American Nuclear Society
Join ANS|Member Center|ANS Store|Contact Us
Home

Home / Publications / Journals / Nuclear Science and Engineering / Volume 195 / Number 5

Volume 195

Number 5

Supercritical Transient Analysis for Ramp Reactivity Insertion Using Multiregion Integral Kinetics Code

Kodai Fukuda, Jun Nishiyama, Toru Obara

Nuclear Science and Engineering / Volume 195 / Number 5 / May 2021 / Pages 453-463

Technical Paper / dx.doi.org/10.1080/00295639.2020.1847979

Unstructured Mesh–Based Neutronics and Thermomechanics Coupled Steady-State Analysis on Advanced Three-Dimensional Fuel Elements with Monte Carlo Code iMC

HyeonTae Kim, Yonghee Kim

Nuclear Science and Engineering / Volume 195 / Number 5 / May 2021 / Pages 464-477

Technical Paper / dx.doi.org/10.1080/00295639.2020.1839342

Numerical Simulation on Asymmetrical Three-Dimensional Thermal and Hydraulic Characteristics of the Primary Sodium Pool Under the Pump Stuck Accident in CEFR

Jiaxuan Tang, Daogang Lu, Jiangtao Liang, Xiangfeng Ma, Yizhe Liu, Shangshang Ye, Zihan Xia, Yuhao Zhang

Nuclear Science and Engineering / Volume 195 / Number 5 / May 2021 / Pages 478-495

Technical Paper / dx.doi.org/10.1080/00295639.2020.1834314

Individual Adjustment of Independent Cross-Section Set Based on Bayesian Theory

Satoshi Takeda, Takanori Kitada

Nuclear Science and Engineering / Volume 195 / Number 5 / May 2021 / Pages 496-508

Technical Paper / dx.doi.org/10.1080/00295639.2020.1833601

Study of the Effects of Moderators on ADS System Performance Based on UN-ThO2 Fuel

A. M. M. Ali, Hanaa H. Abou-Gabal, Nader M. A. Mohamed, Ayah E. Elshahat

Nuclear Science and Engineering / Volume 195 / Number 5 / May 2021 / Pages 509-519

Technical Paper / dx.doi.org/10.1080/00295639.2020.1839248

ROM-Based Surrogate Systems Modeling of EBR-II

Yeni Li, Hany S. Abdel-Khalik, Acacia J. Brunett, Elise Jennings, Travis Mui, Rui Hu

Nuclear Science and Engineering / Volume 195 / Number 5 / May 2021 / Pages 520-537

Technical Paper / dx.doi.org/10.1080/00295639.2020.1840238

On the Use of Graph Theory to Interpret the Output Results from a Monte-Carlo Depletion Code

Benjamin Dechenaux

Nuclear Science and Engineering / Volume 195 / Number 5 / May 2021 / Pages 538-554

Technical Paper / dx.doi.org/10.1080/00295639.2020.1847980

Prediction of the Power Peaking Factor in a Boron-Free Small Modular Reactor Based on a Support Vector Regression Model and Control Rod Bank Positions

Priscila Palma Sanchez, Adimir dos Santos

Nuclear Science and Engineering / Volume 195 / Number 5 / May 2021 / Pages 555-562

Technical Note / dx.doi.org/10.1080/00295639.2020.1854541

 

Home|Contact Us|Invoice Payment|Nuclear Links

Privacy Policy|Terms of Use