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Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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2025 ANS Annual Conference
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BREAKING NEWS: Trump issues executive orders to overhaul nuclear industry
The Trump administration issued four executive orders today aimed at boosting domestic nuclear deployment ahead of significant growth in projected energy demand in the coming decades.
During a live signing in the Oval Office, President Donald Trump called nuclear “a hot industry,” adding, “It’s a brilliant industry. [But] you’ve got to do it right. It’s become very safe and environmental.”
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Some Improvements in State/Parameter Estimation Using the Cell-to-Cell Mapping Technique
Peng Wang, Tunc Aldemir
Nuclear Science and Engineering | Volume 147 | Number 1 | May 2004 | Pages 1-25
Technical Paper | doi.org/10.13182/NSE04-A2415
Krylov Subspace Iterations for Deterministic k-Eigenvalue Calculations
James S. Warsa, Todd A. Wareing, Jim E. Morel, John M. McGhee, Richard B. Lehoucq
Nuclear Science and Engineering | Volume 147 | Number 1 | May 2004 | Pages 26-42
Technical Paper | doi.org/10.13182/NSE04-1
Improvement of MERCURE-6's General Formalism for Calculating Gamma-Ray Buildup Factors in Multilayer Shields
Christophe Suteau, Maurice Chiron, Gilles Arnaud
Nuclear Science and Engineering | Volume 147 | Number 1 | May 2004 | Pages 43-55
Technical Paper | doi.org/10.13182/NSE04-A2417
A Model for Dead-Time Effects in Coincidence Counting
Ming-Shih Lu, Theodor Teichmann
Nuclear Science and Engineering | Volume 147 | Number 1 | May 2004 | Pages 56-62
Technical Paper | doi.org/10.13182/NSE04-A2418
A Systematics to Investigate the (n,) Cross Section with Energy Below 20 MeV Based on the Evaporation and Exciton Models
Sheng Fan, Xiaochun Shi, Fang Yan, Hongzhou Zhang, Zhixiang Zhao
Nuclear Science and Engineering | Volume 147 | Number 1 | May 2004 | Pages 63-72
Technical Paper | doi.org/10.13182/NSE04-A2419
Production of Neutrons with Protons of 22, 30, and 40 MeV in Stopping Targets of Carbon, Aluminum, Copper, Silver, Tantalum, and Lead
Thomas M. Amos, Robert R. Doering, Aaron Galonsky, Raj Jolly, Mary K. Zigrang
Nuclear Science and Engineering | Volume 147 | Number 1 | May 2004 | Pages 73-82
Technical Paper | doi.org/10.13182/NSE04-A2420
The Neutron Production Cross Sections for Pb, Bi, and Au Targets and Neutron Multiplicity for Nuclear Spallation Reaction Induced by 20- to 1600-MeV Protons
I. Demirkol, E. Tel, A. Arasoglu, A. Özmen, B. Sarer, A. Acir, M. Alkan
Nuclear Science and Engineering | Volume 147 | Number 1 | May 2004 | Pages 83-91
Technical Note | doi.org/10.13182/NSE04-A2421
Super-Nodal Methods for Space-Time Kinetics
Ugur Mertyurek, Paul J. Turinsky
Nuclear Science and Engineering | Volume 147 | Number 2 | June 2004 | Pages 93-126
Technical Paper | doi.org/10.13182/NSE04-A2422
Convergence Analysis of the Nonlinear Coarse-Mesh Finite Difference Method for One-Dimensional Fixed-Source Neutron Diffusion Problem
Deokjung Lee, Thomas J. Downar, Yonghee Kim
Nuclear Science and Engineering | Volume 147 | Number 2 | June 2004 | Pages 127-147
Technical Paper | doi.org/10.13182/NSE03-64
