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Volume 188

Number 1 | Number 2 | Number 3

Number 1

Two-Level Convergence Speedup Schemes for p-CMFD Acceleration in Neutron Transport Calculation

Seungsu Yuk, Nam Zin Cho

Nuclear Science and Engineering / Volume 188 / Number 1 / October 2017 / Pages 1-14

Technical Paper / dx.doi.org/10.1080/00295639.2017.1332891

Resonance Self-Shielding Methods for Fast Reactor Calculations—Comparison of a New Tone’s Method with the Subgroup Method in APOLLO3

Li Mao, Igor Zmijarevic, Richard Sanchez

Nuclear Science and Engineering / Volume 188 / Number 1 / October 2017 / Pages 15-32

Technical Paper / dx.doi.org/10.1080/00295639.2017.1332890

Improved Approach to Multiregion Supercritical Transient Analysis Based on the Integral Kinetic Model and Monte Carlo Method

Delgersaikhan Tuya, Hiroki Takezawa, Toru Obara

Nuclear Science and Engineering / Volume 188 / Number 1 / October 2017 / Pages 33-42

Technical Paper / dx.doi.org/10.1080/00295639.2017.1337383

Optimal Run Strategies in Monte Carlo Iterated Fission Source Simulations

Paul K. Romano, Amanda L. Lund, Andrew R. Siegel

Nuclear Science and Engineering / Volume 188 / Number 1 / October 2017 / Pages 43-56

Technical Paper / dx.doi.org/10.1080/00295639.2017.1340692

Fission Chain Restart Theory

K. S. Kim, L. F. Nakae, M. K. Prasad, N. J. Snyderman, J. M. Verbeke

Nuclear Science and Engineering / Volume 188 / Number 1 / October 2017 / Pages 57-84

Technical Paper / dx.doi.org/10.1080/00295639.2017.1340691

Effects of Endcaps and Spacer Pads on Unsteady Fluid Forces and Flow Through a 37-Element CANDU Fuel Bundle

M. Fadaee, S. D. Yu

Nuclear Science and Engineering / Volume 188 / Number 1 / October 2017 / Pages 85-101

Technical Paper / dx.doi.org/10.1080/00295639.2017.1337382

Estimation of d-2H Breakup Neutron Energy Distributions From d-3He

B. Hoop (ret.), S. M. Grimes, M. Drosg

Nuclear Science and Engineering / Volume 188 / Number 1 / October 2017 / Pages 102-107

Technical Note / dx.doi.org/10.1080/00295639.2017.1332892

Number 2

Kernel Density Estimation of Reaction Rates in Neutron Transport Simulations of Nuclear Reactors

Timothy P. Burke, Brian C. Kiedrowski, William R. Martin

Nuclear Science and Engineering / Volume 188 / Number 2 / November 2017 / Pages 109-139

Technical Paper / dx.doi.org/10.1080/00295639.2017.1350000

Space-Dependent Wielandt Shifts for Multigroup Diffusion Eigenvalue Problems

Ben C. Yee, Brendan Kochunas, Edward W. Larsen, Yunlin Xu

Nuclear Science and Engineering / Volume 188 / Number 2 / November 2017 / Pages 140-159

Technical Paper / dx.doi.org/10.1080/00295639.2017.1350001

A Three-Dimensional Variational Nodal Method for Pin-Resolved Neutron Transport Analysis of Pressurized Water Reactors

Tengfei Zhang, Yongping Wang, E. E. Lewis, M. A. Smith, W. S. Yang, Hongchun Wu

Nuclear Science and Engineering / Volume 188 / Number 2 / November 2017 / Pages 160-174

Technical Paper / dx.doi.org/10.1080/00295639.2017.1350002

Experimental Investigation of Single- and Two-Phase Diversion Cross Flow in Simulated Subchannels of a Natural-Circulation Pressure Tube–Type BWR

M. P. Sharma, A. K. Nayak

Nuclear Science and Engineering / Volume 188 / Number 2 / November 2017 / Pages 175-186

Technical Paper / dx.doi.org/10.1080/00295639.2017.1339539

The Analysis of Global Stability Boundary and Multistability in the Nonlinear Dynamical System of an Advanced Heavy Water Reactor

Vikas Pandey, Suneet Singh

Nuclear Science and Engineering / Volume 188 / Number 2 / November 2017 / Pages 187-197

Technical Paper / dx.doi.org/10.1080/00295639.2017.1350003

Activation Cross Section and Isomeric Cross-Section Ratio for the (n,2n) Reaction on 113,115In

Junhua Luo, Li Jiang, Suyuan Li

Nuclear Science and Engineering / Volume 188 / Number 2 / November 2017 / Pages 198-206

Technical Paper / dx.doi.org/10.1080/00295639.2017.1352366

Number 3

Improvement of Nodal Accuracy by Using Albedo-Corrected Parameterized Equivalence Constants

Woosong Kim, Woong Heo, Yonghee Kim

Nuclear Science and Engineering / Volume 188 / Number 3 / December 2017 / Pages 207-245

Technical Paper / dx.doi.org/10.1080/00295639.2017.1354592

Neutron Multiplicity Counting Moments for Fissile Mass Estimation in Scatter-Based Neutron Detection Systems

Tony H. Shin, Michael Y. Hua, Matthew J. Marcath, David L. Chichester, Imre Pázsit, Angela Di Fulvio, Shaun D. Clarke, Sara A. Pozzi

Nuclear Science and Engineering / Volume 188 / Number 3 / December 2017 / Pages 246-269

Technical Paper / dx.doi.org/10.1080/00295639.2017.1354591

Research on the Subchannel Analysis Method via CFD Analysis for PWR

Guangliang Chen, Zhijian Zhang, Zhaofei Tian, Thompson Appah, Lei Li, Xiaomeng Dong, Peizheng Hu

Nuclear Science and Engineering / Volume 188 / Number 3 / December 2017 / Pages 270-281

Technical Paper / dx.doi.org/10.1080/00295639.2017.1367568

Parent Isotopic and Elemental Contributing Factors to Minimize Nuclear Radiological Responses and Optimize Material Composition

Sai Chaitanya Tadepalli, Priti Kanth, P. V. Subhash

Nuclear Science and Engineering / Volume 188 / Number 3 / December 2017 / Pages 282-293

Technical Paper / dx.doi.org/10.1080/00295639.2017.1367570

Microfluidic Alpha Spectrometry of UOX PWR UNF in a Molten Salt

Eric Lukosi

Nuclear Science and Engineering / Volume 188 / Number 3 / December 2017 / Pages 294-302

Technical Paper / dx.doi.org/10.1080/00295639.2017.1367248

 
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