American Nuclear Society

/Create an Account

Home

Home / Publications / Journals / Nuclear Science and Engineering / Volume 196 / Number 5

Volume 196

Number 5

Table of Contents

Exponential Time Differencing Schemes for Fuel Depletion and Transport in Molten Salt Reactors: Theory and Implementation

Zack Taylor, Benjamin S. Collins, G. Ivan Maldonado

Nuclear Science and Engineering / Volume 196 / Number 5 / May 2022 / Pages 497-525

Technical Paper / dx.doi.org/10.1080/00295639.2021.1996197

A Residual-Based Subgrid-Scale Method Combined with Spherical Harmonics Angular Approximation for Solving the Boltzmann Transport Equation

Chao Fang, Liangzhi Cao, Hongchun Wu, Kang Li

Nuclear Science and Engineering / Volume 196 / Number 5 / May 2022 / Pages 526-543

Technical Paper / dx.doi.org/10.1080/00295639.2021.2011667

Real-Time Monitoring for Detection of Adversarial Subtle Process Variations

Yeni Li, Arvind Sundaram, Hany S. Abdel-Khalik, Paul W. Talbot

Nuclear Science and Engineering / Volume 196 / Number 5 / May 2022 / Pages 544-567

Technical Paper / dx.doi.org/10.1080/00295639.2021.1997041

Safety Analysis in VVER-1000 Due to Large-Break Loss-of-Coolant Accident and Station Blackout Transient Using RELAP5/SCDAPSIM/MOD3.5

Fabiano Gibson Daud Thulu, Ayah Elshahat, Mohamed Hassan

Nuclear Science and Engineering / Volume 196 / Number 5 / May 2022 / Pages 568-583

Technical Paper / dx.doi.org/10.1080/00295639.2021.2009984

Deposition Behavior of Cesium Molybdate on Type 304 Austenite Stainless Steel in Severe Accident

Thi-Mai-Dung Do, Supamard Sujatanond, Toru Ogawa

Nuclear Science and Engineering / Volume 196 / Number 5 / May 2022 / Pages 584-599

Technical Paper / dx.doi.org/10.1080/00295639.2021.2009985

Numerical Evaluation for Spacer Vane Effects on Flow and Heat Transfer of Water at Supercritical Pressure in Annular Channel

Satish Kumar Dhurandhar, S. L. Sinha, Shashi Kant Verma

Nuclear Science and Engineering / Volume 196 / Number 5 / May 2022 / Pages 600-613

Technical Paper / dx.doi.org/10.1080/00295639.2021.2003650

A Study of Gamma Heating, Neutron Flux, and Gamma Flux Under Several Reactor Core Conditions in the McMaster Nuclear Reactor

Mohammed Alqahtani, Adriaan Buijs, Meshari ALQahtani

Nuclear Science and Engineering / Volume 196 / Number 5 / May 2022 / Pages 614-622

Technical Paper / dx.doi.org/10.1080/00295639.2021.2003651

Effect of Cladding Surface Roughness on Thermal-Hydraulic Response of Nuclear Fuel Rod of Advanced Gas-Cooled Reactor

Sadek Hossain Nishat, Md. Hossain Sahadath, Farhana Islam Farha

Nuclear Science and Engineering / Volume 196 / Number 5 / May 2022 / Pages 623-636

Technical Note / dx.doi.org/10.1080/00295639.2021.2003644

Home|Contact Us|Invoice Payment|Nuclear Links

Privacy Policy|Terms of Use