ANS / Publications / Journals / Nuclear Science and Engineering

Second-Order Adjoint Sensitivity and Uncertainty Analysis of a Heat Transport Benchmark Problem—I: Analytical Results

Dan G. Cacuci

Nuclear Science and Engineering / Volume 183 / Number 1 / May 2016 / Pages 1-21

Technical Paper / dx.doi.org/10.13182/NSE15-81

Second-Order Adjoint Sensitivity and Uncertainty Analysis of a Heat Transport Benchmark Problem—II: Computational Results Using G4M Reactor Thermal-Hydraulic Parameters

Dan G. Cacuci, Milica Ilic, Madalina C. Badea, Ruixian Fang

Nuclear Science and Engineering / Volume 183 / Number 1 / May 2016 / Pages 22-38

Technical Paper / dx.doi.org/10.13182/NSE15-80

Discontinuity Factors for Simplified P3 Theory

Akio Yamamoto, Tatsuya Sakamoto, Tomohiro Endo

Nuclear Science and Engineering / Volume 183 / Number 1 / May 2016 / Pages 39-51

Technical Paper / dx.doi.org/10.13182/NSE15-102

First Flight Escape Probability and Uncollided Flux of Nuclear Particles in Convex Bodies with Spherical Symmetry

P. Chiovaro, P. A. Di Maio, S. Garitta, E. Vallone, G. Vella

Nuclear Science and Engineering / Volume 183 / Number 1 / May 2016 / Pages 52-64

Technical Paper / dx.doi.org/10.13182/NSE15-68

Improving the Accuracy of the Chebyshev Rational Approximation Method Using Substeps

Aarno Isotalo, Maria Pusa

Nuclear Science and Engineering / Volume 183 / Number 1 / May 2016 / Pages 65-77

Technical Paper / dx.doi.org/10.13182/NSE15-67

Emulation-Based Calibration for Parameters in Parameterized Phonon Spectrum of ZrH_x in TRIGA Reactor Simulations

Weixiong Zheng, Ryan G. McClarren

Nuclear Science and Engineering / Volume 183 / Number 1 / May 2016 / Pages 78-95

Technical Paper / dx.doi.org/10.13182/NSE15-48

Accuracy of Reactor Physics Parameters in Thorium-Loaded Accelerator-Driven System Experiments at Kyoto University Critical Assembly

Masao Yamanaka, Cheol Ho Pyeon, Takahiro Yagi, Tsuyoshi Misawa

Nuclear Science and Engineering / Volume 183 / Number 1 / May 2016 / Pages 96-106

Technical Paper / dx.doi.org/10.13182/NSE15-51

Code Development and Target Station Design for Chinese Accelerator-Driven System Project

Han-Jie Cai, Fen Fu, Jian-Yang Li, Ya-Ling Zhang, Xun-Chao Zhang, Xue-Song Yan, Zhi-Lei Zhang, Jian-Ya Xv, Mei-Ling Qi, Lei Yang

Nuclear Science and Engineering / Volume 183 / Number 1 / May 2016 / Pages 107-115

Technical Paper / dx.doi.org/10.13182/NSE15-59

Burst Wait-Times in the Caliban Reactor Using the Gamma Probability Distribution Function

M. M. R. Williams

Nuclear Science and Engineering / Volume 183 / Number 1 / May 2016 / Pages 116-125

Technical Paper / dx.doi.org/10.13182/NSE15-62

Arbitrary Lagrangian Eulerian Formulation for Sloshing Tank Analysis in Nuclear Engineering

M. Souli, A. V. Kultsep, E. Al-Bahkali, C. C. Pain, M. Moatamedi

Nuclear Science and Engineering / Volume 183 / Number 1 / May 2016 / Pages 126-134

Technical Paper / dx.doi.org/10.13182/NSE15-63

Photonuclear Benchmarks of C, Al, Cu, Ta, Pb, and U from the ENDF/B-VII Cross-Section Library ENDF7U Using MCNPX

Matthias Frankl, Rafael Macián-Juan

Nuclear Science and Engineering / Volume 183 / Number 1 / May 2016 / Pages 135-142

Technical Paper / dx.doi.org/10.13182/NSE15-47

Measuring the Neutron Signature of the t→d+n Triton Breakup Reaction and the Angle-Dependent Differential Cross Section of ⁶Li(n,t)⁴He at 2.32 MeV

M. Drosg

Nuclear Science and Engineering / Volume 183 / Number 1 / May 2016 / Pages 143-148

Technical Note / dx.doi.org/10.13182/NSE15-65

Analysis of Multiple TRIGA-Based Molybdenum Production Reactor Cores Using a New Low-Enriched Uranium Target as Fuel

Andrew J. Hummel, Todd S. Palmer

Nuclear Science and Engineering / Volume 183 / Number 1 / May 2016 / Pages 149-159

Technical Note / dx.doi.org/10.13182/NSE15-37

A Method for the Adaptive Selection of Angular Flux Expansion Orders in the Coarse Mesh Radiation Transport (COMET) Method

Kyle Remley, Farzad Rahnema

Nuclear Science and Engineering / Volume 183 / Number 2 / June 2016 / Pages 161-172

Technical Paper / dx.doi.org/10.13182/NSE15-97

Optimization Algorithms for Multigroup Energy Structures

M. J. Fleming, L. W. G. Morgan, E. Shwageraus

Nuclear Science and Engineering / Volume 183 / Number 2 / June 2016 / Pages 173-184

Technical Paper / dx.doi.org/10.13182/NSE15-55

A New Nodal Expansion Method with High-Order Moments for the Reduction of Numerical Oscillation in Convection-Diffusion Problems

