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Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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
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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Photon Transport Studies in Media with Strongly Anisotropic Scattering with the Boltzmann-Fokker-Planck Equation
Anil Kumar, Jacques Ligou
Nuclear Science and Engineering | Volume 96 | Number 1 | May 1987 | Pages 1-7
Technical Paper | doi.org/10.13182/NSE87-A16358
Fission Product Yields for Fast-Neutron Fission of 243,244,246,248Cm
J. K. Dickens
Nuclear Science and Engineering | Volume 96 | Number 1 | May 1987 | Pages 8-16
Technical Paper | doi.org/10.13182/NSE87-A16359
Gadolinium Burnable Absorber Optimization by the Method of Conjugate Gradients
Clifton R. Drumm, John C. Lee
Nuclear Science and Engineering | Volume 96 | Number 1 | May 1987 | Pages 17-29
Technical Paper | doi.org/10.13182/NSE87-1
Optimum Arrangement for the Neutron Dose Rate of an Iron-Polyethylene Shielding System
Kohtaro Ueki, Yoshihito Namito
Nuclear Science and Engineering | Volume 96 | Number 1 | May 1987 | Pages 30-38
Technical Paper | doi.org/10.13182/NSE87-A16361
Cross Sections for Two-Body Sequential Decay Reactions
M. D. Baker, H. D. Knox, E. Breitenberger
Nuclear Science and Engineering | Volume 96 | Number 1 | May 1987 | Pages 39-45
Technical Note | doi.org/10.13182/NSE87-A16362
Stability of Muon Catalyzed Fusion Systems
D. R. Wyman, R. E. Stone, A. A. Harms
Nuclear Science and Engineering | Volume 96 | Number 1 | May 1987 | Pages 46-51
Technical Note | doi.org/10.13182/NSE87-A16363
7Li(n,n’t)4He Reaction Cross Section via Tritium Counting
S. M. Qaim, R. Wölfle
Nuclear Science and Engineering | Volume 96 | Number 1 | May 1987 | Pages 52-57
Technical Note | doi.org/10.13182/NSE87-A16364
R-Matrix Analysis of the 241 Pu Cross Sections up to 100 eV
H. Derrien, N. M. Larson, G. de Saussure, R. B. Perez
Nuclear Science and Engineering | Volume 96 | Number 1 | May 1987 | Pages 58-65
Technical Note | doi.org/10.13182/NSE87-A16365
Investigations of Electromagnetic Cascades Produced in Lead by 2.5-GeV Bremsstrahlung
Hideo Hirayama, Syuichi Ban, Shigeyuki Miura
Nuclear Science and Engineering | Volume 96 | Number 1 | May 1987 | Pages 66-72
Technical Note | doi.org/10.13182/NSE87-A16366
Improvement of Passive Safety of Reactors
Yoshiro Asahi, Tadashi Watanabe,Hiroaki Wakabayashi
Nuclear Science and Engineering | Volume 96 | Number 1 | May 1987 | Pages 73-84
Technical Note | doi.org/10.13182/NSE87-A16367
Optimization of Core Reload Design for Low-Leakage Fuel Management in Pressurized Water Reactors
Young Jin Kim,* Thomas J. Downar, Alexander Sesonske
Nuclear Science and Engineering | Volume 96 | Number 2 | June 1987 | Pages 85-101
Technical Paper | doi.org/10.13182/NSE87-A16369
Fission Rates and High-Energy Neutron Fluxes in the Purdue Fast Breeder Blanket Facility
Helio C. Vital,* F. M. Clikeman, K. O. Ott
Nuclear Science and Engineering | Volume 96 | Number 2 | June 1987 | Pages 102-111
Technical Paper | doi.org/10.13182/NSE87-A16370
Resonance Self-Shielding near Zone Interfaces
S. C. Mo, K. O. Ott
Nuclear Science and Engineering | Volume 96 | Number 2 | June 1987 | Pages 112-121
Technical Paper | doi.org/10.13182/NSE87-A16371
Nuclear Data for 235U, 238U, and 239Pu in the Unresolved Resonance Region
A. A. Vankov and V. F. Ukraintsev, N. Yaneva, S. Toshkov, A. Mateeva
Nuclear Science and Engineering | Volume 96 | Number 2 | June 1987 | Pages 122-136
Technical Paper | doi.org/10.13182/NSE87-A16372
Thermocapillary-Induced Breakup of Molten Cladding Films
P. R. Henkel
Nuclear Science and Engineering | Volume 96 | Number 2 | June 1987 | Pages 137-144
Technical Paper | doi.org/10.13182/NSE87-A16373
Estimation of Failed Sensor Outputs
J. Louis Tylee
Nuclear Science and Engineering | Volume 96 | Number 2 | June 1987 | Pages 145-152
Technical Paper | doi.org/10.13182/NSE87-A16374
Some Aspects of the Forward Method for High-Order Sensitivity Analysis
Yigal Ronen
Nuclear Science and Engineering | Volume 96 | Number 2 | June 1987 | Pages 153-158
Technical Paper | doi.org/10.13182/NSE87-A16375
