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

Home / Publications / Journals / Nuclear Science and Engineering / Volume 195 / Number 8

Volume 195

Number 8

An Analytic Benchmark for Neutron Boltzmann Transport with Downscattering—Part I: Flux and Eigenvalue Solutions

Vladimir Sobes, Pablo Ducru, Abdulla Alhajri, Barry Ganapol, Benoit Forget

Nuclear Science and Engineering / Volume 195 / Number 8 / August 2021 / Pages 795-812

Technical Paper / dx.doi.org/10.1080/00295639.2021.1874777

An Analytic Benchmark for Neutron Boltzmann Transport with Downscattering—Part II: Flux and Eigenvalue Sensitivities to Nuclear Cross Sections and Resonance Parameters

A. Alhajri, V. Sobes, P. Ducru, B. Ganapol, B. Forget

Nuclear Science and Engineering / Volume 195 / Number 8 / August 2021 / Pages 813-824

Technical Paper / dx.doi.org/10.1080/00295639.2021.1898923

Reactor Physics Benchmark of the First Criticality in the Molten Salt Reactor Experiment

Dan Shen, Germina Ilas, Jeffrey J. Powers, Massimiliano Fratoni

Nuclear Science and Engineering / Volume 195 / Number 8 / August 2021 / Pages 825-837

Technical Paper / dx.doi.org/10.1080/00295639.2021.1880850

Experimental Study of Air-Steam–Mixture Condensation Underneath Containment Vessel Surface

Bing Tan, W. X. Tian, R. H. Chen, S. Z. Qiu, G. H. Su

Nuclear Science and Engineering / Volume 195 / Number 8 / August 2021 / Pages 838-852

Technical Paper / dx.doi.org/10.1080/00295639.2021.1878780

A Newly Developed Suppression Pool Model Based on the ISAA Code

Bin Zhang, Jian Deng, Maolin Jing, Tao Xu, Xiaowei Jiang, Jianqiang Shan

Nuclear Science and Engineering / Volume 195 / Number 8 / August 2021 / Pages 853-863

Technical Paper / dx.doi.org/10.1080/00295639.2020.1861862

Concrete Modeling for Neutron Transport and Associated Sensitivity Studies Performed at the AMANDE-MIRCOM Facility

Michaël Petit

Nuclear Science and Engineering / Volume 195 / Number 8 / August 2021 / Pages 864-876

Technical Paper / dx.doi.org/10.1080/00295639.2020.1867436

Uncertainty Quantification of Lead and Bismuth Sample Reactivity Worth at Kyoto University Critical Assembly

Cheol Ho Pyeon, Masao Yamanaka, Masahiro Fukushima

Nuclear Science and Engineering / Volume 195 / Number 8 / August 2021 / Pages 877-889

Technical Paper / dx.doi.org/10.1080/00295639.2020.1870861

Multilevel-in-Space-and-Energy CMFD in VERA

L. R. Cornejo, B. S. Collins, S. G. Stimpson, A. M. Graham

Nuclear Science and Engineering / Volume 195 / Number 8 / August 2021 / Pages 890-905

Technical Paper / dx.doi.org/10.1080/00295639.2021.1877503

 

Home|Contact Us|Invoice Payment|Nuclear Links

Privacy Policy|Terms of Use