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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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Senate committee hears from energy secretary nominee Chris Wright
Wright
Chris Wright, president-elect Trump’s pick to lead the U.S. Department of Energy, spent hours today fielding questions from members of the U.S. Senate’s committee on Energy and Natural Resources.
During the hearing, Wright—who’s spent most of his career in fossil fuels—made comments in support of nuclear energy and efforts to expand domestic generation in the near future. Asked what actions he would take as energy secretary to improve the development and deployment of SMRs, Wright said: “It’s a big challenge, and I’m new to government, so I can’t list off the five levers I can pull. But (I’ve been in discussions) about how to make it easier to research, to invest, to build things. The DOE has land at some of its facilities that can be helpful in this regard.”
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Optimal Choice of Parameters for Exponential Biasing in Monte Carlo
A. Dubi, Donald J. Dudziak
Nuclear Science and Engineering | Volume 70 | Number 1 | April 1979 | Pages 1-13
Technical Paper | doi.org/10.13182/NSE79-A18922
Bounded Flux-at-a-Point Estimators for Multigroup Monte Carlo Computer Codes
S. K. Fraley, T. J. Hoffman
Nuclear Science and Engineering | Volume 70 | Number 1 | April 1979 | Pages 14-19
Technical Paper | doi.org/10.13182/NSE79-A18923
Development of Depletion Perturbation Theory for Coupled Neutron/Nuclide Fields
M. L. Williams
Nuclear Science and Engineering | Volume 70 | Number 1 | April 1979 | Pages 20-36
Technical Paper | doi.org/10.13182/NSE79-3
PURNIMA—A PuO2-Fueled Zero-Energy Fast Reactor at Trombay
P. K. Iyengar, T. K. Basu, K. Chandramoleshwar, S. Das, P. K. Job, S. K. Kapil, V. R. Nargundkar, C. S. Pasupathy, M. Srinivasan, K. Subba Rao
Nuclear Science and Engineering | Volume 70 | Number 1 | April 1979 | Pages 37-52
Technical Paper | doi.org/10.13182/NSE79-A18925
Neutron Capture Cross Sections of Rhodium, Thulium, Iridium, and Gold Between 0.5 and 3.0 MeV
S. Joly, J. Voignier, G. Grenier, D. M. Drake, L. Nilsson
Nuclear Science and Engineering | Volume 70 | Number 1 | April 1979 | Pages 53-59
Technical Paper | doi.org/10.13182/NSE79-A18926
Diagnostic Neutron Spectra from Deuterons on Several Materials
H. W. Lefevre, J. C. Davis, J. D. Anderson
Nuclear Science and Engineering | Volume 70 | Number 1 | April 1979 | Pages 60-65
Technical Paper | doi.org/10.13182/NSE79-A18927
Transitor Damage Characterization by Neutron Displacement Cross Section in Silicon: Experimental
V. V. Verbinski, C. Cassapakis, R. L. Pease, H. L. Scott
Nuclear Science and Engineering | Volume 70 | Number 1 | April 1979 | Pages 66-72
Technical Paper | doi.org/10.13182/NSE79-A18928
Diffusion Coefficients of Sodium Vapors in Argon and Helium
T. Kumada, R. Ishiguro, Y. Kimachi
Nuclear Science and Engineering | Volume 70 | Number 1 | April 1979 | Pages 73-81
Technical Paper | doi.org/10.13182/NSE79-A18929
An Atomic Model for Neutral and Singly Ionized Uranium
Edward L. Maceda, George H. Miley
Nuclear Science and Engineering | Volume 70 | Number 1 | April 1979 | Pages 82-95
Technical Paper | doi.org/10.13182/NSE79-A18930