Measurement and Status of Neutron Scattering on 1Li and 7Li Between 6 and 14 MeV
D. Schmidt, D. Seeliger, G. N. Lovchikova, A. M. Trufanov
Nuclear Science and Engineering | Volume 96 | Number 2 | June 1987 | Pages 159-167
Technical Note | doi.org/10.13182/NSE87-A16376
Time Behavior of the Neutron Flux at the Vessel Boundary of a Boiling Water Reactor Power Plant
A. Cesana, M. Terrani, G. Sandrelli
Nuclear Science and Engineering | Volume 96 | Number 2 | June 1987 | Pages 168-170
Technical Note | doi.org/10.13182/NSE87-A16377
GERES: A Code to Process MC2-II Data for Heterogeneous Fast Reactor Cell Calculation
M. Galli
Nuclear Science and Engineering | Volume 96 | Number 2 | June 1987 | Pages 171-172
Computer Code Abstract | doi.org/10.13182/NSE87-A16378
A Critique of Three Methodologies for Estimating the Probability of Containment Failure Due to Steam Explosions
Marshall Berman
Nuclear Science and Engineering | Volume 96 | Number 3 | July 1987 | Pages 173-191
Technical Paper | doi.org/10.13182/NSE87-A16380
A Rigorous Pole Representation of Multilevel Cross Sections and Its Practical Applications
R. N. Hwang
Nuclear Science and Engineering | Volume 96 | Number 3 | July 1987 | Pages 192-209
Technical Paper | doi.org/10.13182/NSE87-A16381
Calculation of Capture Cross Sections and Gamma-Ray Spectra Following the Interaction of Neutrons with 181Ta and 197Au
Nobuhiro Yamamuro, Kazuyuki Udagawa, Toshihiro Natsume
Nuclear Science and Engineering | Volume 96 | Number 3 | July 1987 | Pages 210-220
Technical Paper | doi.org/10.13182/NSE87-A16382
On the Generalized Neutron Noise Formulation with Application to a Coupled Core Reactor
Shyn-Jen Lee
Nuclear Science and Engineering | Volume 96 | Number 3 | July 1987 | Pages 221-233
Technical Paper | doi.org/10.13182/NSE87-A16383
Neutron Transport Theory in a Ring Reactor
M. M. R. Williams
Nuclear Science and Engineering | Volume 96 | Number 3 | July 1987 | Pages 234-240
Technical Note | doi.org/10.13182/NSE87-A16384
A Comparison of Gamma-Ray Buildup Factors for Low-Z Material and for Low Energies Using Discrete Ordinates and Point Monte Carlo Methods
Yoshiko Harima, Hideo Hirayama, Toshio Ishikawa, Yukio Sakamoto, Shun-ich Tanaka
Nuclear Science and Engineering | Volume 96 | Number 3 | July 1987 | Pages 241-252
Technical Note | doi.org/10.13182/NSE87-A16385
Effect of a Mixing Vane in a Three-Subchannel Simulated Fuel Rod Bundle Using a Gamma Camera
Alireza Sedaghat, Robert Macduff, Frank Castellana
Nuclear Science and Engineering | Volume 96 | Number 3 | July 1987 | Pages 253-259
Technical Note | doi.org/10.13182/NSE87-A16386
LEPRICON Analysis of Pressure Vessel Surveillance Dosimetry Inserted into H. B. Robinson-2 During Cycle 9
R. E. Maerker
Nuclear Science and Engineering | Volume 96 | Number 4 | August 1987 | Pages 263-289
Technical Paper | doi.org/10.13182/NSE87-A16391
DOXCY—A Discrete Ordinates Approximation of Neutron Transport in Heterogeneous Rod Lattices
H. Dietmar Märtens, D. Stegemann
Nuclear Science and Engineering | Volume 96 | Number 4 | August 1987 | Pages 290-302
Technical Paper | doi.org/10.13182/NSE87-A16392
Prompt Response Self-Powered Neutron Detectors I: The Effective Charge per Neutron Captured
Maria Do Carmo Lopes, Jorge Molina Avila
Nuclear Science and Engineering | Volume 96 | Number 4 | August 1987 | Pages 303-309
Technical Paper | doi.org/10.13182/NSE87-A16393
Prompt Response Self-Powered Neutron Detectors II: Thermal and Epithermal Sensitivities
Jorge Molina Avila, Maria Do Carmo Lopes
Nuclear Science and Engineering | Volume 96 | Number 4 | August 1987 | Pages 310-317
Technical Paper | doi.org/10.13182/NSE87-A16394
Parameters of the 1.056-eV Resonance in 240Pu and the 2200 m/s Neutron Total Cross Sections of 235U, 239Pu, and 240Pu
R. Spencer, J. A. Harvey, N. W. Hill, L. W. Weston
Nuclear Science and Engineering | Volume 96 | Number 4 | August 1987 | Pages 318-329
Technical Paper | doi.org/10.13182/NSE87-A16395
Effect of Fluorescence in Deep Penetration of Gamma Rays
K. V. Subbaiah, A. Natarajan
Nuclear Science and Engineering | Volume 96 | Number 4 | August 1987 | Pages 330-342
Technical Paper | doi.org/10.13182/NSE87-A16396
