages 255-265
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT02-A3337
Experimental Study on Critical Power in a Hemispherical Narrow Gap
Rae-Joon Park, Kwang-Soon Ha, Sang-Baik Kim, Hee-Dong Kim, Ji-Hwan Jeong
Nuclear Technology | Volume 140 | Number 3 | December 2002 | Pages 266-278
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT02-A3338
Derivation of Geometry Factors for Internal Gamma Dose Calculations for a Cylindrical Radioactive Waste Package
Brent J. Lewis, Aamir Husain
Nuclear Technology | Volume 140 | Number 3 | December 2002 | Pages 279-287
Technical Paper | Radiation Protection | doi.org/10.13182/NT02-A3339
The Kinetics of 60Co Uptake on and Release from Stainless Steel With and Without 65Zn Addition Under Boiling Water Reactor Conditions
Derek H. Lister, Gopala Venkateswaran, Norman Arbeau
Nuclear Technology | Volume 140 | Number 3 | December 2002 | Pages 288-302
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT02-A3340
PROMETHEE: An Alpha Low Level Waste Assay System Using Passive and Active Neutron Measurement Methods
Christian Passard, Alain Mariani, Fanny Jallu, Jacques Romeyer-Dherbey, Hervé Recroix, Michel Rodriguez, Joel Loridon, Caroline Denis, Hervé Toubon
Nuclear Technology | Volume 140 | Number 3 | December 2002 | Pages 303-314
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT02-A3341
A Study of the Kinetics of I2 Deposition on Stainless Steel Sampling Lines
Greg J. Evans, Tutun Nugraha
Nuclear Technology | Volume 140 | Number 3 | December 2002 | Pages 315-327
Technical Paper | Radioisotopes | doi.org/10.13182/NT02-A3342
Neutron Spectrometry for the Assay of High Fissile Content Spent Fuel
L. Eric Smith, Naeem M. Abdurrahman
Nuclear Technology | Volume 140 | Number 3 | December 2002 | Pages 328-349
Technical Paper | Radiation Measurements and Instrumentation | doi.org/10.13182/NT02-A3343
Summary of Research on Light Water Reactor Improvement Concepts
Alfred L. Mowery
Nuclear Technology | Volume 140 | Number 3 | December 2002 | Pages 350-355
Technical Note | Fuel Cycle and Management | doi.org/10.13182/NT02-A3344