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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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
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Analysis of Differences in Void Coefficient Predictions for Mixed-Oxide-Fueled Tight-Pitch Light Water Reactor Cells
Hironobu Unesaki, Seiji Shiroya, Keiji Kanda, Stéphane Cathalau, Franck-Olivier Carré, Otohiko Aizawa, Toshikazu Takeda
Nuclear Science and Engineering | Volume 135 | Number 1 | May 2000 | Pages 1-22
Technical Paper | doi.org/10.13182/NSE00-A2120
Measurement of Activation Reaction Rate Distributions in a Lead Assembly Bombarded with 500-MeV Protons
Hiroshi Takada, Shin-ichro Meigo, Toshinobu Sasa, Kazufumi Tsujimoto, Hideshi Yasuda
Nuclear Science and Engineering | Volume 135 | Number 1 | May 2000 | Pages 23-32
Technical Paper | doi.org/10.13182/NSE00-A2121
Epithermal Inverse Kinetic Measurements and Their Interpretation Using a Two-Group Point-Kinetic Model
Marc Rosselet, Rakesh Chawla, Tony Williams
Nuclear Science and Engineering | Volume 135 | Number 1 | May 2000 | Pages 33-47
Technical Paper | doi.org/10.13182/NSE99-33
Influence of the Thermal Cutoff Energy on the Calculation of Neutronic Parameters for Light Water Reactor Lattices
Jean-Marie Paratte, Sandro Pelloni
Nuclear Science and Engineering | Volume 135 | Number 1 | May 2000 | Pages 48-56
Technical Paper | doi.org/10.13182/NSE00-A2123
Properties of a Cold-Neutron Irradiation Facility for In Vitro Research on Boron Neutron Capture Therapy at the Geesthacht Neutron Facility
L. Lüdemann, R. Kampmann, W. Sosaat, P. Staron, P. Wille
Nuclear Science and Engineering | Volume 135 | Number 1 | May 2000 | Pages 57-63
Technical Paper | doi.org/10.13182/NSE00-A2124
Verification of the Neutron Flux of a Modified Zero-Power Reactor Using a Neutron Activation Method
Lung Kwang Pan, Cheng Si Tsao
Nuclear Science and Engineering | Volume 135 | Number 1 | May 2000 | Pages 64-72
Technical Paper | doi.org/10.13182/NSE00-A2125
A Multigroup Albedo Method for Transport Calculations: Application to the Orphée Core
S. Rauck, R. Sanchez, I. Zmijarevic, M. Nobile
Nuclear Science and Engineering | Volume 135 | Number 1 | May 2000 | Pages 73-83
Technical Paper | doi.org/10.13182/NSE00-A2126
Nuclide Importance and the Steady-State Burnup Equation
Hiroshi Sekimoto, Atsushi Nemoto
Nuclear Science and Engineering | Volume 135 | Number 1 | May 2000 | Pages 84-102
Technical Paper | doi.org/10.13182/NSE00-A2127
Differential Sampling Applied to Mammography Image Simulation
Douglas E. Peplow, Kuruvilla Verghese
Nuclear Science and Engineering | Volume 135 | Number 2 | June 2000 | Pages 103-122
Technical Paper | doi.org/10.13182/NSE00-A2128
Neutron Transport in Spatially Random Media: An Assessment of the Accuracy of First Order Smoothing
M. M. R. Williams
Nuclear Science and Engineering | Volume 135 | Number 2 | June 2000 | Pages 123-140
Technical Paper | doi.org/10.13182/NSE00-A2129
New High-Resolution Fission Cross-Section Measurements of 233U in the 0.4-eV to 700-keV Energy Range
K. H. Guber, R. R. Spencer, L. C. Leal, J. A. Harvey, N. W. Hill, G. Dos Santos, R. O. Sayer, D. C. Larson
Nuclear Science and Engineering | Volume 135 | Number 2 | June 2000 | Pages 141-149
Technical Paper | doi.org/10.13182/NSE00-A2130
