1. Experimental Measurement and Multiphysics Simulation of Tritium Transport in Neutron-Irradiated Flibe Salt. (3rd April 2023) Authors: Dolan, Kieran; Su, Guanyu; Zheng, Guiqiu; Ames, Michael; Carpenter, David; Hu, Lin-Wen Journal: Nuclear technology Issue: Volume 209:Number 4(2023) Page Start: 515 Record Type: Journal Article View Content: Available online (eLD content is only available in our Reading Rooms) ↗
2. Miniature Sensor Irradiation Tests Under Steady-State and Transient Conditions at MIT Research Reactor (MITR) and Transient Reactor Test Facility (TREAT). (2nd June 2020) Authors: Sun, Kaichao; Carpenter, David; Ames, Michael; Dave, Akshay J.; Hu, Lin-Wen Journal: Nuclear technology Issue: Volume 206:Number 6(2020) Page Start: 924 Record Type: Journal Article View Content: Available online (eLD content is only available in our Reading Rooms) ↗
3. Miniature Sensor Irradiation Tests Under Steady-State and Transient Conditions at MIT Research Reactor (MITR) and Transient Reactor Test Facility (TREAT). (2nd June 2020) Authors: Sun, Kaichao; Carpenter, David; Ames, Michael; Dave, Akshay J.; Hu, Lin-Wen Journal: Nuclear technology Issue: Volume 206:Number 6(2020) Page Start: 924 Record Type: Journal Article View Content: Available online (eLD content is only available in our Reading Rooms) ↗
4. Modeling Tritium Retention in Graphite for Fluoride-Salt-Cooled High-Temperature Reactors. (3rd October 2021) Authors: Dolan, Kieran; Huang, Steven; Hackett, Micah; Hu, Lin-Wen Journal: Nuclear technology Issue: Volume 207:Number 10(2021) Page Start: 1578 Record Type: Journal Article View Content: Available online (eLD content is only available in our Reading Rooms) ↗
5. Thermal-Hydraulic Analyses of Transportable Fluoride Salt–Cooled High-Temperature Reactor with CFD Modeling. (1st October 2016) Authors: Wang, Chenglong; Sun, Kaichao; Hu, Lin-Wen; Qiu, Suizheng; Su, G. H. Journal: Nuclear technology Issue: Volume 196:Number 1(2016) Page Start: 34 Record Type: Journal Article View Content: Available online (eLD content is only available in our Reading Rooms) ↗
6. Tritium Content and Chemical Form in Nuclear Graphite from Molten Fluoride Salt Irradiations. (18th May 2020) Authors: Dolan, Kieran; Zheng, Guiqiu; Carpenter, David; Huang, Steven; Hu, Lin-Wen Journal: Fusion science and technology Issue: Volume 76:Number 4(2020) Page Start: 398 Record Type: Journal Article View Content: Available online (eLD content is only available in our Reading Rooms) ↗
7. Tritium Content and Chemical Form in Nuclear Graphite from Molten Fluoride Salt Irradiations. (18th May 2020) Authors: Dolan, Kieran; Zheng, Guiqiu; Carpenter, David; Huang, Steven; Hu, Lin-Wen Journal: Fusion science and technology Issue: Volume 76:Number 4(2020) Page Start: 398 Record Type: Journal Article View Content: Available online (eLD content is only available in our Reading Rooms) ↗