Guiqiu Zheng

Profile Information
Name
Dr. Guiqiu Zheng
Institution
Massachusetts Institute of Technology
Position
Research Scientist
h-Index
ORCID
0000-0002-5783-5848
Biography

Dr. Guiqiu (Tony) Zheng is a research scientist at the Massachusetts Institute of Technology’s Nuclear Reactor Laboratory (MIT-NRL). He has been continuously working on the R&D of Molten Salt Reactor since his Ph.D. study at the University of Wisconsin-Madison where he earned a master degree and PhD degree in Materials Science. He joined the MIT-NRL research group in 2015 continuing the FHR projects with research focuses on the post-irradiation examinations (PIE) of in-core molten salt corroded materials, molten salt neutron irradiation and tritium permeation barrier. He has been involved in the design and operation of multiple in-core molten salt experiments in support of the FHR.  His expertise includes high-temperature molten salts corrosion, microstructural characterizations of irradiated and non-irradiated materials, molten salt chemistry analysis, and tritium permeation barrier. He has been awarded multiple times to operate the facilities at Idaho National Laboratory for the PIE of in-core irradiated materials through Nuclear Science User Facilities Rapid Turnaround Experiment program. 

Expertise
Fluoride-Salt-Cooled High-Temperature Reactor, microstructure characterization, Nuclear Graphite
Publications:
"Corrosion of Structural Alloys in High-Temperature Molten Fluoride Salts for Applications in Molten Salt Reactors" Guiqiu Zheng, Kumar Sridharan, JOM Vol. 70 2018 1535-1541 Link
"Effect of exposure environment on surface decomposition of SiC–silver ion implantation diffusion couples" Todd Allen, Kevin Field, Tyler Gerczak, Guiqiu Zheng, Journal of Nuclear Materials Vol. 456 2015 281-286 Link
SiC is a promising material for nuclear applications and is a critical component in the construction of tristructural isotropic (TRISO) fuel. A primary issue with TRISO fuel operation is the observed release of 110mAg from intact fuel particles. The release of Ag has prompted research efforts to directly measure the transport mechanism of Ag in bulk SiC. Recent experimental efforts have focused primarily on Ag ion implantation designs. The effect of the thermal exposure system on the ion implantation surface has been investigated. Results indicate the utilization of a mated sample geometry and the establishment of a static thermal exposure environment is critical to maintaining an intact surface for diffusion analysis. The nature of the implantation surface and its potential role in Ag diffusion analysis are discussed.
"Effect of exposure environment on surface decomposition of SiC–silver ion implantation diffusion couples" Tyler Gerczak, Guiqiu Zheng, Kevin Field, Todd Allen, Journal of Nuclear Materials Vol. 456 2015 281-286
"Investigation of Nuclear Graphite and Cf/C Composite in High-Temperature Molten FLiBe Salt in the MIT Reactor" David Carpenter, Guiqiu Zheng, Lin-wen Hu, MIT technical report MIT-NRL-17-03 Vol. 2018 75
Presentations:
"Investigation of Nuclear Graphite and C/C Composite in Molten Li2BeF4 (FLiBe) under Neutron Irradiation" Guiqiu Zheng, David Carpenter, Kieran Dolan, Lin-wen Hu, 19th International Nuclear Graphite Specialists' Meeting September 2-6, (2018) Link
"Microstructure of In-Core Molten Salt Corrosion Hastelloy N® and 316 Stainless Steel" Michael Ames, David Carpenter, Gordon Kohse, Guiqiu Zheng, 2017 ANS Annual Meeting [unknown]
NSUF Articles:
RTE 1st Call Awards Announced - Projects total approximately $1.4 million These projects will continue to advance the understanding of irradiation effects in nuclear fuels and materials in support of the mission of the DOE-NE. Friday, February 8, 2019 - Calls and Awards
RTE 2nd Call Awards Announced - Projects total approximately $1.6 million These project awards went to principal investigators from 26 U.S. universities, eight national laboratories, two British universities, and one Canadian laboratory. Tuesday, May 14, 2019 - Calls and Awards