Three Basic Neutron-Transport Problems in Spherical Geometry
C. E. Siewert, P. Grandjean
Nuclear Science and Engineering | Volume 70 | Number 1 | April 1979 | Pages 96-98
Technical Note | doi.org/10.13182/NSE70-96
The Total Neutron Cross Section of Boron-10 Between 90 and 420 keV
H. Beer, R. R. Spencer
Nuclear Science and Engineering | Volume 70 | Number 1 | April 1979 | Pages 98-101
Technical Note | doi.org/10.13182/NSE79-A18932
Fission Yields for Fast-Neutron Fission of Uranium-238
J. E. Gindler, L. E. Glendenin, J. W. Meadows, Jr., K. F. Flynn
Nuclear Science and Engineering | Volume 70 | Number 1 | April 1979 | Pages 101-106
Technical Note | doi.org/10.13182/NSE79-A18933
Identifiability of Dynamics of a Boiling Water Reactor Using Autoregressive Modeling
Masaharu Kitamura, Kunihiko Matsubara, Ritsuo Oguma
Nuclear Science and Engineering | Volume 70 | Number 1 | April 1979 | Pages 106-110
Technical Note | doi.org/10.13182/NSE79-A18934
On the Use of Minimum Film Boiling Temperature as a Criterion for Coherent Molten Metal-Coolant Interactions
Vijay K. Dhir
Nuclear Science and Engineering | Volume 70 | Number 2 | May 1979 | Pages 119-126
Technical Paper | doi.org/10.13182/NSE79-A19644
Application of Acoustic Agglomerators for Emergency Use in Liquid-Metal Fast Breeder Reactor Plants
D. T. Shaw, N. Rajendran
Nuclear Science and Engineering | Volume 70 | Number 2 | May 1979 | Pages 127-134
Technical Paper | doi.org/10.13182/NSE79-A19645
Expert Opinion and Statistical Evidence: An Application to Reactor Core Melt Frequency
George Apostolakis, Ali Mosleh
Nuclear Science and Engineering | Volume 70 | Number 2 | May 1979 | Pages 135-149
Technical Paper | doi.org/10.13182/NSE79-A19646
The Transmission of Neutrons Through Iron-56 at 24.37 keV
H. I. Liou, R. E. Chrien, R. C. Block, U. N. Singh
Nuclear Science and Engineering | Volume 70 | Number 2 | May 1979 | Pages 150-154
Technical Paper | doi.org/10.13182/NSE79-A19647
Neutron Resonance Parameters for Neptunium-237
L. Mewissen, F. Poortmans, E. Cornelis, G. Vanpraet, A. Angeletti, G. Rohr, H. Weigmann
Nuclear Science and Engineering | Volume 70 | Number 2 | May 1979 | Pages 155-162
Technical Paper | doi.org/10.13182/NSE79-A19648
Cross Sections for the 14N(n,p0), (n,α0), and (n,α1) Reactions from 0.5 to 15 MeV
G. L. Morgan
Nuclear Science and Engineering | Volume 70 | Number 2 | May 1979 | Pages 163-176
Technical Paper | doi.org/10.13182/NSE79-A19649
Fission Yields for Thermal-Neutron Fission of Plutonium-241
J. K. Dickens
Nuclear Science and Engineering | Volume 70 | Number 2 | May 1979 | Pages 177-183
Technical Paper | doi.org/10.13182/NSE79-A19650
Calculated Time-Dependent Delayed Neutron Group Yields for Thermal-Neutron Fission of Uranium-235
D. R. Alexander, Y. K. Peng
Nuclear Science and Engineering | Volume 70 | Number 2 | May 1979 | Pages 184-191
Technical Paper | doi.org/10.13182/NSE79-A19651
Electron Transport in One-Dimensional Finite Systems
S. K. Gupta, M. A. Prasad
Nuclear Science and Engineering | Volume 70 | Number 2 | May 1979 | Pages 192-200
Technical Paper | doi.org/10.13182/NSE79-A19652
Use of Temperature Variance to Detect Sodium Boiling
C. C. Meek, R. C. Doerner, R. F. Hurt
Nuclear Science and Engineering | Volume 70 | Number 2 | May 1979 | Pages 201-204
Technical Note | doi.org/10.13182/NSE79-A19653
