ANS / Publications / Journals / Nuclear Science and Engineering

Zero-Variance Monte Carlo Schemes Revisited

J. Eduard Hoogenboom

Nuclear Science and Engineering / Volume 160 / Number 1 / September 2008 / Pages 1-22

Technical Paper / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.13182/NSE160-261TN

A Quantitative Theory of Angular Truncation Errors in Three-Dimensional S_N Calculations

Edward W. Larsen, Allan B. Wollaber

Nuclear Science and Engineering / Volume 160 / Number 3 / November 2008 / Pages 267-283

Technical Paper / dx.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 / dx.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 / dx.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 / dx.doi.org/10.13182/NSE160-318

Calculation and Analysis of the Complete Set of Neutron Data for ^{46,47,48,49,50,nat}Ti 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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.13182/NSE160-370

Preparation and Characterization of Pu_0.5Am_0.5O_2-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 / dx.doi.org/10.13182/NSE160-378

A Continuous Finite Element-Based, Discontinuous Finite Element Method for S_N Transport

James S. Warsa

Nuclear Science and Engineering / Volume 160 / Number 3 / November 2008 / Pages 385-400

Technical Note / dx.doi.org/10.13182/NSE160-385TN