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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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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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The Effect of Random Geometry on the Criticality of a Multiplying System IV: Transport Theory
M. M. R. Williams
Nuclear Science and Engineering | Volume 143 | Number 1 | January 2003 | Pages 1-18
Technical Paper | doi.org/10.13182/NSE03-A2314
Perturbation Theory for Lattice Cell Calculations
T. Courau, G. Marleau
Nuclear Science and Engineering | Volume 143 | Number 1 | January 2003 | Pages 19-32
Technical Paper | doi.org/10.13182/NSE02-11
A Neutronic Program for Critical and Nonequilibrium Study of Mobile Fuel Reactors: The Cinsf1D Code
David Lecarpentier, Vincent Carpentier
Nuclear Science and Engineering | Volume 143 | Number 1 | January 2003 | Pages 33-46
Technical Paper | doi.org/10.13182/NSE03-A2316
An Angular Leakage Correction for Modeling a Hemisphere, Using One-Dimensional Spherical Coordinates
K. N. Schwinkendorf, C. S. Eberle
Nuclear Science and Engineering | Volume 143 | Number 1 | January 2003 | Pages 47-60
Technical Paper | doi.org/10.13182/NSE03-A2317
The Characteristics and Subgroup Methods in Square Light Water Reactor Cell Calculations
Tadashi Ushio, Toshikazu Takeda, Masaaki Mori
Nuclear Science and Engineering | Volume 143 | Number 1 | January 2003 | Pages 61-80
Technical Note | doi.org/10.13182/NSE03-A2318
Elastic Scattering of Heavy Projectiles by Light Targets
Raymond L. Murray
Nuclear Science and Engineering | Volume 143 | Number 1 | January 2003 | Pages 81-85
Technical Note | doi.org/10.13182/NSE03-A2319
Measurement of Differential Cross Sections of the 6Li(n,t)4He Reaction at 1.85 and 2.67 MeV
Guohui Zhang, Guoyou Tang, Jinxiang Chen, Zhaomin Shi, Zemin Chen, Yu. M. Gledenov, M. Sedysheva, G. Khuukhenkhuu
Nuclear Science and Engineering | Volume 143 | Number 1 | January 2003 | Pages 86-89
Technical Note | doi.org/10.13182/NSE03-A2320
Calculations for Proton-Induced Reactions Below 250 MeV on 208Pb and 209Bi Targets
Zhengjun Zhang, Xiuquan Sun, Chonghai Cai, Qingbiao Shen, Yinlu Han
Nuclear Science and Engineering | Volume 143 | Number 1 | January 2003 | Pages 90-98
Technical Note | doi.org/10.13182/NSE03-A2321
Methodology of Continuous-Energy Adjoint Monte Carlo for Neutron, Photon, and Coupled Neutron-Photon Transport
J. Eduard Hoogenboom
Nuclear Science and Engineering | Volume 143 | Number 2 | February 2003 | Pages 99-120
Technical Paper | doi.org/10.13182/NSE03-A2322
Monte Carlo Calculation of Sensitivities to Secondaries' Angular Distributions
R. L. Perel
Nuclear Science and Engineering | Volume 143 | Number 2 | February 2003 | Pages 121-131
Technical Paper | doi.org/10.13182/NSE03-A2323
Sensitivity Analyses for Polyethylene-Moderated and Polyethylene-Reflected Highly Enriched Uranium Experiments Mixed with Waste Matrix Materials
David J. Loaiza, Rene Sanchez, Roger Brewer
Nuclear Science and Engineering | Volume 143 | Number 2 | February 2003 | Pages 132-140
Technical Paper | doi.org/10.13182/NSE03-A2324
Optimization of Height-to-Diameter Ratio for an Accelerator-Driven System
Yonghee Kim, Won Seok Park, Tae Yung Song, Chang Kue Park
Nuclear Science and Engineering | Volume 143 | Number 2 | February 2003 | Pages 141-157
