Graduate Student Researchernicolas.email@example.com
During his time in the Thermal-Hydraulics Laboratory, Nicolas was involved in modeling and experimental validation for passive safety systems used in FHRs. In particular, he was responsible for design, fabrication and startup testing in the Compact Integral Effects Test (CIET) facility, which reproduces key fluid mechanics and heat transfer phenomena in FHRs at 50% scale, reduced fluid temperature and heating power under 2% of prototypical values. He also studied reliability of the Direct Reactor Auxiliary Cooling System (DRACS) used for passive decay heat removal in FHRs, by developing a methodology that uses best-estimate codes validated with experimental data from CIET.
Prior to attending UC Berkeley, Nicolas received a BS and a MS in Mechanical Engineering and Physics applied to energy at Ecole Polytechnique in France. During his PhD, Nicolas worked at the Electric Power Research Institute on risk aggregation methods applied to safety analysis of nuclear power plants,
- Zweibaum, “Experimental Validation of Passive Safety System Models: Application to Design and Optimization of Fluoride-Salt-Cooled, High-Temperature Reactors,” PhD Dissertation, Department of Nuclear Engineering, University of California, Berkeley (2015).
- Zweibaum, J. E. Bickel, Z. Guo, J. C. Kendrick, and P. F. Peterson, “Design, Fabrication and Startup Testing in the Compact Integral Effects Test Facility in Support of Fluoride-Salt-Cooled, High-Temperature Reactor Technology,” Proc. NURETH-16, Chicago, Illinois, August 30-September 4, 2015, American Nuclear Society (2015).
- Zweibaum, Z. Guo, L. R. Huddar, and P. F. Peterson, “Validation of Best Estimate Models for Fluoride-Salt-Cooled, High-Temperature Reactors Using Data from the Compact Integral Effects Test (CIET 1.0) Facility,” Proc. NURETH-16, Chicago, Illinois, August 30-September 4, 2015, American Nuclear Society (2015).
- Zweibaum et al., “Role and Status of Scaled Experiments in the Development of Fluoride-Salt-Cooled, High-Temperature Reactors,” Proc. Int. Congress on Advances in Nuclear Power Plants (ICAPP ’15), Nice, France, May 3-6, 2015, American Nuclear Society (2015).
- Zweibaum, C. Andreades, S. Hong, and P. F. Peterson, “Life Cycle Assessment of the Mark 1 Pebble-Bed, Fluoride-Salt-Cooled, High-Temperature Reactor,” Proc. Int. Congress on Advances in Nuclear Power Plants (ICAPP ’15), Nice, France, May 3-6, 2015, American Nuclear Society (2015).
- Zweibaum, J. E. Bickel, and P. F. Peterson, “Design, Fabrication and Startup Testing in the Compact Integral Effects Test (CIET 1.0) Facility in Support of Fluoride-Salt-Cooled, High-Temperature Reactor Technology,” Department of Nuclear Engineering, University of California, Berkeley, UCBTH-14-009 (2014).
- Zweibaum et al., “Phenomenology, Methods and Experimental Program for Fluoride-Salt-Cooled, High-Temperature Reactors (FHRs),” Prog. Nucl. Energ., 77, 390 (2014).
- Zweibaum, R. O. Scarlat, and P. F. Peterson, “Design of a Compact Integral Effects Test Facility for Fluoride-Salt- Cooled, High-Temperature Reactors,” T. Am. Nucl. Soc., <strong>109</strong>, 1, 1588 (2013).
- T. Cisneros, N. Zweibaum et al., “Fluoride-Salt-Cooled, High-Temperature Reactor (FHR) Methods and Experiments Program White Paper,” Department of Nuclear Engineering, University of California, Berkeley, UCBTH-12-002 (2013).
- Zweibaum, R. O. Scarlat and P. F. Peterson, “Verification and Validation of a Single-Phase Natural Circulation Loop Model in RELAP5-3D,” Proc. IRUG 2013 Meeting, Idaho Falls, ID, September 12-13, 2013, International RELAP5 Users Group (2013).
- T. Cisneros, N. Zweibaum, C. Di Sanzo, J. Cohen, and E. Greenspan, “Feasibility of Once Through Subcritical Cores Driven by an Accelerator Spallation Neutron Source,” Fusion Sci. Technol., 61, 1T, 431 (2012).
- Zweibaum and P. F. Peterson, “Validation, through Scaled Experiments, of RELAP5-3D Models of Porous Media Flow, and their Applicability to the Development of the Pebble-Bed Advanced High Temperature Reactor (PB-AHTR),” MS Report, Department of Nuclear Engineering, University of California, Berkeley (2011).
Nicolas enjoys traveling, reading and going to concerts in his spare time. He is particularly interested in global energy matters and served as the Nuclear Engineering Department’s liaison to the Berkeley Energy and Resources Collaborative between 2011 and 2012.
