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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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
Marzano sworn in as NRC commissioner
Marzano
Matthew Marzano became the newest member of the Nuclear Regulatory Commission when he was officially sworn into office by chair Christopher Hanson this week.
The nuclear engineer and former reactor operator was confirmed last month in a 50–45 vote in the U.S. Senate. Last July, President Biden nominated Marzano to serve on the commission, which is tasked with formulating policies, developing regulations, issuing orders, and resolving legal matters.
Marzano’s term expires June 30, 2028.
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Reduction in Reactor Vessel Irradiation Through Fuel Management
Charles W. Bagnal, Jr., Gerard P. Cavanaugh, Robert P. Harris, Regis A. Matzie, Laszlo B. Tarko
Nuclear Technology | Volume 68 | Number 1 | January 1985 | Pages 7-17
Technical Paper | Fission Reactor | doi.org/10.13182/NT85-A33562
Reducing the Cobalt Inventory in Light Water Reactors
Howard Ocken
Nuclear Technology | Volume 68 | Number 1 | January 1985 | Pages 18-28
Technical Paper | Fission Reactor | doi.org/10.13182/NT85-A33563
Shielding Factors for Gamma Radiation from Activity Deposited on Structures and Ground Surfaces
Per Hedemann Jensen
Nuclear Technology | Volume 68 | Number 1 | January 1985 | Pages 29-39
Technical Paper | Nuclear Safety | doi.org/10.13182/NT85-A33564
Postirradiation Behavior of UO2 Fuel II: Fragments at 175 to 275°C in Air
Ian J. Hastings, Elio Mizzan, Alan M. Ross, John R. Kelm, Real J. Chenier, D. H. Rose, J. Novak
Nuclear Technology | Volume 68 | Number 1 | January 1985 | Pages 40-47
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT85-A33565
The Sodium-Bonding Pin Concept for Advanced Fuels. Part III: Calculations of the Swelling Performance
Claudio Ronchi, Jacques van de Laar, Hubert Blank
Nuclear Technology | Volume 68 | Number 1 | January 1985 | Pages 48-65
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT85-A33566
Incineration of Ion Exchange Resins Using Concentric Burners
Tetsuo Fukasawa, Koichi Chino, Osamu Kuriyama, Fumio Kawamura, Hideo Yusa
Nuclear Technology | Volume 68 | Number 1 | January 1985 | Pages 66-72
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT85-A33567
A Simple Probabilistic Risk Analysis for High-Level Waste Repositories
Bernard L. Cohen
Nuclear Technology | Volume 68 | Number 1 | January 1985 | Pages 73-76
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT85-A33568
ROSA-III Double-Ended Break Test Series for a Loss-of-Coolant Accident in a Boiling Water Reactor
K. Tasaka, M. Suzuki, Y. Anoda, Y. Koizumi, T. Yonomoto, H. Kumamaru, H. Nakamura, M. Shiba
Nuclear Technology | Volume 68 | Number 1 | January 1985 | Pages 77-93
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT85-A33569
Neutron Radiography with a Sealed-Tube Neutron Generator in a Hot Laboratory Water Pool at Nagoya University
Genichi Matsumoto, Soichi Doi, Kohei Ohkubo, Yasushi Ikeda
Nuclear Technology | Volume 68 | Number 1 | January 1985 | Pages 94-101
Technical Paper | Analyse | doi.org/10.13182/NT85-A33570
Development of Nuclear Power Plant Noise Diagnostics into a Process-Measuring Method
Günther Hessel, Hans-Erich Köppen, Peter Liewers, Peter Schumann, Frank-Peter Weiß
Nuclear Technology | Volume 68 | Number 1 | January 1985 | Pages 102-110
Technical Note | Fission Reactor | doi.org/10.13182/NT85-A33571
Superphénix 1 at Creys-Malville: Overall Nuclear Steam Supply System Coordination and Construction by Novatome-Nira
