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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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
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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Multidimensional Electron-Photon Transport with Standard Discrete Ordinates Codes
C. R. Drumm
Nuclear Science and Engineering | Volume 127 | Number 1 | September 1997 | Pages 1-21
Technical Paper | doi.org/10.13182/NSE97-A1918
Automatic Variance Reduction for Three-Dimensional Monte Carlo Simulations by the Local Importance Function Transform—I: Analysis
Scott A. Turner, Edward W. Larsen
Nuclear Science and Engineering | Volume 127 | Number 1 | September 1997 | Pages 22-35
Technical Paper | doi.org/10.13182/NSE127-22
Automatic Variance Reduction for Three-Dimensional Monte Carlo Simulations by the Local Importance Function Transform—II: Numerical Results
Nuclear Science and Engineering | Volume 127 | Number 1 | September 1997 | Pages 36-53
Technical Paper | doi.org/10.13182/NSE127-36
Confidence Interval Procedures for Monte Carlo Transport Simulations
S. P. Pederson, R. A. Forster, T. E. Booth
Nuclear Science and Engineering | Volume 127 | Number 1 | September 1997 | Pages 54-77
Technical Paper | doi.org/10.13182/NSE97-A1921
Difficulties in Vector-Parallel Processing of Monte Carlo Codes
Kenji Higuchi, Kiyoshi Asai, Yukihiro Hasegawa
Nuclear Science and Engineering | Volume 127 | Number 1 | September 1997 | Pages 78-88
Technical Paper | doi.org/10.13182/NSE97-A1922
Effect of a 0.3-eV Resonance Cross Section for Plutonium on the Coolant Void Reactivity in a Heavy Water Lattice
Yasuki Kowata, Nobuo Fukumura
Nuclear Science and Engineering | Volume 127 | Number 1 | September 1997 | Pages 89-103
Technical Paper | doi.org/10.13182/NSE97-A1923
R-Matrix Analysis of the 240Pu Neutron Cross Sections in the Thermal to 5700-eV Energy Range
O. Bouland, H. Derrien, N. M. Larson, L. C. Leal
Nuclear Science and Engineering | Volume 127 | Number 2 | October 1997 | Pages 105-129
Technical Paper | doi.org/10.13182/NSE127-105
Partial-Wave Analysis with the Optical Model for the Resolved and Unresolved Resonance Regions of 56Fe
Toshihiko Kawano, Fritz H. Fröhner
Nuclear Science and Engineering | Volume 127 | Number 2 | October 1997 | Pages 130-138
Technical Paper | doi.org/10.13182/NSE97-A28592
A Composite Nodal Finite Element for Hexagons
J. P. Hennart, E. H. Mund, E. Del Valle
Nuclear Science and Engineering | Volume 127 | Number 2 | October 1997 | Pages 139-153
Technical Paper | doi.org/10.13182/NSE97-A28593
Variational Nodal Transport Methods with Heterogeneous Nodes
T. H. Fanning, G. Palmiotti
Nuclear Science and Engineering | Volume 127 | Number 2 | October 1997 | Pages 154-168
Technical Paper | doi.org/10.13182/NSE97-A28594
Discrete Ordinates Methods in xy Geometry with Spatially Varying Angular Discretization
Guillaume Bal, Xavier Warin
Nuclear Science and Engineering | Volume 127 | Number 2 | October 1997 | Pages 169-181
Technical Paper | doi.org/10.13182/NSE97-A28595
A Non-Gaussian Treatment of Radiation Pencil Beams
G. C. Pomraning
Nuclear Science and Engineering | Volume 127 | Number 2 | October 1997 | Pages 182-198
Technical Paper | doi.org/10.13182/NSE97-A28596
Parameter Estimation Toward Fault Diagnosis in Nonlinear Systems Using a Markov Model of System Dynamics
Laurian Dinca, Tunc Aldemir
Nuclear Science and Engineering | Volume 127 | Number 2 | October 1997 | Pages 199-219
Technical Paper | doi.org/10.13182/NSE97-A28597
Heat Transfer Characteristics of Reflux Condensation Phenomena in a Single Vertical Tube
Gung-Huei Chou, Jyh-Chen Chen
Nuclear Science and Engineering | Volume 127 | Number 2 | October 1997 | Pages 220-229
Technical Paper | doi.org/10.13182/NSE97-A28598
Neutron Skyshine Calculations with the Integral Line-Beam Method
Ah Auu Gui, J. Kenneth Shultis, Richard E. Faw
Nuclear Science and Engineering | Volume 127 | Number 2 | October 1997 | Pages 230-237
Technical Note | doi.org/10.13182/NSE97-A28599
Multiple Recycling of Light Water Reactor Waste Plutonium in a Fast Spectrum Core
M. Segev, A. Misulovin, A. Galperin
Nuclear Science and Engineering | Volume 127 | Number 2 | October 1997 | Pages 238-244
Technical Note | doi.org/10.13182/NSE97-A28600
Experimental and Calculated Scandium Threshold Reaction Cross Sections Averaged over a 235U Fission Neutron Spectrum
P. M. Suárez, M. A. Arribére, S. Ribeiro Guevara, A. J. Kestelman
Nuclear Science and Engineering | Volume 127 | Number 3 | November 1997 | Pages 245-261
Technical Paper | doi.org/10.13182/NSE97-A1934
Neutronic Analysis of Critical Configurations in Geologic Repositories: I - Weapons-Grade Plutonium
Ehud Greenspan, J. Vujic, J. Burch
Nuclear Science and Engineering | Volume 127 | Number 3 | November 1997 | Pages 262-291
Technical Paper | doi.org/10.13182/NSE97-A1935
Hydrolysis of Zinc Ion and Solubility of Zinc Oxide in High-Temperature Aqueous Systems
Yukiko Hanzawa, Daisuke Hiroishi, Chihiro Matsuura, Kenkichi Ishigure, Masashi Nagao, Masashi Haginuma
Nuclear Science and Engineering | Volume 127 | Number 3 | November 1997 | Pages 292-299
Technical Paper | doi.org/10.13182/NSE97-03
Development of a Generalized Critical Heat Flux Correlation Through the Alternating Conditional Expectation Algorithm
Han Gon Kim, John C. Lee
Nuclear Science and Engineering | Volume 127 | Number 3 | November 1997 | Pages 300-316
Technical Paper | doi.org/10.13182/NSE97-A1937
Numerical Evaluation of the Three-Dimensional Searchlight Problem in a Half-Space
D. E. Kornreich, B. D. Ganapol
Nuclear Science and Engineering | Volume 127 | Number 3 | November 1997 | Pages 317-337
Technical Paper | doi.org/10.13182/NSE97-A1938
Exponential Convergence on a Continuous Monte Carlo Transport Problem
Thomas E. Booth
Nuclear Science and Engineering | Volume 127 | Number 3 | November 1997 | Pages 338-345
Technical Paper | doi.org/10.13182/NSE97-A1939
Mixed Integer Programming for Pressurized Water Reactor Fuel-Loading-Pattern Optimization
Taek Kyum Kim, Chang Hyo Kim
Nuclear Science and Engineering | Volume 127 | Number 3 | November 1997 | Pages 346-357
Technical Paper | doi.org/10.13182/NSE97-A1940
