UC Berkeley TH Reports
Integrated FHR Technology Development: Tritium Management, Materials Testing, Salt Chemistry Control, Thermal Hydraulics and Neutronics, Associated Benchmarking and Commercial Basis (UCBTH-18-001)
C.W. Forsberg, P.F. Peterson, K. Sridharan, Lin-wen Hu, M. Fratoni, A. Kant Prinja, “Integrated FHR Technology Development: Tritium Management, Materials Testing, Salt Chemistry Control, Thermal Hydraulics and Neutronics, Associated Benchmarking and Commercial Basis” Department of Nuclear Engineering, U.C. Berkeley, Report UCBTH-18-001, October 2018.
Cyber Security in Nuclear Power Plants: Insights for Advanced Nuclear Technologies (UCBTH-17-004)
Christopher Poresky, Charalampos Andreades, James Kendrick, and Per Peterson, “Cyber Security in Nuclear Power Plants: Insights for Advanced Nuclear Technologies,” Department of Nuclear Engineering, U.C. Berkeley, Report UCBTH-17-004, September 2017.
Frequency Response Testing in the CIET Facility (UCBTH-17-002)
Christopher M. Poresky “Frequency Response Testing in the CIET Facility,” Department of Nuclear Engineering, U.C. Berkeley, May 2017.
Cyber Security in Civilian Aviation: Insights for Advanced Nuclear Technologies (UCBTH-17-001)
Charalampos Andreades, James Kendrick, Chris Poresky, Per Peterson “Cyber Security in Civilian Aviation: Insights for Advanced Nuclear Technologies,” Department of Nuclear Engineering, U.C. Berkeley, April 2017.
Simulation Methods for the Characterization of Coiled-Tube Gas Heaters (UCBTH-16-003)
Andrew Greenop, Per Peterson, “Simulation Methods for the Characterization of Coiled-Tube Gas Heaters,” Department of Nuclear Engineering, U.C. Berkeley, December 2016.
Offshore co-generation of electricity and desalinated water: Trident (UCBTH-16-001)
Alex Shrier, Junghyun Bae, Chao Yin, “Offshore co-generation of electricity and desalinated water: Trident,” Department of Nuclear Engineering, U.C. Berkeley, April 2016.
Instrumentation and Controls Development for the Compact Integral Effects Test Facility (UCBTH-15-006)
Rohit Upadhya and James Kendrick, “Instrumentation and Controls Development for the Compact Integral Effects Test Facility,” Department of Nuclear Engineering, U.C. Berkeley, September 2015.
Control Blade Insertion Dynamics in Pebble-Bed Fluoride-Salt-Cooled High Temperature Reactors (UCBTH-15-005)
Grant Buster, Ryan Sawadichai, Michael Laufer, and Per F. Peterson, “Control Blade Insertion Dynamics in Pebble-Bed Fluoride-Salt-Cooled High Temperature Reactors,” Department of Nuclear Engineering, U.C. Berkeley, 2015.
Fracture Analysis of Reduced Diameter Spherical Graphite Fuel Elements under Diametrical Loading Conditions (UCBTH-15-004)
Michael Laufer, Grant Buster, and Per F. Peterson, “Fracture Analysis of Reduced Diameter Spherical Graphite Fuel Elements under Diametrical Loading Conditions,” Department of Nuclear Engineering, U.C. Berkeley, 2015.
X-Ray Pebble Recirculation Experiment (X-PREX) Design and Initial Experimental Results (UCBTH-15-002)
Michael Laufer, Grant Buster, “X-Ray Pebble Recirculation Experiment (X-PREX) Design and Initial Experimental Results,” Department of Nuclear Engineering, U.C. Berkeley, 2015.
Design, Fabrication and First Experimental Results from the Compact Integral Effects (CIET 1.0) Test Facility in Support of Fluoride-Salt-Cooled, High-Temperature Reactor Technology (UCBTH-14-009)
Jeffrey E. Bickel, Andrew J. Gubser, James Kendrick, Raluca O. Scarlat, Rohit Upadhya, Nicolas Zweibaum, and Per F. Peterson, “Design, Fabrication and First Experimental Results from the Compact Integral Effects Test (CIET 1.0) Facility in Support of Fluoride-Salt-Cooled, High-Temperature Reactor Technology,” Department of Nuclear Engineering, U.C. Berkeley, 2014.