Jean Befre
Nuclear Technology | Volume 68 | Number 2 | February 1985 | Pages 125-134
Technical Paper | Fabrication of Components of the Creys-Malville Plant / Fission Reactor | doi.org/10.13182/NT85-A33548
Superphénix 1 Reactor Block Fabrication
Joël Branchu, Charles Gigarel
Nuclear Technology | Volume 68 | Number 2 | February 1985 | Pages 135-145
Technical Paper | Fabrication of Components of the Creys-Malville Plant / Fission Reactor | doi.org/10.13182/NT85-A33549
Superphénix 1 Intermediate Heat Exchanger Fabrication
Henri Noël, Francesco Granito, Pierre Pouderoux
Nuclear Technology | Volume 68 | Number 2 | February 1985 | Pages 146-152
Technical Paper | Fabrication of Components of the Creys-Malville Plant / Fission Reactor | doi.org/10.13182/NT85-A33550
Fabrication and Testing of Main Sodium Pumps of Superphénix 1
Henri Noël, Gilbert Pasqualini
Nuclear Technology | Volume 68 | Number 2 | February 1985 | Pages 153-159
Technical Paper | Fabrication of Components of the Creys-Malville Plant / Fission Reactor | doi.org/10.13182/NT85-A33551
Superphénix 1 Primary Handling System Fabrication and Testing
Joël Branchu, Charles Gigarel, Kurt Ebbinghaus
Nuclear Technology | Volume 68 | Number 2 | February 1985 | Pages 160-170
Technical Paper | Fabrication of Components of the Creys-Malville Plant / Fission Reactor | doi.org/10.13182/NT85-A33552
Superphénix 1 Steam Generator Fabrication
Jean-Paul Crette, Thierry Zuber
Nuclear Technology | Volume 68 | Number 2 | February 1985 | Pages 171-179
Technical Paper | Fabrication of Components of the Creys-Malville Plant / Fission Reactor | doi.org/10.13182/NT85-A33553
A Survey of Expert Opinion and Its Probabilistic Evaluation for Specific Aspects of the SNR-300 Risk Study
Eduard Hofer, Vijen Javeri, Horst Löffler, Dankward F. Struwe
Nuclear Technology | Volume 68 | Number 2 | February 1985 | Pages 180-225
Technical Paper | Fabrication of Components of the Creys-Malville Plant / Nuclear Safety | doi.org/10.13182/NT85-A33554
Two Measures of Risk Importance and Their Application
William E. Vesely, Thomas C. Davis
Nuclear Technology | Volume 68 | Number 2 | February 1985 | Pages 226-234
Technical Paper | Fabrication of Components of the Creys-Malville Plant / Nuclear Safety | doi.org/10.13182/NT85-A33555
The Fuel Cycle Effect of 236U in Pressurized Water Reactors
Ansar Parvez
Nuclear Technology | Volume 68 | Number 2 | February 1985 | Pages 235-241
Technical Paper | Fabrication of Components of the Creys-Malville Plant / Fuel Cycle | doi.org/10.13182/NT85-A33556
Experimental and Analytical Study on the Time-Dependent Removal Efficiency of Methyl Iodide by an Impregnated Charcoal Bed
Soon Heung Chang, Won Jin Cho
Nuclear Technology | Volume 68 | Number 2 | February 1985 | Pages 242-251
Technical Paper | Fabrication of Components of the Creys-Malville Plant / Chemical Processing | doi.org/10.13182/NT85-A33557
Considerations for Modeling Critical Heat Flux Behavior
Joe E. Dahlquist, Fred S. GL, Ralph A. Nelson
Nuclear Technology | Volume 68 | Number 2 | February 1985 | Pages 252-262
Technical Paper | Fabrication of Components of the Creys-Malville Plant / Heat Transfer and Fluid Flow | doi.org/10.13182/NT85-A33558
Reactor Physics Calculations on Close-Packed Pressurized Water Reactor Lattices
Erik Johansson
Nuclear Technology | Volume 68 | Number 2 | February 1985 | Pages 263-268
Technical Note | Fabrication of Components of the Creys-Malville Plant / Fission Reactor | doi.org/10.13182/NT85-A33559
A Semiempirical Relationship for the Excess Reactivity of a Reactor as a Function of Cycle Time, Axial Flux Form Factor, and Leakage Parameter
