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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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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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Zero-Variance Monte Carlo Schemes Revisited
J. Eduard Hoogenboom
Nuclear Science and Engineering | Volume 160 | Number 1 | September 2008 | Pages 1-22
Technical Paper | doi.org/10.13182/NSE160-01
A Linear Surface Characteristics Approximation for Neutron Transport in Unstructured Meshes
S. Santandrea, R. Sanchez, P. Mosca
Nuclear Science and Engineering | Volume 160 | Number 1 | September 2008 | Pages 23-40
Technical Paper | doi.org/10.13182/NSE07-69
Generalized Energy Condensation Theory
Farzad Rahnema, Steven Douglass, Benoit Forget
Nuclear Science and Engineering | Volume 160 | Number 1 | September 2008 | Pages 41-58
Technical Paper | doi.org/10.13182/NSE160-41
Optimization of One-Pass Transuranic Deep Burn in a Modular Helium Reactor
Yonghee Kim, Francesco Venneri
Nuclear Science and Engineering | Volume 160 | Number 1 | September 2008 | Pages 59-74
Technical Paper | doi.org/10.13182/NSE160-59
Corrosion of Materials by Liquid NaK Coolant in a Nuclear Power System
J. Zhang, R. Kapernick, T. F. Marcille
Nuclear Science and Engineering | Volume 160 | Number 1 | September 2008 | Pages 75-97
Technical Paper | doi.org/10.13182/NSE160-75
The Impact of Power Uprate on the Corrosion Mitigation Effectiveness of Hydrogen Water Chemistry in Boiling Water Reactors
Tsung-Kuang Yeh, Mei-Ya Wang
Nuclear Science and Engineering | Volume 160 | Number 1 | September 2008 | Pages 98-107
Technical Paper | doi.org/10.13182/NSE07-38
Assessment and Propagation of the 237Np Nuclear Data Uncertainties in Integral Calculations by Monte Carlo Techniques
Gilles Noguere, David Bernard, Cyrille De Saint Jean, Bertrand Iooss, Frank Gunsing, Katsuhei Kobayashi, Said F. Mughabghab, Peter Siegler
Nuclear Science and Engineering | Volume 160 | Number 1 | September 2008 | Pages 108-122
Technical Paper | doi.org/10.13182/NSE160-108
Measurement of Differential Cross Section for the 64Zn(n,)61Ni Reaction at 2.54, 4.00, and 5.50 MeV
Guohui Zhang, Jiaguo Zhang, Rongtai Cao, Li'an Guo, Jinxiang Chen, Yu. M. Gledenov, M. V. Sedysheva, G. Khuukhenkhuu, P. J. Szalanski
Nuclear Science and Engineering | Volume 160 | Number 1 | September 2008 | Pages 123-128
Technical Paper | doi.org/10.13182/NSE160-123
Verification and Determination of the Decay Heat in Spent PWR Fuel by Means of Gamma Scanning
Otasowie Osifo, Staffan Jacobsson Svärd, Ane Håkansson, Christofer Willman, Anders Bäcklin, Tobias Lundqvist
Nuclear Science and Engineering | Volume 160 | Number 1 | September 2008 | Pages 129-143
Technical Note | doi.org/10.13182/NSE160-129TN
The Systematic Behavior of the Spontaneous Fission Branching Ratios of Even-Z Isotopes
Yigal Ronen
Nuclear Science and Engineering | Volume 160 | Number 1 | September 2008 | Pages 144-147
Technical Note | doi.org/10.13182/NSE160-144TN
R-Matrix Analysis of 232Th Neutron Transmissions and Capture Cross Sections in the Energy Range Thermal to 4 keV
H. Derrien, L. C. Leal, N. M. Larson
Nuclear Science and Engineering | Volume 160 | Number 2 | October 2008 | Pages 149-167
Technical Paper | doi.org/10.13182/NSE160-149
Evaluation of Neutron Cross Sections for a Complete Set of Nd Isotopes
Hyeong Il Kim, M. Herman, S. F. Mughabghab, P. Oblozinský, D. Rochman, Young-Ouk Lee
Nuclear Science and Engineering | Volume 160 | Number 2 | October 2008 | Pages 168-189
Technical Paper | doi.org/10.13182/NSE160-168
Reevaluation of Prompt Neutron Emission Multiplicity Distributions for Spontaneous Fission
P. Santi, M. Miller
Nuclear Science and Engineering | Volume 160 | Number 2 | October 2008 | Pages 190-199
Technical Paper | doi.org/10.13182/NSE07-85
Measurement of the 236U(n,f) Cross Section in the Neutron Energy Range from 0.5 eV up to 25 keV
C. Wagemans, L. De Smet, S. Vermote, J. Heyse, J. Van Gils, O. Serot
Nuclear Science and Engineering | Volume 160 | Number 2 | October 2008 | Pages 200-206
Technical Paper | doi.org/10.13182/NSE160-200
An Attempt to Improve Empirical Formulas for (n,p) and (n,) Cross Sections
M. H. Hadizadeh, S. M. Grimes
