A Monte Carlo Code for Radiation Damage by NeutronsKUMAR, V; NAGENDRA SINGH RAGHAW; PALSANIA, H. S et al.Nuclear science and engineering. 2012, Vol 172, Num 2, pp 151-163, issn 0029-5639, 13 p.Article

An Efficient Multiproblem Strategy for Accurate Solutions of Linear Particle Transport Problems in Spherical GeometryPICCA, Paolo; FURFARO, Roberto; GANAPOL, Barry D et al.Nuclear science and engineering. 2012, Vol 170, Num 2, pp 103-124, issn 0029-5639, 22 p.Article

Chaotic Data Encryption for Long-Distance Monitoring of Nuclear ReactorsABLAY, Günyaz; EMRE KOKSAL, Can; ALDEMIR, Tunc et al.Nuclear science and engineering. 2012, Vol 170, Num 1, pp 27-43, issn 0029-5639, 17 p.Article

Critical Heat Flux in TRIGA-Fueled Reactors Cooled by Natural ConvectionAVERY, Michael; JUN YANG; ANDERSON, Mark et al.Nuclear science and engineering. 2012, Vol 172, Num 3, pp 249-258, issn 0029-5639, 10 p.Article

Evaluation and Adjustment of the Neutron-Induced Reactions of ^63,65CuROCHMAN, D; KONING, A. J.Nuclear science and engineering. 2012, Vol 170, Num 3, pp 265-279, issn 0029-5639, 15 p.Article

Explicit Treatment of Thermal Motion in Continuous-Energy Monte Carlo Tracking RoutinesVIITANEN, Tuomas; LEPPANEN, Jaakko.Nuclear science and engineering. 2012, Vol 171, Num 2, pp 165-173, issn 0029-5639, 9 p.Article

Parallel Fission Bank Algorithms in Monte Carlo Criticality CalculationsROMANO, Paul K; FORGET, Benoit.Nuclear science and engineering. 2012, Vol 170, Num 2, pp 125-135, issn 0029-5639, 11 p.Article

Peelle's Pertinent Puzzle: A Fake Due to Improper AnalysisNEUDECKER, Denise; FRÜHWIRTH, Rudolf; LEEB, Helmut et al.Nuclear science and engineering. 2012, Vol 170, Num 1, pp 54-60, issn 0029-5639, 7 p.Article

Simulation of Neutron Pulse Height Distributions with a Response Matrix MethodPRASAD, S; CLARKE, S. D; POZZI, S. A et al.Nuclear science and engineering. 2012, Vol 172, Num 1, pp 78-86, issn 0029-5639, 9 p.Article

A Five-Year Core for a Small Modular Light Water ReactorSOLDATOV, Alexey; PALMER, Todd S.Nuclear science and engineering. 2011, Vol 167, Num 1, pp 77-90, issn 0029-5639, 14 p.Article

Adjoint-Weighted Tallies for k-Eigenvalue Calculations with Continuous-Energy Monte CarloKIEDROWSKI, Brian C; BROWN, Forrest B; WILSON, Paul P. H et al.Nuclear science and engineering. 2011, Vol 168, Num 3, pp 226-241, issn 0029-5639, 16 p.Article

An Adaptive Energy Mesh Constructor for Multigroup Library Generation for Transport CodesMOSCA, Pietro; MOUNIER, Claude; SANCHEZ, Richard et al.Nuclear science and engineering. 2011, Vol 167, Num 1, pp 40-60, issn 0029-5639, 21 p.Article

Calculation and Analysis of Neutron-Induced Reactions on ⁵⁹Co up to 200 MeVYUE ZHANG; YINLU HAN; HAIRUI GUO et al.Nuclear science and engineering. 2011, Vol 168, Num 2, pp 151-163, issn 0029-5639, 13 p.Article

Comparison of Different Numerical Methods Used in Delayed Neutron Decay Parameters EstimationJINKAI WANG; REECE, Warren D.Nuclear science and engineering. 2011, Vol 167, Num 2, pp 154-164, issn 0029-5639, 11 p.Article

Deterministic and Stochastic Evaluation of Criticality Excursion Power BurstsRAMSEY, Scott D; HUTCHENS, Gregory J.Nuclear science and engineering. 2011, Vol 168, Num 3, pp 265-277, issn 0029-5639, 13 p.Article

Geometric Convergence of Adaptive Monte Carlo Algorithms for Radiative Transport Problems Based on Importance Sampling MethodsKONG, Rong; SPANIER, Jerome.Nuclear science and engineering. 2011, Vol 168, Num 3, pp 197-225, issn 0029-5639, 29 p.Article

How to Randomly Evaluate Nuclear Data: A New Data Adjustment Method Applied to ²³⁹PuROCHMAN, D; KONING, A. J.Nuclear science and engineering. 2011, Vol 169, Num 1, pp 68-80, issn 0029-5639, 13 p.Article

Many-Group Cross-Section Adjustment Techniques for Boiling Water Reactor Adaptive SimulationJESSEE, M. A; TURINSKY, P. J; ABDEL-KHALIK, H. S et al.Nuclear science and engineering. 2011, Vol 169, Num 1, pp 40-55, issn 0029-5639, 16 p.Article

Monte Carlo Application of Arnoldi's Method for Acceleration of Eigenvalue and Fission Source ConvergenceLLOYD CONLIN, Jeremy; HOLLOWAY, James Paul.Nuclear science and engineering. 2011, Vol 169, Num 2, pp 168-177, issn 0029-5639, 10 p.Article

Multilevel Quasidiffusion Methods for Solving Multigroup Neutron Transport k-Eigenvalue Problems in One-Dimensional Slab GeometryANISTRATOV, Dmitriy Y; GOL'DIN, Vladimir Ya.Nuclear science and engineering. 2011, Vol 169, Num 2, pp 111-132, issn 0029-5639, 22 p.Article

Neutronic Feasibility Assessment of Liquid Salt―Cooled Pebble Bed ReactorsFRATONI, Massimiliano; GREENSPAN, Ehud.Nuclear science and engineering. 2011, Vol 168, Num 1, pp 1-22, issn 0029-5639, 22 p.Article

On the Construction of Galerkin Angular QuadraturesSANCHEZ, Richard; RAGUSA, Jean.Nuclear science and engineering. 2011, Vol 169, Num 2, pp 133-154, issn 0029-5639, 22 p.Article

Rational Approximations to the Matrix Exponential in Burnup CalculationsPUSA, Maria.Nuclear science and engineering. 2011, Vol 169, Num 2, pp 155-167, issn 0029-5639, 13 p.Article

Sensors for Next-Generation Nuclear Plants: Fiber-Optic and WirelessHASHEMIAN, H. M; BEAN, Wendell C.Nuclear science and engineering. 2011, Vol 169, Num 3, pp 262-278, issn 0029-5639, 17 p.Article

Using Core Symmetry in Monte Carlo Dominance Ratio CalculationsGORODKOV, Sergey S.Nuclear science and engineering. 2011, Vol 168, Num 3, pp 242-247, issn 0029-5639, 6 p.Article