Exact Closed-Form Solution for a Terminal Cost Problem of Nuclear Reactors with Distributed Parameters
S. H. Kim
Nuclear Science and Engineering | Volume 70 | Number 2 | May 1979 | Pages 204-207
Technical Note | doi.org/10.13182/NSE79-A19654
On the Polynomial Form of Gamma-Ray Buildup Factor Functions
M. Metghalchi
Nuclear Science and Engineering | Volume 70 | Number 2 | May 1979 | Pages 207-209
Technical Note | doi.org/10.13182/NSE79-A19655
Optimum Biasing of Integral Equations in Monte Carlo Calculations
J. E. Hoogenboom
Nuclear Science and Engineering | Volume 70 | Number 2 | May 1979 | Pages 210-212
Technical Note | doi.org/10.13182/NSE79-A19656
Two- and Three-Dimensional Neutronics Calculations for the Tokamak Fusion Test Reactor Neutral Beam Injectors
R. T. Santoro, R. A. Lillie, R. G. Alsmiller, Jr., J. M. Barnes
Nuclear Science and Engineering | Volume 70 | Number 3 | June 1979 | Pages 225-242
Technical Paper | doi.org/10.13182/NSE79-A20145
Prediction of Statistical Error and Optimization of Biased Monte Carlo Transport Calculations
P. K. Sarkar, M. A. Prasad
Nuclear Science and Engineering | Volume 70 | Number 3 | June 1979 | Pages 243-261
Technical Paper | doi.org/10.13182/NSE79-A20146
Lattice Eigenvalue as a Function of Buckling: Correction to First-Order Perturbation Theory
Ely M. Gelbard, Raymond P. Hughes
Nuclear Science and Engineering | Volume 70 | Number 3 | June 1979 | Pages 262-273
Technical Paper | doi.org/10.13182/NSE79-A20147
Tritium Production in a Sphere of 6LiD Irradiated by 14-MeV Neutrons
A. Hemmendinger, C. E. Ragan, Jon M. Wallace
Nuclear Science and Engineering | Volume 70 | Number 3 | June 1979 | Pages 274-280
Technical Paper | doi.org/10.13182/NSE79-A20148
Neutron Interaction with Carbon-12 in the Few-MeV Region
A. Smith, R. Holt, J. Whalen
Nuclear Science and Engineering | Volume 70 | Number 3 | June 1979 | Pages 281-293
Technical Paper | doi.org/10.13182/NSE79-A20149
Neutron Inelastic Scattering in Silicon-28 to 4.15 MeV
N. B. Sullivan, J. J. Egan, G. H. R. Kegel, P. Harihar
Nuclear Science and Engineering | Volume 70 | Number 3 | June 1979 | Pages 294-297
Technical Paper | doi.org/10.13182/NSE79-A20150
Emission Probability of the 312-keV Gamma Ray from the Decay of Protactinium-233
R. J. Gehrke, R. G. Helmer, C. W. Reich
Nuclear Science and Engineering | Volume 70 | Number 3 | June 1979 | Pages 298-306
Technical Paper | doi.org/10.13182/NSE79-A20151
Self-Shielded Fission Rates for Uranium-235
J. B. Czirr
Nuclear Science and Engineering | Volume 70 | Number 3 | June 1979 | Pages 307-308
Technical Note | doi.org/10.13182/NSE79-A20152
Neutron Multiplication Studies in Beryllium for Fusion Reactor Blankets
T. K. Basu, V. R. Nargundkar, P. Cloth, D. Filges, S. Taczanowski
Nuclear Science and Engineering | Volume 70 | Number 3 | June 1979 | Pages 309-313
Technical Note | doi.org/10.13182/NSE79-A20153
Reactor Fuel Burnup Calculations in the LASER Code
Y. Y. Chang, S. K. Loyalka, D. H. Timmons
Nuclear Science and Engineering | Volume 70 | Number 3 | June 1979 | Pages 313-315
Technical Note | doi.org/10.13182/NSE79-A20154
Availability Maximization of Supervised Protective Systems for Nuclear Reactors
J. M. Kontoleon
Nuclear Science and Engineering | Volume 70 | Number 3 | June 1979 | Pages 315-317
Technical Note | doi.org/10.13182/NSE79-A20155