Graduate Student Researcher
Graduate Student Researchergrant.firstname.lastname@example.org
Grant performed research in the X-ray Pebble Recirculation Experiment (XPREX) facility. His research involved the design and fabrication of experiments, the instrumentation and controls for the facility, and the creation of the x-ray tomography software. Grant graduated with a B.S. in Nuclear and Mechanical Engineering from UC Berkeley in the Spring of 2014. He also graduated with a Masters in Science in Nuclear Engineering from UC Berkeley in the Spring of 2015, with a thesis titled “Control Blade Insertion Dynamics in Pebble-Bed Fluoride-Salt-Cooled High-Temperature Reactors”.
Grant has taken a job at NuScale power in the PRA group, which he will start in Fall of 2015.
Outside of nuclear engineering, Grant enjoys skiing, snowboarding, hiking, rock-climbing, reading, and creative design-thinking. He was president of the College Ski and Snowboard Club (CSSC), and also a founding member/president of the Design Engineering Collaborative (DEC) at UC Berkeley.
Graduate Student Researcher
David Jeffery Colby
Undergraduate Student Researcherdavcal12@berkeley.edu
David is a senior Physics major assisting on the development of the LabView control system for the Pebble-Bed Heat Transfer Experiment (PB-HTX) during Summer 2015.
From May 2014 to August 2015 he managed the network, printer, and the recycling at Kidd, which is one of the boarding house units of the Berkeley Student Cooperative. He graduated from Hercules High School in Hercules, CA and has been at the University of California – Berkeley for three years since then.
David is involved in the Compass Physics Project and the Cal NERDS UC LEADS Program.
David Jeffery Colby
Undergraduate Student Researcher
Undergraduate Student Researcheraj.email@example.com
Alan Yamanaka started working in the Thermal Hydraulics group during the summer of his 2nd year at UC Berkeley. Alan has machined parts for the experiment, helped with the construction of the CTAH experiment, and assisted with the maintenance and experimental testing of the CIET experiment. He has also led a separate effects test on the CIET check valve to evaluate and optimize its performance.
Alan received his B.S. in Nuclear Engineering from UC Berkeley in May 2015 and continued to work in the TH group until August 2015 . Alan currently works at Los Alamos National Laboratory as a nuclear criticality safety analyst.
Alan was the secretary and a member of the student section of the American Nuclear Society at UC Berkeley. Alan enjoys going to the movies, playing board games and video games, reading, experiencing the food the world has to offer, and trying new things. He is also a fan of the NBA.
Undergraduate Student Researcher
Hongbing is currently involved in design and research on Fuel Handling System (FHS) of High Temperature Reactor-Pebblebed Modules (HTR-PM). His research interests include computation fluids dynamics (CFD), pneumatic transportation and high temperature gas cooled reactor (HTGR). He got his B.S. in Mechanical Engineering from Tsinghua University in 2011. Now he is a PhD student in Dept. of Mechanical Engineering, Tsinghua University.
- Hongbing Liu, Dong Du, Zandong Han, Yirong Zou and Jiluan Pan. Dynamic Analysis and Application of Fuel Elements Pneumatic transportation in a Pebble Bed Reactor. Energy 2015; 79:33-39.
- Hongbing Liu, Ayada He, Dong Du, Xin Wang and Haiquan Zhang. A Deceleration System for Near-diameter Spheres in Pipeline Transportation in a Pebble Bed Reactor based on the Resistance of a Pneumatic Cushion. Nuclear Engineering and Design 2014; 275: 61-68.
- Hongbing Liu, Peng Shen, Dong Du, Xin Wang and Haiquan Zhang. Modeling of Fuel Elements Cycling System in Pebble Bed Reactor Based on Timed Places Control Petri Nets. Energy and Power Engineering 2013; 5:510-516.
- Hongbing Liu, Dong Du, Peng Shen. Method for Fast-filling Fuel-Buffering System with Helium in a Pebble-bed Reactor. 2015 ANS Annual Meeting.
- Hongbing Liu, Dong Du, Peng Shen. Method for Detecting Stuck Fuel Element in a Pebble-bed Reactor. 2015 ANS Annual Meeting.
Zhangpeng is involved in performing integral effects experiments for thermal hydraulics code validation, as part of a project to develop the technical basis for design and licensing of fluoride-salt-cooled, high-temperature reactors (FHRs). Furthermore, he has developed the FHR advanced natural circulation analysis (FANCY) code for assessment of passive decay heat removal capability and safety analysis of these innovative system designs. Code-to-code comparison with established thermal hydraulic system codes such as RELAP5, and validation against experimental data from UCB’s Compact Integral Effects Test facility, are performed. He is currently a PhD candidate from Department of Nuclear Science and Technology in Xi’an Jiaotong University (China) and has some experience in coupling neutronics and thermal hydraulics for analysis of molten salt reactor experiment (MSRE) by using MCNP5 and in house subchannel analysis code and also performs CFD analysis of air condensing inside containment in severe accident
Zhangpeng enjoys swimming, hiking, skiing, traveling and badminton.