Ashwin P. Muzumdar, Douglas G. Andrews
Nuclear Technology | Volume 68 | Number 3 | March 1985 | Pages 275-280
Technical Paper | Fission Reactor | doi.org/10.13182/NT85-A33574
Primary Coolant Feed and Bleed Operating Regions for the Midland Plant
Hsian Shi Tsai
Nuclear Technology | Volume 68 | Number 3 | March 1985 | Pages 281-292
Technical Paper | Fission Reactor | doi.org/10.13182/NT85-A33575
Experimental Determination of the Atmospheric Dispersion Parameters at the Karlsruhe Nuclear Research Center for Emission Heights of 60 and 100 m
P. Thomas, K. Nester
Nuclear Technology | Volume 68 | Number 3 | March 1985 | Pages 293-310
Technical Paper | Nuclear Safety | doi.org/10.13182/NT85-A33576
Hiroshima and Nagasaki Initial Radiations: Delayed Neutron Contributions and Comparison of Calculated and Measured Cobalt Activations
William E. Loewe
Nuclear Technology | Volume 68 | Number 3 | March 1985 | Pages 311-318
Technical Paper | Nuclear Safety | doi.org/10.13182/NT85-A33577
Optimal Thorium-Fueled CANDU Nuclear Reactor Fuel Management
Hugues W. Bonin, Alexander Sesonske
Nuclear Technology | Volume 68 | Number 3 | March 1985 | Pages 319-335
Technical Paper | Fuel Cycle | doi.org/10.13182/NT85-A33578
Uranium Diffusion in H-451 Graphite
O. K. Tallent, R. P. Wichner, Roy L. Towns
Nuclear Technology | Volume 68 | Number 3 | March 1985 | Pages 336-343
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT85-A33579
High-Temperature Gas-Cooled Reactor Fuel Pressure Vessel Performance Models
William J. Kovacs, Karl Bongartz, Dan T. Goodin
Nuclear Technology | Volume 68 | Number 3 | March 1985 | Pages 344-354
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT85-A33580
Rod Bundle Burnout Data and Correlation Comparison
Graydon L. Yoder, Jr., David G. Morris, Charles B. Mullins
Nuclear Technology | Volume 68 | Number 3 | March 1985 | Pages 355-369
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT85-A33581
ISARD, A Method of Tomographic Reconstruction of the Position of Gamma Emitters in a Nuclear Fuel Pin from Transversal Gamma Scanning
Gérard Ducros
Nuclear Technology | Volume 68 | Number 3 | March 1985 | Pages 370-384
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT85-A33582
Dissolution of Metal Oxides Accumulated in Nuclear Steam Generators: Study of Solutions Containing Organic Chelating Agents
Roland Gilbert, Lorenzo Ouellet
Nuclear Technology | Volume 68 | Number 3 | March 1985 | Pages 385-394
Technical Paper | Material | doi.org/10.13182/NT85-A33583
Computational Investigation of Fluid and Thermal Mixing of the EPRI/Creare One-Fifth-Scale Facility
Yassin A. Hassan, J. H. KIM
Nuclear Technology | Volume 68 | Number 3 | March 1985 | Pages 395-407
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT85-A33584
Evaluation of Countercurrent Gas/Liquid Flow in Parallel Channels with Restricted Ends
Michio Murase, Hiroaki Suzuki
Nuclear Technology | Volume 68 | Number 3 | March 1985 | Pages 408-417
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT85-A33585
Postirradiation Behavior of Naturally and Artificially Defected UO2 Fuel Elements at 250°C in Air
Ian J. Hastings, Elio Mizzan, John R. Kelm, Robert E. Moeller, J. Novak
Nuclear Technology | Volume 68 | Number 3 | March 1985 | Pages 418-422
Technical Note | Nuclear Fuel | doi.org/10.13182/NT85-A33586
Thermal Expansion of U.S. and Australian SYNROC B
Hans Rolf Käse, John Aloysius Tesk, Eldon Darrel Case
Nuclear Technology | Volume 68 | Number 3 | March 1985 | Pages 423-426
Technical Note | Material | doi.org/10.13182/NT85-A33587