Reactivity Control Method for Direct Use of Spent Pressurized Water Reactor Fuel in CANDU Reactors (DUPIC)
Hangbok Choi, Won Il Ko, Myung Seung Yang
Nuclear Science and Engineering | Volume 135 | Number 2 | June 2000 | Pages 150-164
Technical Paper | doi.org/10.13182/NSE00-A2131
SPACON - A Theoretical Model for Calculating the Heat Transport Properties in Sphere-Pac Fuel Pins
F. Botta, C. Hellwig
Nuclear Science and Engineering | Volume 135 | Number 2 | June 2000 | Pages 165-176
Technical Paper | doi.org/10.13182/NSE00-A2132
Experimental Study of Two-Phase Flow Oscillation in Natural Circulation
S. Y. Jiang, X. X. Wu, Y. J. Zhang
Nuclear Science and Engineering | Volume 135 | Number 2 | June 2000 | Pages 177-189
Technical Paper | doi.org/10.13182/NSE00-A2133
On the Curvature of Transmitted Intensity Plots in Broad Beam Studies
A. H. El-Kateb
Nuclear Science and Engineering | Volume 135 | Number 2 | June 2000 | Pages 190-198
Technical Paper | doi.org/10.13182/NSE00-A2134
Spatial and Angular Moment Analysis of Continuous and Discretized Transport Problems
Patrick S. Brantley, Edward W. Larsen
Nuclear Science and Engineering | Volume 135 | Number 3 | July 2000 | Pages 199-226
Technical Paper | doi.org/10.13182/NSE00-A2135
Measurement of Absolute Fission Yields in the Fast Neutron-Induced Fission of Actinides: 238U, 237Np, 238Pu, 240Pu, 243Am, and 244Cm by Track-Etch-cum-Gamma Spectrometry
R. H. Iyer, H. Naik, A. K. Pandey, P. C. Kalsi, R. J. Singh, A. Ramaswami, A. G. C. Nair
Nuclear Science and Engineering | Volume 135 | Number 3 | July 2000 | Pages 227-245
Technical Paper | doi.org/10.13182/NSE00-A2136
Effects of Differing Energy Dependences in Three Level-Density Models on Calculated Cross Sections
C. Y. Fu
Nuclear Science and Engineering | Volume 135 | Number 3 | July 2000 | Pages 246-259
Technical Paper | doi.org/10.13182/NSE00-A2137
16O(n,p)16N Reaction Cross Sections Around 14 MeV
M.Subasi, E. Gültekin, I. A. Reyhancan, Y. Özbir, G. Tarcan, M. Sirin, M. N. Erduran
Nuclear Science and Engineering | Volume 135 | Number 3 | July 2000 | Pages 260-266
Technical Paper | doi.org/10.13182/NSE00-A2138
Numerical Simulation of the Emergency Condenser of the SWR-1000
Eckhard Krepper, Andreas Schaffrath, Attila Aszódi
Nuclear Science and Engineering | Volume 135 | Number 3 | July 2000 | Pages 267-279
Technical Paper | doi.org/10.13182/NSE00-A2139
Use of Axially Graded Burnable Boron for Hot-Spot Temperature Reduction in a Pressurized Water Reactor Core
M. Segev, A. Galperin, E. Schwageraus
Nuclear Science and Engineering | Volume 135 | Number 3 | July 2000 | Pages 280-287
Technical Paper | doi.org/10.13182/NSE00-A2140
Lognormal Size Distribution Theory for Deposition of Polydisperse Aerosol Particles
S. H. Park, K. W. Lee
Nuclear Science and Engineering | Volume 135 | Number 3 | July 2000 | Pages 288-295
Technical Note | doi.org/10.13182/NSE00-A2141
Application of a Simple Ramsauer Model for Neutron Total Cross Sections for Nuclear Mass Numbers A < 40
S. M. Grimes, J. D. Anderson, R. W. Bauer
Nuclear Science and Engineering | Volume 135 | Number 3 | July 2000 | Pages 296-303
Technical Note | doi.org/10.13182/NSE00-A2142
Calculation of the Dancoff Factor for Pebble Bed Reactors
J. Valko, P. V. Tsvetkov, J. E. Hoogenboom
Nuclear Science and Engineering | Volume 135 | Number 3 | July 2000 | Pages 304-307
Technical Note | doi.org/10.13182/NSE00-A2143
