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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
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ANS standard updated for determining meteorological information at nuclear facilities
Following approval in October from the American National Standards Institute, ANSI/ANS-3.11-2024, Determining Meteorological Information at Nuclear Facilities, was published in late November. This standard provides criteria for gathering, assembling, processing, storing, and disseminating meteorological information at commercial nuclear power plants, U.S. Department of Energy/National Nuclear Security Administration nuclear facilities, and other national or international nuclear facilities.
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A New Approximation for the Neutron Albedo
Ronald C. Brockhoff, J. Kenneth Shultis
Nuclear Science and Engineering | Volume 155 | Number 1 | January 2007 | Pages 1-17
Technical Paper | doi.org/10.13182/NSE07-A2641
Sensitivity and Uncertainty Analysis for Eigenvalue-Difference Responses
Mark L. Williams
Nuclear Science and Engineering | Volume 155 | Number 1 | January 2007 | Pages 18-36
Technical Paper | doi.org/10.13182/NSE06-11
Multigroup Adjoint Transport Solution Using the Method of Cyclic Characteristics
M. Assawaroongruengchot, G. Marleau
Nuclear Science and Engineering | Volume 155 | Number 1 | January 2007 | Pages 37-52
Technical Paper | doi.org/10.13182/NSE07-A2643
Plutonium Denaturing by 238Pu
G. Kessler
Nuclear Science and Engineering | Volume 155 | Number 1 | January 2007 | Pages 53-73
Technical Paper | doi.org/10.13182/NSE07-A2644
Neutron Scattering from an Asymmetric Rotor: 197Au
Alan B. Smith
Nuclear Science and Engineering | Volume 155 | Number 1 | January 2007 | Pages 74-83
Technical Paper | doi.org/10.13182/NSE07-A2645
Improved Evaluations of Neutron-Induced Reactions on Americium Isotopes
P. Talou, T. Kawano, P. G. Young, M. B. Chadwick, R. E. MacFarlane
Nuclear Science and Engineering | Volume 155 | Number 1 | January 2007 | Pages 84-95
Technical Paper | doi.org/10.13182/NSE07-A2646
Radial and Azimuthal 235U Fission and 238U Capture Distributions in BWR UO2 Pins: CASMO-4 and MCNP4C Versus Activation Foil Measurements
K. Macku, F. Jatuff, M. Murphy, M. Plaschy, P. Grimm, O. P. Joneja, R. Chawla
Nuclear Science and Engineering | Volume 155 | Number 1 | January 2007 | Pages 96-101
Technical Paper | doi.org/10.13182/NSE07-A2647
Studies on Effective Atomic Numbers and Electron Densities in Some Commonly Used Solvents
Ashok Kumar, Sukhpal Singh, Gurmel S. Mudahar, Kulwant Singh Thind
Nuclear Science and Engineering | Volume 155 | Number 1 | January 2007 | Pages 102-108
Technical Paper | doi.org/10.13182/NSE07-A2648
Polynomial Chaos Functions and Neutron Diffusion
M. M. R. Williams
Nuclear Science and Engineering | Volume 155 | Number 1 | January 2007 | Pages 109-118
Technical Note | doi.org/10.13182/NSE05-73TN
A New Approach to Spatio-Temporal Calculation of Nuclear Reactor Cores Using Neural Computing
Mehrdad Boroushaki, Mohammad B. Ghofrani, Caro Lucas
Nuclear Science and Engineering | Volume 155 | Number 1 | January 2007 | Pages 119-130
Technical Note | doi.org/10.13182/NSE07-A2650
Monte Carlo Modeling of Delayed Neutrons from Photofission
Enrico Padovani, Maura Monville, Sara A. Pozzi
Nuclear Science and Engineering | Volume 155 | Number 1 | January 2007 | Pages 131-142
Technical Note | doi.org/10.13182/NSE07-A2651
CEARCPG: A Monte Carlo Simulation Code for Normal and Coincidence Prompt-Gamma-Ray Neutron Activation Analysis
Xiaogang Han, Robin P. Gardner, W. A. Metwally
Nuclear Science and Engineering | Volume 155 | Number 1 | January 2007 | Pages 143-153
Computer Code Abstract | doi.org/10.13182/NSE07-A2652
A Hybrid Monte Carlo-Deterministic Method for Global Particle Transport Calculations
Troy L. Becker, Allan B. Wollaber, Edward W. Larsen
Nuclear Science and Engineering | Volume 155 | Number 2 | February 2007 | Pages 155-167
Technical Paper | Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications | doi.org/10.13182/NSE07-A2653
A Lumped Linear-Discontinuous Spatial Discretization Scheme for Triangular-Mesh Sn Calculations in r-z Geometry
Jim E. Morel, Alejandro Gonzalez-Aller, James S. Warsa
Nuclear Science and Engineering | Volume 155 | Number 2 | February 2007 | Pages 168-178