Nuclear Science and Engineering | Volume 160 | Number 2 | October 2008 | Pages 207-216
Technical Paper | doi.org/10.13182/NSE160-207
Critical Mass and Subcritical Experiments Interlaced with Nb-1Zr, Re, Mo, Ta-2.5W Fueled with Highly Enriched Uranium in Support of the Prometheus Project
David J. Loaiza, Daniel Gehman, Rene Sanchez, David Hayes, Michael Zerkle
Nuclear Science and Engineering | Volume 160 | Number 2 | October 2008 | Pages 217-231
Technical Paper | doi.org/10.13182/NSE160-217
Analysis of the PROFIL and PROFIL-2 Sample Irradiation Experiments in Phénix for JEFF-3.1 Nuclear Data Validation
J. Tommasi, G. Noguere
Nuclear Science and Engineering | Volume 160 | Number 2 | October 2008 | Pages 232-241
Technical Paper | doi.org/10.13182/NSE160-232
Stationarity Diagnostics with Relative Entropy and Wilcoxon Signed Rank in Iterated-Source Monte Carlo Methods
Taro Ueki
Nuclear Science and Engineering | Volume 160 | Number 2 | October 2008 | Pages 242-252
Technical Paper | doi.org/10.13182/NSE160-242
Resonance Absorption in Materials with Randomly Dispersed Grains
M. M. R. Williams
Nuclear Science and Engineering | Volume 160 | Number 2 | October 2008 | Pages 253-260
Technical Paper | doi.org/10.13182/NSE160-253
Scattering Reduction of the Double-Heterogeneity Treatment in Dragon
A. Hébert
Nuclear Science and Engineering | Volume 160 | Number 2 | October 2008 | Pages 261-266
Technical Note | doi.org/10.13182/NSE160-261TN
A Quantitative Theory of Angular Truncation Errors in Three-Dimensional SN Calculations
Edward W. Larsen, Allan B. Wollaber
Nuclear Science and Engineering | Volume 160 | Number 3 | November 2008 | Pages 267-283
Technical Paper | doi.org/10.13182/NSE160-267
Moments-Based Versions of the Spherical Geometry Method of Tubes in Thick, Diffusive Regions
Michael E. Rising, Todd S. Palmer
Nuclear Science and Engineering | Volume 160 | Number 3 | November 2008 | Pages 284-301
Technical Paper | doi.org/10.13182/NSE160-284
Decay Ratio Estimation of BWR Signals Based on Wavelet Ridges
Alfonso Prieto-Guerrero, Gilberto Espinosa-Paredes
Nuclear Science and Engineering | Volume 160 | Number 3 | November 2008 | Pages 302-317
Technical Paper | doi.org/10.13182/NSE160-302
Best-Estimate Evaluation of Large-Break Loss-of-Coolant Accident for Advanced Natural Circulation Nuclear Reactor
Vivek Bhasin, A. Srivastava, R. Rastogi, H. G. Lele, K. K. Vaze, A. K. Ghosh, H. S. Kushwaha
Nuclear Science and Engineering | Volume 160 | Number 3 | November 2008 | Pages 318-333
Technical Paper | doi.org/10.13182/NSE160-318
Calculation and Analysis of the Complete Set of Neutron Data for 46,47,48,49,50,natTi in the Energy Region 0.3 to 20 MeV
Ruirui Xu, Haicheng Wu, Zhigang Ge, Yinlu Han, Tingjin Liu
Nuclear Science and Engineering | Volume 160 | Number 3 | November 2008 | Pages 334-348
Technical Paper | doi.org/10.13182/NSE160-334
Determination of Neutron Scattering Cross Sections with High Precision at PTB in the Energy Region 8 to 14 MeV
D. Schmidt
Nuclear Science and Engineering | Volume 160 | Number 3 | November 2008 | Pages 349-362
Technical Paper | doi.org/10.13182/NSE160-349
Measurement of the Photonuclear (,n) Reaction Cross Section for 129I Using Bremsstrahlung Photons
Abul Kalam Md. Lutfor Rahman, Shigeyuki Kuwabara, Kunio Kato, Hidehiko Arima, Nobuhiro Shigyo, Kenji Ishibashi, Jun-ichi Hori, Ken Nakajima, Tetsuo Goto, Mikio Uematsu
Nuclear Science and Engineering | Volume 160 | Number 3 | November 2008 | Pages 363-369
Technical Paper | doi.org/10.13182/NSE160-363
Sensitivity of Photoneutron Production to Perturbations in Cross-Section Data
S. D. Clarke, S. A. Pozzi, E. Padovani, T. J. Downar
Nuclear Science and Engineering | Volume 160 | Number 3 | November 2008 | Pages 370-377
Technical Paper | doi.org/10.13182/NSE160-370
Preparation and Characterization of Pu0.5Am0.5O2-x-MgO Ceramic/Ceramic Composites
A. Jankowiak, F. Jorion, C. Maillard, L. Donnet
Nuclear Science and Engineering | Volume 160 | Number 3 | November 2008 | Pages 378-384
Technical Paper | doi.org/10.13182/NSE160-378
A Continuous Finite Element-Based, Discontinuous Finite Element Method for SN Transport
James S. Warsa
Nuclear Science and Engineering | Volume 160 | Number 3 | November 2008 | Pages 385-400
Technical Note | doi.org/10.13182/NSE160-385TN
