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Volume 208

Number 7

Foundations for a Fission Battery Digital Twin

Jeren Browning, Andrew Slaughter, Ross Kunz, Joshua Hansel, Bri Rolston, Katherine Wilsdon, Adam Pluth, Dillon McCardell

Nuclear Technology / Volume 208 / Number 7 / July 2022 / Pages 1089-1101

Technical Paper / dx.doi.org/10.1080/00295450.2021.2011574

Reactor Performance and Safety Characteristics of Beryllium-Based Composite Moderators as Replacements for Graphite in mHTGRs

Veronica Karriem, Edward M. Duchnowski, Bin Cheng, Lance L. Snead, Jason R. Trelewicz, Nicholas R. Brown

Nuclear Technology / Volume 208 / Number 7 / July 2022 / Pages 1102-1113

Technical Paper / dx.doi.org/10.1080/00295450.2021.2011573

Partial Cross-Section Calculations for PGNAA Based on a Deterministic Neutron Transport Solver

Alexander Jesser, Kai Krycki, Martin Frank

Nuclear Technology / Volume 208 / Number 7 / July 2022 / Pages 1114-1123

Technical Paper / dx.doi.org/10.1080/00295450.2021.2016018

Direct Dissolution of Used Nuclear Fuel in PUREX Solvent: Review and Flowsheet Development

Stuart T. Arm

Nuclear Technology / Volume 208 / Number 7 / July 2022 / Pages 1124-1136

Technical Paper / dx.doi.org/10.1080/00295450.2021.2018274

Shielding Analysis for a Moderated Low-Enriched-Uranium–Fueled Kilopower Reactor

Jeffrey C. King, Leonardo de Holanda Mencarini

Nuclear Technology / Volume 208 / Number 7 / July 2022 / Pages 1137-1148

Technical Paper / dx.doi.org/10.1080/00295450.2021.2004870

Alloying of Pu-Al with Stainless Steel for Material Disposition

R. A. Pierce, L. C. Olson, H. M Ajo

Nuclear Technology / Volume 208 / Number 7 / July 2022 / Pages 1149-1164

Technical Paper / dx.doi.org/10.1080/00295450.2021.2004871

Spent Nuclear Fuel Heatup Calculations Supporting Emergency Planning Exemption Using CFD Code

Wen-Yu Wang, Yung-Shin Tseng, Chih-Hung Lin, Tsung-Kuang Yeh

Nuclear Technology / Volume 208 / Number 7 / July 2022 / Pages 1165-1183

Technical Paper / dx.doi.org/10.1080/00295450.2021.2011576

Estimation of Pipe Wall Thinning Using a Convolutional Neural Network for Regression

Jonghwan Kim, Byunyoung Jung, Junhong Park, Youngchul Choi

Nuclear Technology / Volume 208 / Number 7 / July 2022 / Pages 1184-1191

Technical Paper / dx.doi.org/10.1080/00295450.2021.2018271

Optimization Studies of Elemental Composition of Composite Polymer for Neutron Shielding Using Factorial Design Analysis

Pew Basu, R. Sarangapani, D. Datta, B. Venkatraman

Nuclear Technology / Volume 208 / Number 7 / July 2022 / Pages 1192-1204

Technical Paper / dx.doi.org/10.1080/00295450.2021.2018275

Differential Pressure Changes of a High Airflow–Type HEPA Filter During Solvent Fire in Reprocessing Facilities

Shinsuke Tashiro, Gunzo Uchiyama, Takuya Ohno, Yuki Amano, Ryoichiro Yoshida, Hithoshi Abe

Nuclear Technology / Volume 208 / Number 7 / July 2022 / Pages 1205-1213

Technical Paper / dx.doi.org/10.1080/00295450.2021.2018272

Enhancement of Fast Neutron Detection in Liquid Scintillator Detectors

Gang Li, Ghaouti Bentoumi, Liqian Li

Nuclear Technology / Volume 208 / Number 7 / July 2022 / Pages 1214-1222

Technical Paper / dx.doi.org/10.1080/00295450.2021.2011672

Research on the Preliminary Prediction of Nuclear Core Design Based on Machine Learning

Jichong Lei, Zhenping Chen, Jiandong Zhou, Chao Yang, Changan Ren, Wei Li, Chao Xie, Zining Ni, Gan Huang, Leiming Li, Jinsen Xie, Tao Yu

Nuclear Technology / Volume 208 / Number 7 / July 2022 / Pages 1223-1232

Technical Note / dx.doi.org/10.1080/00295450.2021.2018270