Technical Paper | Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications | doi.org/10.13182/NSE07-A2654
An Efficient Exponential Directional Iterative Differencing Scheme for Three-Dimensional Sn Computations in XYZ Geometry
Glenn E. Sjoden
Nuclear Science and Engineering | Volume 155 | Number 2 | February 2007 | Pages 179-189
Technical Paper | Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications | doi.org/10.13182/NSE07-A2655
A Two-Dimensional Discontinuous Heterogeneous Finite Element Method for Neutron Transport Calculations
Emiliano Masiello, Richard Sanchez
Nuclear Science and Engineering | Volume 155 | Number 2 | February 2007 | Pages 190-207
Technical Paper | Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications | doi.org/10.13182/NSE07-A2656
A Nonlinear Space-Angle Multigrid Acceleration for the Method of Characteristics in Unstructured Meshes
Gabriele Grassi
Nuclear Science and Engineering | Volume 155 | Number 2 | February 2007 | Pages 208-222
Technical Paper | Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications | doi.org/10.13182/NSE07-A2657
An Integral Multidomain DPN Operator as Acceleration Tool for the Method of Characteristics in Unstructured Meshes
Simone Santandrea
Nuclear Science and Engineering | Volume 155 | Number 2 | February 2007 | Pages 223-235
Technical Paper | Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications | doi.org/10.13182/NSE155-223
Solving Three-Dimensional Large-Scale Neutron Transport Problems Using Hybrid Shared-Distributed Parallelism and Characteristics Method
Mohamed Dahmani, Robert Roy
Nuclear Science and Engineering | Volume 155 | Number 2 | February 2007 | Pages 236-249
Technical Paper | Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications | doi.org/10.13182/NSE155-236
MINOS: A Simplified Pn Solver for Core Calculation
Anne-Marie Baudron, Jean-Jacques Lautard
Nuclear Science and Engineering | Volume 155 | Number 2 | February 2007 | Pages 250-263
Technical Paper | Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications | doi.org/10.13182/NSE07-A2660
Component Mode Synthesis Methods for 3-D Heterogeneous Core Calculations Applied to the Mixed-Dual Finite Element Solver MINOS
Pierre Guérin, Anne-Marie Baudron, Jean-Jacques Lautard, Serge Van Criekingen
Nuclear Science and Engineering | Volume 155 | Number 2 | February 2007 | Pages 264-275
Technical Paper | Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications | doi.org/10.13182/NSE07-A2661
Neutron Transport Models of AEGIS: An Advanced Next-Generation Neutronics Design System
Naoki Sugimura, Akio Yamamoto, Tadashi Ushio, Masaaki Mori, Masato Tabuchi, Tomohiro Endo
Nuclear Science and Engineering | Volume 155 | Number 2 | February 2007 | Pages 276-289
Technical Paper | Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications | doi.org/10.13182/NSE155-276
A Quasilinear Implicit Riemann Solver for the Time-Dependent Pn Equations
Ryan G. McClarren, James Paul Holloway, Thomas A. Brunner, Thomas A. Mehlhorn
Nuclear Science and Engineering | Volume 155 | Number 2 | February 2007 | Pages 290-299
Technical Paper | Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications | doi.org/10.13182/NSE07-A2663
The Boundary Source Method with Arbitrary Order Anisotropic Scattering
Gert Van den Eynde, Robert Beauwens, Ernest Mund
Nuclear Science and Engineering | Volume 155 | Number 2 | February 2007 | Pages 300-309
Technical Paper | Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications | doi.org/10.13182/NSE07-A2664
A Review of Legacy and Advanced Self-Shielding Models for Lattice Calculations
Alain Hébert
Nuclear Science and Engineering | Volume 155 | Number 2 | February 2007 | Pages 310-320
Technical Paper | Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications | doi.org/10.13182/NSE06-50
Variational Estimates of Neutron-Induced Gamma Line Leakages and Ratios for Internal Interface Perturbations
Jeffrey A. Favorite
Nuclear Science and Engineering | Volume 155 | Number 2 | February 2007 | Pages 321-329
Technical Paper | Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications | doi.org/10.13182/NSE07-A2666
Description of the LANCER02 Lattice Physics Code for Single-Assembly and Multibundle Analysis
Dave Knott, Erin Wehlage
Nuclear Science and Engineering | Volume 155 | Number 3 | March 2007 | Pages 331-354
Technical Paper | Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications | doi.org/10.13182/NSE155-331