Xiafeng Zhou, Jiong Guo, Fu Li

Nuclear Science and Engineering / Volume 183 / Number 2 / June 2016 / Pages 185-195

Technical Paper / dx.doi.org/10.13182/NSE15-95

Convergence Analysis for the Method of Characteristics in Unstructured Meshes

Richard Sanchez, Simone Santandrea

Nuclear Science and Engineering / Volume 183 / Number 2 / June 2016 / Pages 196-213

Technical Paper / dx.doi.org/10.13182/NSE15-78

Stochastic Analog Neutron Transport with TRIPOLI-4 and FREYA: Bayesian Uncertainty Quantification for Neutron Multiplicity Counting

J. M. Verbeke, O. Petit

Nuclear Science and Engineering / Volume 183 / Number 2 / June 2016 / Pages 214-228

Technical Paper / dx.doi.org/10.13182/NSE15-82

Nuclear Reactor Transient Analysis by Continuous-Energy Monte Carlo Calculation Based on Predictor-Corrector Quasi-Static Method

YuGwon Jo, Bumhee Cho, Nam Zin Cho

Nuclear Science and Engineering / Volume 183 / Number 2 / June 2016 / Pages 229-246

Technical Paper / dx.doi.org/10.13182/NSE15-100

Assessment of the Online Core Power Measured by a Boron Chamber in a Pool-Type Research Reactor Using a Nonlinear Calibration Model

L. Pantera, Y. Garnier, F. Jeury

Nuclear Science and Engineering / Volume 183 / Number 2 / June 2016 / Pages 247-260

Technical Paper / dx.doi.org/10.13182/NSE15-77

Sensitivity of Cross Sections to Isotopic Densities for Subgroup Resonance Self-Shielding Calculations

M. Dion, G. Marleau

Nuclear Science and Engineering / Volume 183 / Number 2 / June 2016 / Pages 261-274

Technical Paper / dx.doi.org/10.13182/NSE15-60

Preequilibrium Models for ⁶³Cu(n, xp) Reaction in Neutrons at 9, 11, 14.8, and 15 MeV Using the EMPIRE 3.2 Code

L. Yettou

Nuclear Science and Engineering / Volume 183 / Number 2 / June 2016 / Pages 275-285

Technical Paper / dx.doi.org/10.13182/NSE15-73

Neutron Total Cross Sections and Resonance Parameters of Palladium

Taofeng Wang, Guinyun Kim, Young Do Oh, Moo-Hyun Cho, In Soo Ko, Won Namkung

Nuclear Science and Engineering / Volume 183 / Number 2 / June 2016 / Pages 286-297

Technical Paper / dx.doi.org/10.13182/NSE15-64

Double-Differential Angle-Dependent Three-Body Neutron Production Cross Sections of the Reaction ²H(t,n)X+Y at Triton Energies Between 5.97 and 16.41 MeV

M. Drosg, G. Haouat, D. M. Drake

Nuclear Science and Engineering / Volume 183 / Number 2 / June 2016 / Pages 298-303

Technical Note / dx.doi.org/10.13182/NSE15-118

Predictive Modeling Applied to a Spent Fuel Dissolver Model—I: Adjoint Sensitivity Analysis

James J. Peltz, Dan G. Cacuci

Nuclear Science and Engineering / Volume 183 / Number 3 / July 2016 / Pages 305-331

Technical Paper / dx.doi.org/10.13182/NSE15-98

Predictive Modeling Applied to a Spent Fuel Dissolver Model—II: Uncertainty Quantification and Reduction

James J. Peltz, Dan G. Cacuci, Aurelian F. Badea, Madalina C. Badea

Nuclear Science and Engineering / Volume 183 / Number 3 / July 2016 / Pages 332-346

Technical Paper / dx.doi.org/10.13182/NSE15-99

Resonance Parameter Adjustment Based on Integral Experiments

Vladimir Sobes, Luiz Leal, Goran Arbanas, Benoit Forget

Nuclear Science and Engineering / Volume 183 / Number 3 / July 2016 / Pages 347-355

Technical Paper / dx.doi.org/10.13182/NSE15-50

A Preliminary Examination of the Application of Unscented Transformation Technique to Error Propagation in Nonlinear Cases of Nuclear Data Science

Harshavardhan Kadvekar, Sana Khan, Sangeetha Prasanna Ram, Jayalekshmi Nair, S. Ganesan

Nuclear Science and Engineering / Volume 183 / Number 3 / July 2016 / Pages 356-370

Technical Paper / dx.doi.org/10.13182/NSE15-103

Total Uncertainty Analysis for PWR Assembly Based on the Statistical Sampling Method

Tiejun Zu, Chenghui Wan, Liangzhi Cao, Hongchun Wu, Wei Shen

Nuclear Science and Engineering / Volume 183 / Number 3 / July 2016 / Pages 371-386

Technical Paper / dx.doi.org/10.13182/NSE15-96

Improvement of Code Behavior in a Design of Experiments by Metamodeling

François Bachoc, Karim Ammar, Jean-Marc Martinez

Nuclear Science and Engineering / Volume 183 / Number 3 / July 2016 / Pages 387-406

Technical Paper / dx.doi.org/10.13182/NSE15-108

Semianalytical Approximation and Lookup Table of Neutron Escape Probability from Rectangular Cell for Collision Probability Method

T. Matsumura

Nuclear Science and Engineering / Volume 183 / Number 3 / July 2016 / Pages 407-420

Technical Paper / dx.doi.org/10.13182/NSE15-86

Calculating Time-Integral Quantities in Depletion Calculations

Aarno Isotalo

Nuclear Science and Engineering / Volume 183 / Number 3 / July 2016 / Pages 421-429

Technical Paper / dx.doi.org/10.13182/NSE15-119