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Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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
Virginia utility considers SMRs
Dominion Energy Virginia has issued a request for proposals from leading nuclear companies to study the feasibility of putting a small modular reactor at its North Anna nuclear power plant.
While the utility says it is not a commitment to build an SMR at the site, the RFP is “an important first step in evaluating the technology and the North Anna site to support Dominion Energy customers’ future energy needs consistent with the company’s most recent Integrated Resource Plan.”
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An Approach for Integrating Plant Operations and Maintenance Information with System Reliability Analysis
Edmund T. Rumble, Boyer B. Chu
Nuclear Technology | Volume 79 | Number 1 | October 1987 | Pages 7-19
Technical Paper | Fission Reactor | doi.org/10.13182/NT87-A16001
The Multispectrum High Convertor Water Reactor
Yigal Ronen, Melvin J. Leibson
Nuclear Technology | Volume 79 | Number 1 | October 1987 | Pages 20-34
Technical Paper | Fission Reactor | doi.org/10.13182/NT87-A16002
A Resonant Cavity Level Measurement Technique for Use with Gas Enhancement Modules in Liquid-Metal Reactors
Douglas R. Smith, Robert W. Albrecht
Nuclear Technology | Volume 79 | Number 1 | October 1987 | Pages 35-50
Technical Paper | Fission Reactor | doi.org/10.13182/NT87-A16003
Preliminary Analysis of a Small, Inherently Safe Boiling Water Reactor
Sreenivas Jayanti, Richard N. Christensen, Nancy Yost, Chris Wang, David van Deusen, Don W. Miller
Nuclear Technology | Volume 79 | Number 1 | October 1987 | Pages 51-65
Technical Paper | Fission Reactor | doi.org/10.13182/NT87-A16004
Distributions for Binomial Failure Rate Parameters
Corwin L. Atwood
Nuclear Technology | Volume 79 | Number 1 | October 1987 | Pages 66-81
Technical Paper | Nuclear Safety | doi.org/10.13182/NT87-A16005
Critical Experiments Using High-Enriched Uranyl Nitrate with Cadmium Absorber
Raymond C. Lloyd, E. Duane Clayton, Robert E. Wilson, Robert C. McBroom, Robert R. Jones
Nuclear Technology | Volume 79 | Number 1 | October 1987 | Pages 82-91
Technical Paper | Nuclear Safety | doi.org/10.13182/NT87-A16006
Safety Analyses and Derivation of Site-Specific Requirements on Radioactive Waste for the Planned German Repository “Konrad”
Heinz Peter Berg, Dietrich Ehrlich, Heinrich Illi, Bruno R. Thomauske
Nuclear Technology | Volume 79 | Number 1 | October 1987 | Pages 92-99
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT87-A16007
Numerical Investigation of Fluid and Thermal Mixing During High-Pressure Injection
Tzing-Shenq Horng, Cheng-Chang Chieng
Nuclear Technology | Volume 79 | Number 1 | October 1987 | Pages 100-115
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT87-A16008
Dissolution of PuO2 in HNO3-HF-N2H4 Medium
Mrs. Abdul Majeed Shakila, Thandangorai Ganapathi Srinivasan, Kanwal Nain Sabharwal, Polur Rangarao Vasudeva Rao
Nuclear Technology | Volume 79 | Number 1 | October 1987 | Pages 116-119
Technical Note | Chemical Processing | doi.org/10.13182/NT87-A16009
Measurement of Velocity Profile of Mercury Flow by Ultrasound Doppler Shift Method
Yasushi Takeda
Nuclear Technology | Volume 79 | Number 1 | October 1987 | Pages 120-124
Technical Note | Heat Transfer and Fluid Flow | doi.org/10.13182/NT87-A16010
The Politics of Uranium
Mary Gerry White
Nuclear Technology | Volume 79 | Number 1 | October 1987 | Page 125
Department | Book Review | doi.org/10.13182/NT87-A16011
HTR-100 Industrial Nuclear Power Plant for Generation of Heat and Electricity
Siegfried Brandes, Wolfgang Kohl
Nuclear Technology | Volume 79 | Number 2 | November 1987 | Pages 135-143
Technical Paper | Nuclear Power Plants for Generation of Heat / Fission Reactor | doi.org/10.13182/NT87-A34031
Design Principles of a Simple and Safe 200-MW(thermal) Nuclear District Heating Plant
Claus Goetzmann, Dietmar Bittermann, Andreas Göbel
Nuclear Technology | Volume 79 | Number 2 | November 1987 | Pages 144-157
Technical Paper | Nuclear Power Plants for Generation of Heat / Fission Reactor | doi.org/10.13182/NT87-A34032
Assessment of Safety-Relevant Aspects of Kraftwerk Union’s 200-MW(thermal) Nuclear District Heating Plant Concept
Peter Erlenwein, Willi Frisch, Peter Kafka, Rudolf E. Kirmse, Siegfried Langenbuch
Nuclear Technology | Volume 79 | Number 2 | November 1987 | Pages 158-166
Technical Paper | Nuclear Power Plants for Generation of Heat / Fission Reactor | doi.org/10.13182/NT87-A34033
The Swiss Heating Reactor for District Heating of Small Communities
Peter Burgsmüller, Andreas Jacobi, Jr., Jean-François Jaeger, Max J. Kläntschi, Walter Seifritz, François Vuilleumier, Ferdinand Wegmann
Nuclear Technology | Volume 79 | Number 2 | November 1987 | Pages 167-174
Technical Paper | Nuclear Power Plants for Generation of Heat / Fission Reactor | doi.org/10.13182/NT87-A34034