An Analysis of the Extended-Transport Correction with Application to Electron Beam Transport
Clifton R. Drumm, Wesley C. Fan, Leonard Lorence, Jennifer Liscum-Powell
Nuclear Science and Engineering | Volume 155 | Number 3 | March 2007 | Pages 355-366
Technical Paper | Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications | doi.org/10.13182/NSE07-A2668
Development of a Scatter Search Optimization Algorithm for Boiling Water Reactor Fuel Lattice Design
Juan-Luis François, Cecilia Martín-del-Campo, Luis B. Morales, Miguel-Angel Palomera
Nuclear Science and Engineering | Volume 155 | Number 3 | March 2007 | Pages 367-377
Technical Paper | Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications | doi.org/10.13182/NSE07-A2669
Coupled Bundle-Core Design Using Fuel Rod Optimization for Boiling Water Reactors
Matthew A. Jessee, David J. Kropaczek
Nuclear Science and Engineering | Volume 155 | Number 3 | March 2007 | Pages 378-385
Technical Paper | Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications | doi.org/10.13182/NSE07-A2670
Optimized Adaptive Fuzzy Controller of the Water Level of a Pressurized Water Reactor Steam Generator
M. Marseguerra, E. Zio, F. Cadini
Nuclear Science and Engineering | Volume 155 | Number 3 | March 2007 | Pages 386-394
Technical Paper | Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications | doi.org/10.13182/NSE07-A2671
High-Fidelity Light Water Reactor Analysis with the Numerical Nuclear Reactor
David P. Weber, Tanju Sofu, Won Sik Yang, Thomas J. Downar, Justin W. Thomas, Zhaopeng Zhong, Jin Young Cho, Kang Seog Kim, Tae Hyun Chun, Han Gyu Joo, Chang Hyo Kim
Nuclear Science and Engineering | Volume 155 | Number 3 | March 2007 | Pages 395-408
Technical Paper | Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications | doi.org/10.13182/NSE07-A2672
Use of 3D-VAR and Kalman Filter Approaches for Neutronic State and Parameter Estimation in Nuclear Reactors
Sébastien Massart, Samuel Buis, Patrick Erhard, Guillaume Gacon
Nuclear Science and Engineering | Volume 155 | Number 3 | March 2007 | Pages 409-424
Technical Paper | Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications | doi.org/10.13182/NSE07-A2673
Theory of Neutron Noise in a Temporally Fluctuating Multiplying Medium
Lénárd Pál, Imre Pázsit
Nuclear Science and Engineering | Volume 155 | Number 3 | March 2007 | Pages 425-440
Technical Paper | Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications | doi.org/10.13182/NSE07-A2674
Atomic Mix Synthetic Acceleration of Dose Computations in Binary Statistical Media
Anil K. Prinja, Erin D. Fichtl
Nuclear Science and Engineering | Volume 155 | Number 3 | March 2007 | Pages 441-448
Technical Paper | Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications | doi.org/10.13182/NSE07-A2675
Investigation of the Impact of Simple Carbon Interstitial Formations on Thermal Neutron Scattering in Graphite
Ayman I. Hawari, Iyad I. Al-Qasir, Abderrafi M. Ougouag
Nuclear Science and Engineering | Volume 155 | Number 3 | March 2007 | Pages 449-462
Technical Paper | Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications | doi.org/10.13182/NSE07-A2676
Effect of Mass and Activity Heterogeneities on the Activity Measurement of Large Packages of Radioactive Waste
Bernard Rottner
Nuclear Science and Engineering | Volume 155 | Number 3 | March 2007 | Pages 463-474
Technical Paper | Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications | doi.org/10.13182/NSE07-A2677
Interactions Between Fluid-Dynamics and Neutronic Phenomena in the Physics of Molten-Salt Systems
S. Dulla, P. Ravetto
Nuclear Science and Engineering | Volume 155 | Number 3 | March 2007 | Pages 475-488
Technical Paper | Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications | doi.org/10.13182/NSE07-A2678
Turbulent Heat Flux and Temperature Variance Dissipation Rate in Natural Convection in Lead-Bismuth
I. Otic, G. Grötzbach
Nuclear Science and Engineering | Volume 155 | Number 3 | March 2007 | Pages 489-496
Technical Paper | Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications | doi.org/10.13182/NSE07-A2679
Some Measure Theoretic Issues in Probabilistic Dynamics
Tunc Aldemir
Nuclear Science and Engineering | Volume 155 | Number 3 | March 2007 | Pages 497-507
Technical Note | Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications | doi.org/10.13182/NSE07-A2680
