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Volume 196

Number 2

Measurements of Neutron Scattering from a Copper Sample Using a Quasi-Differential Method in the Region from 2 keV to 20 MeV

E. Blain, Y. Danon, D. P. Barry, B. E. Epping, A. Youmans, M. J. Rapp, A. M. Daskalakis, R. C. Block

Nuclear Science and Engineering / Volume 196 / Number 2 / February 2022 / Pages 121-132

Technical Paper / dx.doi.org/10.1080/00295639.2021.1961542

Applicability of Dynamic Mode Decomposition to Estimate Fundamental Mode Component of Prompt Neutron Decay Constant from Experimental Data

Fuga Nishioka, Tomohiro Endo, Akio Yamamoto, Masao Yamanaka, Cheol Ho Pyeon

Nuclear Science and Engineering / Volume 196 / Number 2 / February 2022 / Pages 133-143

Technical Paper / dx.doi.org/10.1080/00295639.2021.1968225

Transport Corrections and Sensitivities in the Discrete-Ordinates Method

Jeffrey A. Favorite

Nuclear Science and Engineering / Volume 196 / Number 2 / February 2022 / Pages 144-160

Technical Paper / dx.doi.org/10.1080/00295639.2021.1968224

A Stable Method for Solving the Simplified Time-Dependent Neutron Transport Equation with Background Motion

Longfei Xu, Huayun Shen, Junxia Wei, Liujun Pan

Nuclear Science and Engineering / Volume 196 / Number 2 / February 2022 / Pages 161-182

Technical Paper / dx.doi.org/10.1080/00295639.2021.1941565

Optimal Batch Size Growth for Wielandt Method and Superhistory Method

Qingquan Pan, Tengfei Zhang, Xiaojing Liu, Yun Cai, Lianjie Wang, Kan Wang

Nuclear Science and Engineering / Volume 196 / Number 2 / February 2022 / Pages 183-192

Technical Paper / dx.doi.org/10.1080/00295639.2021.1968223

Dynamical System Scaling Application to Zircaloy Cladding Thermal Response During Reactivity-Initiated Accident Experiment

Alexander Duenas, Daniel Wachs, Guillaume Mignot, Jose N. Reyes, Qiao Wu, Wade Marcum

Nuclear Science and Engineering / Volume 196 / Number 2 / February 2022 / Pages 193-208

Technical Paper / dx.doi.org/10.1080/00295639.2021.1955591

Study on LOFA and LOHS Accidents with Passive Safety System for Integrated Marine Reactor

Dong Li, Rao Hao

Nuclear Science and Engineering / Volume 196 / Number 2 / February 2022 / Pages 209-220

Technical Paper / dx.doi.org/10.1080/00295639.2021.1968760

Stress Distribution and Safety Evaluation of Pipeline in Ice Plug of Nuclear Power

Linjun Xie, Changxun Wang, Wei Zhang, Xin Shen, Minglei Hu, Chunhua Bian, Yilun Xu

Nuclear Science and Engineering / Volume 196 / Number 2 / February 2022 / Pages 221-233

Technical Note / dx.doi.org/10.1080/00295639.2021.1964325