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Volume 194

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Number 1

Three-Dimensional Pin-Resolved Transient Diffusion Analysis of PWR Core by the Hybrid Coarse-Mesh Finite Difference Algorithm

Jaeha Kim, Yonghee Kim

Nuclear Science and Engineering / Volume 194 / Number 1 / January 2020 / Pages 1-13

Technical Paper / dx.doi.org/10.1080/00295639.2019.1642016

Deterministic Truncation of the Monte Carlo Transport Solution for Reactor Eigenvalue and Pinwise Power Distribution

Inhyung Kim, HyeonTae Kim, Yonghee Kim

Nuclear Science and Engineering / Volume 194 / Number 1 / January 2020 / Pages 14-31

Technical Paper / dx.doi.org/10.1080/00295639.2019.1654815

Development of the Assembly-Level Monte Carlo Neutron Transport Code M3C for Reactor Physics Calculations

Anek Kumar, Umasankari Kannan, S. Ganesan

Nuclear Science and Engineering / Volume 194 / Number 1 / January 2020 / Pages 32-43

Technical Paper / dx.doi.org/10.1080/00295639.2019.1645502

Generation of Multigroup Cross Sections with an Improved Monte Carlo Algorithm

Li Cheng, Bin Zhong, Huayun Shen, Zehua Hu, Baiwen Li

Nuclear Science and Engineering / Volume 194 / Number 1 / January 2020 / Pages 44-55

Technical Paper / dx.doi.org/10.1080/00295639.2019.1650520

Derivation of the Two-Exponential Probability Density Function for Rossi-Alpha Measurements of Reflected Assemblies and Validation for the Special Case of Shielded Measurements

Michael Y. Hua, Jesson D. Hutchinson, George E. McKenzie, Tony H. Shin, Shaun D. Clarke, Sara A. Pozzi

Nuclear Science and Engineering / Volume 194 / Number 1 / January 2020 / Pages 56-68

Technical Paper / dx.doi.org/10.1080/00295639.2019.1654327

Effects of Gamma Irradiation on the Morphological, Physical, and Thermal Properties of B4C/CF/PI/AA6061 Hybrid Composite Laminates

Xuelong Fu, Jie Tao, Dunwen Zuo

Nuclear Science and Engineering / Volume 194 / Number 1 / January 2020 / Pages 69-83

Technical Paper / dx.doi.org/10.1080/00295639.2019.1654328

ADDENDUM: Approximate Methods for Inverting Generating Functions from the Pál-Bell Equations for Low Source Problems

M. M. R. Williams

Nuclear Science and Engineering / Volume 194 / Number 1 / January 2020 / Pages 84-85

Addendum / dx.doi.org/10.1080/00295639.2019.1687193

Number 2

Monte Carlo Solution of k-Eigenvalue Problem Using Subspace Iteration Method

Anurag Gupta, R. S. Modak

Nuclear Science and Engineering / Volume 194 / Number 2 / February 2020 / Pages 87-103

Technical Paper / dx.doi.org/10.1080/00295639.2019.1668655

A Transport-Free Method for Predicting the Post-Depletion Spatial Neutron Flux Distribution

Andrew E. Johnson, Dan Kotlyar

Nuclear Science and Engineering / Volume 194 / Number 2 / February 2020 / Pages 120-137

Technical Paper / dx.doi.org/10.1080/00295639.2019.1661171

Systematic Measurements and Analyses for Lead Void Reactivity Worth in a Plutonium Core and Two Uranium Cores with Different Enrichments

M. Fukushima, J. Goda, A. Oizumi, J. Bounds, T. Cutler, T. Grove, D. Hayes, J. Hutchinson, G. McKenzie, A. McSpaden, R. Sanchez, J. Walker, K. Tsujimoto

Nuclear Science and Engineering / Volume 194 / Number 2 / February 2020 / Pages 138-153

Technical Paper / dx.doi.org/10.1080/00295639.2019.1663089

Simulation of the Nondestructive Assay of 237Np Using Active Neutron Multiplicity Counting

Michael Y. Hua, Braden Goddard, Cody Lloyd, Evan C. Leppink, Sara A. Abraham, Jordan D. Noey, Shaun D. Clarke, Sara A. Pozzi

Nuclear Science and Engineering / Volume 194 / Number 2 / February 2020 / Pages 154-162

Technical Paper / dx.doi.org/10.1080/00295639.2019.1654329

Preliminary Study of a Prismatic-Core Advanced High-Temperature Reactor Fuel Using Homogenization Double-Heterogeneous Method

Mohammad Alrwashdeh, Saeed A. Alameri, Ahmed K. Alkaabi

Nuclear Science and Engineering / Volume 194 / Number 2 / February 2020 / Pages 163-167

Technical Paper / dx.doi.org/10.1080/00295639.2019.1672511

Number 3

Review of Progress in Coated Fuel Particle Performance Analysis

Nairi Baghdasaryan, Tomasz Kozlowski

Nuclear Science and Engineering / Volume 194 / Number 3 / March 2020 / Pages 169-180

Critical Review / dx.doi.org/10.1080/00295639.2019.1686882

Radiation Dose Analysis in Criticality Accident of Fuel Debris in Water

Kodai Fukuda, Delgersaikhan Tuya, Jun Nishiyama, Toru Obara

Nuclear Science and Engineering / Volume 194 / Number 3 / March 2020 / Pages 181-189

Technical Paper / dx.doi.org/10.1080/00295639.2019.1665459

Adaptive Reweighted Variance Estimation for Monte Carlo Eigenvalue Simulations

Lei Jin, Kaushik Banerjee

Nuclear Science and Engineering / Volume 194 / Number 3 / March 2020 / Pages 190-206

