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Volume 205

Number 11

A Critical Review of the Experimentally Known Properties of U-Pu-Zr Alloys. Part 1: Phases and Phase Diagrams

Dawn E. Janney, Steven L. Hayes, Cynthia A. Adkins

Nuclear Technology / Volume 205 / Number 11 / November 2019 / Pages 1387-1415

Critical Review / dx.doi.org/10.1080/00295450.2019.1578573

Response Matrix Method–Based Importance Solver and Variance Reduction Scheme in the Serpent 2 Monte Carlo Code

Jaakko Leppänen

Nuclear Technology / Volume 205 / Number 11 / November 2019 / Pages 1416-1432

Technical Paper / dx.doi.org/10.1080/00295450.2019.1603710

Application of Boron Carbide as Burnable Poison in Sodium Fast Reactors

H. Guo, P. Sciora, T. Kooyman, L. Buiron, G. Rimpault

Nuclear Technology / Volume 205 / Number 11 / November 2019 / Pages 1433-1446

Technical Paper / dx.doi.org/10.1080/00295450.2019.1620054

Application of Minor Actinides as Burnable Poisons in Sodium Fast Reactors

H. Guo, T. Kooyman, P. Sciora, L. Buiron

Nuclear Technology / Volume 205 / Number 11 / November 2019 / Pages 1447-1459

Technical Paper / dx.doi.org/10.1080/00295450.2019.1611304

Minor Actinide Transmutation in Supercritical-CO2-Cooled and Sodium-Cooled Fast Reactors with Low Burnup Reactivity Swings

Hoai-Nam Tran, Yasuyoshi Kato, Peng Hong Liem, Van-Khanh Hoang, Sy Minh Tuan Hoang

Nuclear Technology / Volume 205 / Number 11 / November 2019 / Pages 1460-1473

Technical Paper / dx.doi.org/10.1080/00295450.2019.1601470

Development of a Monte Carlo Modeling Approach to Determine the Enrichment of UF6 Typical Cylinders

Sayed A. El-Mongy, Kh. A. Allam

Nuclear Technology / Volume 205 / Number 11 / November 2019 / Pages 1474-1479

Technical Paper / dx.doi.org/10.1080/00295450.2019.1593012

Time Resolution of a Cs2LiYCl6:Ce3+ Detector Measured with a DRS4 Waveform Digitizer

Xianfei Wen, Andreas Enqvist

Nuclear Technology / Volume 205 / Number 11 / November 2019 / Pages 1480-1487

Technical Paper / dx.doi.org/10.1080/00295450.2019.1603503

Calculation of Heat Fluxes Exiting a CANDU Calandria During In-Vessel Retention

Robert David

Nuclear Technology / Volume 205 / Number 11 / November 2019 / Pages 1488-1494

Technical Paper / dx.doi.org/10.1080/00295450.2019.1597581

Fluoride-Salt-Cooled High-Temperature Test Reactor Thermal-Hydraulic Licensing and Uncertainty Propagation Analysis

R. R. Romatoski, L. W. Hu

Nuclear Technology / Volume 205 / Number 11 / November 2019 / Pages 1495-1512

Technical Paper / dx.doi.org/10.1080/00295450.2019.1610686

 
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