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Volume 210

Number 8

Elastic, Anelastic, and Thermal Properties of P91 Steel with Microstructural Variability

Z. Miles, A. Balodhi, T. Seuaciuc-Osorio, J. J. Wall, M. Guimaraes, A. Zevalkink, S. K. Chakrapani

Nuclear Technology / Volume 210 / Number 8 / August 2024 / Pages 1279-1294

Research Article / dx.doi.org/10.1080/00295450.2023.2291602

Enhancement of Gamma-Ray and Neutron Shielding Properties of TeO2-Li2O-ZnO-Nb2O5 Glass System with the Addition of Sm2O3

Zhigang Li, Junfeng Zhao, Yuanjie Sun, Yi Wang, Hongtao Zhao

Nuclear Technology / Volume 210 / Number 8 / August 2024 / Pages 1295-1303

Research Article / dx.doi.org/10.1080/00295450.2023.2294603

A Novel Communication Framework for Reduction of Staffs in Advanced MCRs of SMRs: A Prototype Development of a NLP-Based System

Taejin Kim, Donghan Yoo, Jongin Yang, Seoryong Koo, KyungTae Lim

Nuclear Technology / Volume 210 / Number 8 / August 2024 / Pages 1304-1318

Research Article / dx.doi.org/10.1080/00295450.2023.2295147

Irregular, Backward-Compatible PWR Assembles with More Pins to Facilitate Uprates

Ben Lindley

Nuclear Technology / Volume 210 / Number 8 / August 2024 / Pages 1319-1335

Research Article / dx.doi.org/10.1080/00295450.2023.2295164

Evaluation of Reaction Rate Distribution Measurement in the Prototype Fast Reactor Monju

Kazuya Ohgama, Taira Hazama, Hiroki Katagiri, Atsushi Takegoshi, Tetsuya Mouri

Nuclear Technology / Volume 210 / Number 8 / August 2024 / Pages 1336-1353

Research Article / dx.doi.org/10.1080/00295450.2023.2295168

Safeguards and Security for High-Burnup TRISO Pebble Bed Spent Fuel and Reactors

Charles Forsberg, Andrew Kadak

Nuclear Technology / Volume 210 / Number 8 / August 2024 / Pages 1354-1365

Research Article / dx.doi.org/10.1080/00295450.2023.2298157

Multicriteria Decision Making in Site Selection for Nuclear Power Plants

Berna Tuncer, Aysen D. Akkaya, M. Semih Yucemen

Nuclear Technology / Volume 210 / Number 8 / August 2024 / Pages 1366-1391

Research Article / dx.doi.org/10.1080/00295450.2023.2299078

Prediction of Flooding Characteristic in Pulsed Disc and Doughnut Extraction Column Using LASSO Method

Lei Jin, Hui He, Yu Zhou, Hongguo Hou, Meng Zhang, Yang Gao

Nuclear Technology / Volume 210 / Number 8 / August 2024 / Pages 1392-1413

Research Article / dx.doi.org/10.1080/00295450.2023.2299081

Study on Flow Characteristics of Integrated Natural Circulation Reactor Under Inclined Conditions

Haibo Lian, Shengqiang Li, Shengyao Jiang, Hongye Zhu

Nuclear Technology / Volume 210 / Number 8 / August 2024 / Pages 1414-1426

Research Article / dx.doi.org/10.1080/00295450.2023.2299135

Retention of Hydrogen Bubbles Generated from Water Radiolysis in Carbonate Slurry

Tatsuya Ito, Ryuji Nagaishi, Ryo Kuwano

Nuclear Technology / Volume 210 / Number 8 / August 2024 / Pages 1427-1443

Research Article / dx.doi.org/10.1080/00295450.2023.2299893

Discrete Element Method Simulation of the Idaho Calcine Simulant for Hot Isostatic Pressing Canister-Filling Process: Part 1

Simon Chung, Martin Stewart, Andrew Grima, Peter Wypych, Sam Moricca

Nuclear Technology / Volume 210 / Number 8 / August 2024 / Pages 1444-1463

Research Article / dx.doi.org/10.1080/00295450.2023.2299894

In Situ Chlorine Generation and Rare Earth Chlorination by Molten Salt Electrolysis

Mark Schvaneveldt, Tyler Williams, Ranon Fuller, Devin Rappleye

Nuclear Technology / Volume 210 / Number 8 / August 2024 / Pages 1464-1474

Research Article / dx.doi.org/10.1080/00295450.2023.2299908

Sorption of U(VI) on MX-80 Bentonite and Granite in Ca-Na-Cl Saline Solutions

Zhiwei Zheng, Fabiola Guido Garcia, Jianan Liu, Shinya Nagasaki, Tammy (Tianxiao) Yang

Nuclear Technology / Volume 210 / Number 8 / August 2024 / Pages 1475-1486

Research Article / dx.doi.org/10.1080/00295450.2023.2300900

Bentonites as Natural Sources of Thorium and Uranium

Javiera Cervini-Silva

Nuclear Technology / Volume 210 / Number 8 / August 2024 / Pages 1487-1495

Note / dx.doi.org/10.1080/00295450.2023.2295152

Effect of Gamma Heating on Heat Pipe–Cooled, Calcium Hydride–Moderated Core

Rei Kimura, Kazuhito Asano

Nuclear Technology / Volume 210 / Number 8 / August 2024 / Pages 1496-1502

Note / dx.doi.org/10.1080/00295450.2023.2299899