Technical Paper / dx.doi.org/10.1080/00295639.2019.1678104

Spectroscopy of High-Intensity Bremsstrahlung Using Compton Recoiled Electrons

C. V. Midhun, M. M. Musthafa, Shaima Akbar, Swapna Lilly Cyriac, S. Sajeev, Antony Joseph, K. C. Jagadeesan, S. V. Suryanarayana, S. Ganesan

Nuclear Science and Engineering / Volume 194 / Number 3 / March 2020 / Pages 207-212

Technical Paper / dx.doi.org/10.1080/00295639.2019.1681210

Ensuring Criticality Safety of vSMR Core During Transport Based on Its Temperature Reactivity

Rei Kimura, Kazuhito Asano

Nuclear Science and Engineering / Volume 194 / Number 3 / March 2020 / Pages 213-220

Technical Paper / dx.doi.org/10.1080/00295639.2019.1685352

Validation of Unresolved Neutron Resonance Parameters Using a Thick-Sample Transmission Measurement

Jesse M. Brown, R. C. Block, A. Youmans, H. Choun, A. Ney, E. Blain, D. P. Barry, M. J. Rapp, Y. Danon

Nuclear Science and Engineering / Volume 194 / Number 3 / March 2020 / Pages 221-231

Technical Paper / dx.doi.org/10.1080/00295639.2019.1688087

A Comparison Between the Embedded Self-Shielding Method and the Enhanced Neutron Current Method Based on the Equivalent Pin Cell Model on the Irregular Fuel Lattice Problem

Qian Zhang, Liang Liang, Qiang Zhao, Zhijian Zhang, Hongchun Wu, Liangzhi Cao

Nuclear Science and Engineering / Volume 194 / Number 3 / March 2020 / Pages 232-247

Technical Note / dx.doi.org/10.1080/00295639.2019.1664146

Number 4

Integrated State Awareness Through Secure Embedded Intelligence in Nuclear Systems: Opportunities and Implications

Humberto E. Garcia, Steven E. Aumeier, Ahmad Y. Al-Rashdan

Nuclear Science and Engineering / Volume 194 / Number 4 / April 2020 / Pages 249-269

Technical Paper / dx.doi.org/10.1080/00295639.2019.1698237

Neutronic Analysis to Replace Cobalt Radioisotope Facility by Iridium Radioisotope Facility at ETRR-2

Mohamed A. Elsaied, Alya A. Badawi, Nader M. A. Mohamed, Ahmed El Saghir, Asmaa G. Abo Elnour

Nuclear Science and Engineering / Volume 194 / Number 4 / April 2020 / Pages 270-279

Technical Paper / dx.doi.org/10.1080/00295639.2019.1698238

On-The-Fly Prediction of Macroscopic Cross-Section Spatial Response to TH Perturbations Through Transfer Functions: Theory and First Results

Stefano Terlizzi, Dan Kotlyar

Nuclear Science and Engineering / Volume 194 / Number 4 / April 2020 / Pages 280-296

Technical Paper / dx.doi.org/10.1080/00295639.2019.1698239

Real Variance Estimation in Monte Carlo Criticality Calculation Accelerated by p-CMFD Feedback Using Spectral Analysis Method

HyeonTae Kim, YuGwon Jo, Yonghee Kim

Nuclear Science and Engineering / Volume 194 / Number 4 / April 2020 / Pages 297-307

Technical Paper / dx.doi.org/10.1080/00295639.2019.1698240

Application of Neutron Multiplicity Counting Experiments to Optimal Cross-Section Adjustments

Alexander R. Clark, John Mattingly, Jeffrey A. Favorite

Nuclear Science and Engineering / Volume 194 / Number 4 / April 2020 / Pages 308-333

Technical Paper / dx.doi.org/10.1080/00295639.2019.1698267

Number 5

A High-Precision Tagged Neutron n-p Scattering Measurement at 14.9 MeV

N. V. Kornilov, S. M. Grimes, T. N. Massey, C. E. Brient, D. E. Carter, J. E. O’Donnell, K. W. Cooper, A. D. Carlson, F. B. Bateman, C. R. Heimbach, N. Boukharouba

Nuclear Science and Engineering / Volume 194 / Number 5 / May 2020 / Pages 335-349

Technical Paper / dx.doi.org/10.1080/00295639.2019.1702408

Single Scattering Adjoint Monte Carlo Electron Transport in FRENSIE

Luke J. Kersting, Alex Robinson, Eli Moll, Philip Britt, Lewis Gross, Douglass Henderson

Nuclear Science and Engineering / Volume 194 / Number 5 / May 2020 / Pages 350-372

Technical Paper / dx.doi.org/10.1080/00295639.2019.1701344

Simulation of Multiple-Component Charged Aerosol Evolution

Fernando De La Torre Aguilar, Sudarshan K. Loyalka

Nuclear Science and Engineering / Volume 194 / Number 5 / May 2020 / Pages 373-404

Technical Paper / dx.doi.org/10.1080/00295639.2019.1707153

Evaluation of Discharged Fuel in Preproposed Breed-and-Burn Reactors from Proliferation, Decay Heat, and Radiotoxicity Aspects

Kazuki Kuwagaki, Jun Nishiyama, Toru Obara

Nuclear Science and Engineering / Volume 194 / Number 5 / May 2020 / Pages 405-413

Technical Note / dx.doi.org/10.1080/00295639.2019.1706322

 
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