Optimized Algorithm for Collision Probability Calculations in Cubic Geometry
R. D. M. Garcia
Nuclear Science and Engineering | Volume 147 | Number 2 | June 2004 | Pages 148-157
Technical Paper | doi.org/10.13182/NSE04-A2424
Singular Solutions, Integral Transport Theory, and the Sn Method
J. E. Morel, K. D. Lathrop
Nuclear Science and Engineering | Volume 147 | Number 2 | June 2004 | Pages 158-166
Technical Paper | doi.org/10.13182/NSE04-A2425
Neutron Flux Distribution in a Cavity with a Point Source
Biplab Ghosh, S. B. Degweker
Nuclear Science and Engineering | Volume 147 | Number 2 | June 2004 | Pages 167-175
Technical Paper | doi.org/10.13182/NSE04-A2426
Acceleration of Response Matrix Method Using Cross-Section Scaling
Akio Yamamoto
Nuclear Science and Engineering | Volume 147 | Number 2 | June 2004 | Pages 176-184
Technical Paper | doi.org/10.13182/NSE04-A2427
Evaluation of the Efficiency of Gamma Spectrometers for Measuring Volumetric Samples
Nader M. A. Mohamed, M. Abou Mandour
Nuclear Science and Engineering | Volume 147 | Number 2 | June 2004 | Pages 185-188
Technical Paper | doi.org/10.13182/NSE04-A2428
A Comparative Review of Sensitivity and Uncertainty Analysis of Large-Scale Systems—I: Deterministic Methods
Mihaela Ionescu-Bujor, Dan G. Cacuci
Nuclear Science and Engineering | Volume 147 | Number 3 | July 2004 | Pages 189-203
Technical Paper | doi.org/10.13182/NSE03-105CR
A Comparative Review of Sensitivity and Uncertainty Analysis of Large-Scale Systems—II: Statistical Methods
Dan G. Cacuci, Mihaela Ionescu-Bujor
Nuclear Science and Engineering | Volume 147 | Number 3 | July 2004 | Pages 204-217
Technical Paper | doi.org/10.13182/04-54CR
Krylov Iterative Methods and the Degraded Effectiveness of Diffusion Synthetic Acceleration for Multidimensional SN Calculations in Problems with Material Discontinuities
James S. Warsa, Todd A. Wareing, Jim E. Morel
Nuclear Science and Engineering | Volume 147 | Number 3 | July 2004 | Pages 218-248
Technical Paper | doi.org/10.13182/NSE02-14
Discrete Ordinates Solutions for Highly Forward Peaked Scattering
Richard Sanchez, Norman J. McCormick
Nuclear Science and Engineering | Volume 147 | Number 3 | July 2004 | Pages 249-274
Technical Paper | doi.org/10.13182/NSE04-A2432
Unified Nodal Method for Solution to the Space-Time Kinetics Problems
Hyun Chul Lee, Ku Young Chung, Chang Hyo Kim
Nuclear Science and Engineering | Volume 147 | Number 3 | July 2004 | Pages 275-291
Technical Paper | doi.org/10.13182/NSE04-A2433
A Stochastic Problem Arising in the Storage of Radioactive Waste
M. M. R. Williams
Nuclear Science and Engineering | Volume 147 | Number 3 | July 2004 | Pages 292-306
Technical Paper | doi.org/10.13182/NSE04-A2434
Critical Experiments with Highly Enriched Uranium and Matrix Elements (Si, Mg, Al, Gd, and Fe)
Rene Sanchez, David Loaiza, Glenn Brunson, Robert Kimpland
Nuclear Science and Engineering | Volume 147 | Number 3 | July 2004 | Pages 307-318
Technical Paper | doi.org/10.13182/NSE04-A2435
Compression and Heating of a Gaseous Deuterium-Tritium Mixture by Means of Cascaded Light Gas Guns and Its Possible Application to Nuclear Fusion
D. Hofmann
Nuclear Science and Engineering | Volume 147 | Number 3 | July 2004 | Pages 319-322
Technical Note | doi.org/10.13182/NSE04-A2436