The SECURE Heating Reactor
Christen Pind
Nuclear Technology | Volume 79 | Number 2 | November 1987 | Pages 175-185
Technical Paper | Nuclear Power Plants for Generation of Heat / Fission Reactor | doi.org/10.13182/NT87-A34035
Design and Testing of the Reactor-Internal Hydraulic Control Rod Drive for the Nuclear Heating Plant
Pramod Batheja, Werner Jakob Meier, and, Peter Josef Rau
Nuclear Technology | Volume 79 | Number 2 | November 1987 | Pages 186-195
Technical Paper | Nuclear Power Plants for Generation of Heat / Fission Reactor | doi.org/10.13182/NT87-A34036
Optimization of Fuel Exchange Machine Operation for Boiling Water Reactors Using an Artificial Intelligence Technique
Koichi Sekimizu, Tsuneyasu Araki, Shin-Ichiro Tatemichi
Nuclear Technology | Volume 79 | Number 2 | November 1987 | Pages 196-209
Technical Paper | Nuclear Power Plants for Generation of Heat / Fission Reactor | doi.org/10.13182/NT87-A34037
Caorso Limit Cycle Oscillation Analysis with Three-Dimensional Transient Code TOSDYN-2
Yukio Takigawa, Yutaka Takeuchi, Shigeaki Tsunoyama, Shigeo Ebata, Kai C. Chan, Carlo Tricoli
Nuclear Technology | Volume 79 | Number 2 | November 1987 | Pages 210-227
Technical Paper | Nuclear Power Plants for Generation of Heat / Fission Reactor | doi.org/10.13182/NT87-A34038
Probabilistic Fracture Evaluation of a Fast Breeder Reactor Cover
Sadao Hattori, Norihiko Handa
Nuclear Technology | Volume 79 | Number 2 | November 1987 | Pages 228-240
Technical Paper | Nuclear Power Plants for Generation of Heat / Fission Reactor | doi.org/10.13182/NT87-A34039
A Remote Maintenance Robot System for a Pulsed Nuclear Reactor
William M. Davidson, Alan K. Morimoto, Mary M. Moya, J. Lee Schoeneman, Siegfried Thunborg, Gregory P. Starr
Nuclear Technology | Volume 79 | Number 3 | December 1987 | Pages 249-259
Technical Paper | Fission Reactor | doi.org/10.13182/NT87-A34015
A Digital Computer Model for Predicting Reactor Coolant Pump Behavior
Samir M. Sami, C. Tran
Nuclear Technology | Volume 79 | Number 3 | December 1987 | Pages 260-273
Technical Paper | Fission Reactor | doi.org/10.13182/NT87-A34016
Prompt-Neutron Decay Constant Estimation at Full-Power Operation
Mo-Chen Hsu
Nuclear Technology | Volume 79 | Number 3 | December 1987 | Pages 274-283
Technical Paper | Fission Reactor | doi.org/10.13182/NT87-A34017
A Real-Time Expert System for Nuclear Power Plant Failure Diagnosis and Operational Guide
Norio Naito, Akira Sakuma, Kei Shigeno, Nobuyuki Mori
Nuclear Technology | Volume 79 | Number 3 | December 1987 | Pages 284-296
Technical Paper | Fission Reactor | doi.org/10.13182/NT87-A34018
Pool Dynamics of Natural-Convection-Cooled Research Reactors
Jae-Joo Ha, Tunc Aldemir
Nuclear Technology | Volume 79 | Number 3 | December 1987 | Pages 297-310
Technical Paper | Fission Reactor | doi.org/10.13182/NT87-A34019
Site Selection of a Dual Purpose Nuclear Power Plant in Saudi Arabia
Fahmy M. Hussein, Mohamed A. Obeid, Khalid S. El-Malahy
Nuclear Technology | Volume 79 | Number 3 | December 1987 | Pages 311-321
Technical Paper | Nuclear Safety | doi.org/10.13182/NT87-A34020
Calculational Assessment of the Measurability of Key Radionuclides for Severely Failed Nuclear Power Plant Fuel
Stephen E. Binney, Richard D. Harris
Nuclear Technology | Volume 79 | Number 3 | December 1987 | Pages 322-327
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT87-A34021
Melting of Uranium-Contaminated Metal Cylinders by Electroslag Refining
Tatsuhiko Uda, Yoshihiro Ozawa, Hajime Iba
Nuclear Technology | Volume 79 | Number 3 | December 1987 | Pages 328-337
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT87-A34022
Modeling Interaction of Deep Groundwaters with Bentonite and Radionuclide Speciation
Hans Wanner
Nuclear Technology | Volume 79 | Number 3 | December 1987 | Pages 338-347
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT87-A34023
Empirical Correlations from Waste Grout Formulation Data
Othar K. Tallent, Earl W. McDaniel, Karen E. Dodson, Terry T. Godsey
Nuclear Technology | Volume 79 | Number 3 | December 1987 | Pages 348-358
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT87-A34024
Mathematical Modeling of the Chemical Decontamination of Boiling Water Reactor Components
Alexander P. Murray
Nuclear Technology | Volume 79 | Number 3 | December 1987 | Pages 359-370
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT87-A34025
A Study of Flow Through a Fracture Network Described by Statistically Distributed Properties
Carol Braester, Roger Thunvik
Nuclear Technology | Volume 79 | Number 3 | December 1987 | Pages 371-376
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT87-A34026
A Design of the Liquid-Metal Reactor Having an Almost Constant Reactivity
Hyong Chol Kim, Ming-Yuan Hsiao, Samuel H. Levine
Nuclear Technology | Volume 79 | Number 3 | December 1987 | Pages 377-381
Technical Note | Fission Reactor | doi.org/10.13182/NT87-A34027