Technical Paper | doi.org/10.13182/NSE03-A2325
Statistical Analysis of Reactor Pressure Vessel Fluence Calculation Benchmark Data Using Multiple Regression Techniques
John F. Carew, Stephen J. Finch, Lambros Lois
Nuclear Science and Engineering | Volume 143 | Number 2 | February 2003 | Pages 158-163
Technical Paper | doi.org/10.13182/NSE03-A2326
Combining Intranuclear-Cascade and Preequilibrium Hauser-Feshbach Models for Nuclear Cross-Section Calculations Between 1 MeV and 5 GeV
C. Y. Fu, F. B. Guimaraes, L. C. Leal
Nuclear Science and Engineering | Volume 143 | Number 2 | February 2003 | Pages 164-176
Technical Paper | doi.org/10.13182/NSE03-A2327
Neutron Capture Cross Section of 232Th
V. M. Maslov, Yu. V. Porodzinskij, M. Baba, A. Hasegawa
Nuclear Science and Engineering | Volume 143 | Number 2 | February 2003 | Pages 177-187
Technical Paper | doi.org/10.13182/NSE03-A2328
A Design Study for 99Tc and 129I Transmutation in the HYPER System
Won S. Park, Yong H. Kim, Chang K. Park, Jong S. Chung, Chang H. Kim
Nuclear Science and Engineering | Volume 143 | Number 2 | February 2003 | Pages 188-201
Technical Paper | doi.org/10.13182/NSE03-A2329
Calculation and Analysis of n + 232Th Reaction Cross Sections
Yinlu Han, Qingbiao Shen, Jingshang Zhang, Zhengjun Zhang
Nuclear Science and Engineering | Volume 143 | Number 2 | February 2003 | Pages 202-210
Technical Note | doi.org/10.13182/NSE03-A2330
Critical Power Response to Power Oscillations in Boiling Water Reactors
Yousef M. Farawila, Douglas W. Pruitt
Nuclear Science and Engineering | Volume 143 | Number 3 | March 2003 | Pages 211-225
Technical Paper | doi.org/10.13182/NSE03-A2331
Application of Monte Carlo Chord-Length Sampling Algorithms to Transport Through a Two-Dimensional Binary Stochastic Mixture
Timothy J. Donovan, Yaron Danon
Nuclear Science and Engineering | Volume 143 | Number 3 | March 2003 | Pages 226-239
Technical Paper | doi.org/10.13182/NSE03-A2332
Monte Carlo Calculations of Pebble Bed Benchmark Configurations of the PROTEUS Facility
Felix C. Difilippo
Nuclear Science and Engineering | Volume 143 | Number 3 | March 2003 | Pages 240-253
Technical Paper | doi.org/10.13182/NSE02-34
Using Neural Networks to Predict Core Parameters in a Boiling Water Reactor
Juan Jose Ortiz, Ignacio Requena
Nuclear Science and Engineering | Volume 143 | Number 3 | March 2003 | Pages 254-267
Technical Paper | doi.org/10.13182/NSE03-A2334
The Least-Squares Method for Three-Dimensional Core Power Distribution Monitoring in Pressurized Water Reactors
Kibog Lee, Chang Hyo Kim
Nuclear Science and Engineering | Volume 143 | Number 3 | March 2003 | Pages 268-280
Technical Paper | doi.org/10.13182/NSE03-A2335
Styx: A Multidimensional AMR SN Scheme
Christian Aussourd
Nuclear Science and Engineering | Volume 143 | Number 3 | March 2003 | Pages 281-290
Technical Paper | doi.org/10.13182/NSE03-A2336
Computing the Higher k-Eigenfunctions by Monte Carlo Power Iteration: A Conjecture
Thomas E. Booth
Nuclear Science and Engineering | Volume 143 | Number 3 | March 2003 | Pages 291-300
Technical Note | doi.org/10.13182/NSE02-10TN
Recalculation of Complete Sets of Nuclear Data for n + 85,87Rb in Energy Region of 0.1 to 20 MeV
Chonghai Cai
Nuclear Science and Engineering | Volume 143 | Number 3 | March 2003 | Pages 301-314
Technical Note | doi.org/10.13182/NSE03-A2338
