ANS / Publications / Journals / Nuclear Technology

Review of Filtered Containment Venting System (FCVS) Eleven Years After Fukushima Accident

Jawaria Ahad, Amjad Farooq, Masroor Ahmad, Naseem Irfan, Khalid Waheed

Nuclear Technology / Volume 210 / Number 10 / October 2024 / Pages 1767-1823

Review Article / dx.doi.org/10.1080/00295450.2024.2302716

Multiphysics Analysis of PLOFC and DLOFC Accidents in the HTGR-TR

Annie Berens, Nicholas Meehan, Mason Fox, Isabelle Lindsay, Nicholas R. Brown

Nuclear Technology / Volume 210 / Number 10 / October 2024 / Pages 1824-1842

Research Article / dx.doi.org/10.1080/00295450.2024.2302723

i-LAMP: Global, Industrywide Learning Aging Management Program for Neutron-Absorber Materials in Spent Fuel Pools

Hatice Akkurt

Nuclear Technology / Volume 210 / Number 10 / October 2024 / Pages 1843-1857

Research Article / dx.doi.org/10.1080/00295450.2024.2302734

Methodology to Assist in Training Maneuvers of Operation of Pumps of a Nuclear Plant Using Virtual Reality

Daniel Mól Machado, Gustavo Souza Pinheiro dos Santos, Andre Cotelli do Espirito Santo, Antonio Carlos de Abreu Mól, Celso Marcelo Franklin Lapa, Claudio Henrique dos Santos Grecco

Nuclear Technology / Volume 210 / Number 10 / October 2024 / Pages 1858-1870

Research Article / dx.doi.org/10.1080/00295450.2024.2302740

Numerical Simulation on Dispersion of Hydrogen Leaked in Particle Layers of Glass Beads and Soil

Atsuhiko Terada, Ryuji Nagaishi

Nuclear Technology / Volume 210 / Number 10 / October 2024 / Pages 1871-1887

Research Article / dx.doi.org/10.1080/00295450.2024.2302747

Asymmetric Two-Step Thermosiphon for Containment Cooling of Small Modular Reactors

Sung-Jae Yi, Jin-Hwa Yang, Byong Guk Jeon, Hwang Bae, Hyun-Sik Park, Kwang-Won Seul

Nuclear Technology / Volume 210 / Number 10 / October 2024 / Pages 1888-1900

Research Article / dx.doi.org/10.1080/00295450.2024.2304909

Thermal and Electrical Performance Analyses of a 100-W Radioisotope Thermoelectric Generator for Space Exploration

Shiping Wei, Jin Wang, Zhixin Ma, Ming Jin, Chunjing Li, Yuan Hu

Nuclear Technology / Volume 210 / Number 10 / October 2024 / Pages 1901-1913

Research Article / dx.doi.org/10.1080/00295450.2024.2304911

Simulation of Readout Electronics for Nuclear Radiation Detector Using MATLAB Program

Jamal-Eddin Assaf, Zuheir Ahmad

Nuclear Technology / Volume 210 / Number 10 / October 2024 / Pages 1914-1924

Research Article / dx.doi.org/10.1080/00295450.2024.2304913

Temperature-Dependent Swelling in Helium Ion Irradiated Vanadium

Weiping Zhang, Yiheng Chen, Wenrui Cheng, Liping Guo, FengFeng Luo

Nuclear Technology / Volume 210 / Number 10 / October 2024 / Pages 1925-1931

Research Article / dx.doi.org/10.1080/00295450.2024.2304914

Best Estimate Plus Uncertainty Analysis of Station Blackout Transient in Pool-Type Research Reactor

Amitanshu Mishra, Paban Kumar Guchhait, Samiran Sengupta

Nuclear Technology / Volume 210 / Number 10 / October 2024 / Pages 1932-1951

Research Article / dx.doi.org/10.1080/00295450.2024.2304915

Simulation of Neutron Leakage Variations at Fuel Substitution in a Small Modular Reactor and Implications for Unattended Safeguards Monitoring

Markus Preston, Erik Branger, Sophie Grape, Olena Khotiaintseva

Nuclear Technology / Volume 210 / Number 10 / October 2024 / Pages 1952-1974

Research Article / dx.doi.org/10.1080/00295450.2024.2304931

Characterization of a Fast Neutron Irradiation Facility Using a Stilbene Scintillation Detector

Felix Pino, Jessica C. Delgado, Matteo Polo, Erica Fanchini, Anna Selva, Joana Minga, Gianmarco Torilla, Lodovico Ratti, Sandra Moretto

Nuclear Technology / Volume 210 / Number 10 / October 2024 / Pages 1975-1984

Research Article / dx.doi.org/10.1080/00295450.2024.2304993

Polarization of Compton-Scattered Prompt Gamma-Ray Technique for HEU Detection at 186 keV

Athanas Mutiso, Ayodeji B. Alajo, Xin Liu

Nuclear Technology / Volume 210 / Number 10 / October 2024 / Pages 1985-1998

Research Article / dx.doi.org/10.1080/00295450.2024.2306109

Release Behavior of Gaseous Ruthenium Tetroxide During Heating of High-Level Liquid Waste Simulant During Simulated Accident Conditions

Naoki Yoshida, Takuya Ohno, Yuki Amano, Ryoichiro Yoshida, Hitoshi Abe, Yuichi Yamane

Nuclear Technology / Volume 210 / Number 10 / October 2024 / Pages 1999-2007

Note / dx.doi.org/10.1080/00295450.2024.2306688