Design, Manufacture, Modeling and Testing of 316 SS Diffusion Bonded Tube-sheet Joints and In-Service Inspection Methods for the Mk1 PB-FHR CTAHs: NE 170 – Senior Design Project (UCBTH-14-005)
Grant Buster, Nathan Pardede, and Tung Phan, “Design, Manufacture, Modeling and Testing of 316 SS Diffusion Bonded Tube-sheet Joints and In-Service Inspection Methods for the Mk1 PB-FHR CTAHs: NE 170 – Senior Design Project,” Department of Nuclear Engineering, U.C. Berkeley, May 15, 2014.
Structural Design and Modular Construction Approach for the Mk1 PB-FHR: NE 170 – Senior Design Project (UCBTH-14-003)
Jaben Root, Sea Hong, Huu Duy Nguyen, and Diasuke Kazama, “Structural Design and Modular Construction Approach For the Mk1 PB-FHR: NE 170 – Senior Design Project,” Department of Nuclear Engineering, U.C. Berkeley, June 20, 2014.
Technical Description of the ‘Mark 1’ Pebble-Bed Fluoride-Salt-Cooled High-Temperature Fluoride-Salt-Cooled High-Temperature Reactor (PB-FHR) Power Plant (UCBTH-14-002)
C. Andreades, A. T. Cisneros, J.K. Choi, A.Y.K. Chong, D. L. Krumwiede, L.R. Huddar, K. Huff, M. R. Laufer, M.O. Munk, R.O. Scarlat, J. Seifried, N. Zweibaum, E. Greenspan, and P. F. Peterson, “Technical Description of the ‘Mark 1’ Pebble-Bed Fluoride-Salt-Cooled High-Temperature Reactor (PB-FHR) Power Plant,” Department of Nuclear Engineering, U.C. Berkeley, September 30, 2014.
Application of Finite Element Modeling (FEM) and Experiments to Study the Mk1 PB-FHR Center Reflector: NE 170 – Senior Design Project (UCBTH-14-001)
Brigette Badro, Cameron Bailey, Stephen Kaplan, Hin Lee, and Mariam Malek, “Application of Finite Element Modeling (FEM) and Experiments to Study the Mk1 PB-FHR Center Reflector: NE 170 – Senior Design Project,” Department of Nuclear Engineering, U.C. Berkeley, May, 2014.
PB-FHR Reserve Shutdown System (UCBTH-12-008)
S. Chang, A. Gonzalez, J. Kong, and N. Satterlee, “PB-FHR Reserve Shutdown System,” Department of Nuclear Engineering, U.C. Berkeley, May 4, 2012.
Boron Use and Control in PWRs and FHRs (UCBTH-12-007)
A. Monterrosa, A. Iyengar, A. Huynh, C. Madaan, “Boron Use and Control in PWRs and FHRs,” Department of Nuclear Engineering, U.C. Berkeley, May 5, 2012.
Tritium Management Approach for FHRs Using Supercritical Steam, Open-Air Brayton, and Closed Brayton Power Cycles (UCBTH-12-006)
M. Atlas, N. Brickner, W. Chen, D. Tsai, “Tritium Management Approach for FHRs Using Supercritical Steam, Open-Air Brayton, and Closed Gas Brayton Power Cycles,” Department of Nuclear Engineering, U.C. Berkeley, May 5, 2012.
Lithium Isotope Enrichment: Feasible Domestic Enrichment Alternatives (UCBTH-12-005)
T. Ault, K. Brozek, L. Fan, M. Folsom, J. Kim, and J. Zeismer, “Lithium Isotope Enrichment: Feasible Domestic Enrichment Alternatives,” Department of Nuclear Engineering, U.C. Berkeley, May 5, 2012.
Fluoride-Salt-Cooled, High-Temperature Reactor (FHR) Development Roadmap and Test Reactor Performance Requirements White Paper (UCBTH-12-004)
D. Carpenter, et al., “Fluoride-Salt-Cooled, High-Temperature Reactor (FHR) Development Roadmap and Test Reactor Performance Requirements White Paper,” Department of Nuclear Engineering, U.C. Berkeley, June, 2013.
Fluoride-Salt-Cooled High Temperature Reactor (FHR) Materials, Fuels and Components White Paper (UCBTH-12-003)
G. Cao, et al., “Fluoride-Salt-Cooled High Temperature Reactor (FHR) Materials, Fuels and Components White Paper,” Department of Nuclear Engineering, U.C. Berkeley, July, 2013.
Fluoride-Salt-Cooled, High-Temperature Reactor (FHR) Methods and Experiments Program White Paper (UCBTH-12-002)
A. Cisneros, et al., “Fluoride-Salt-Cooled, High-Temperature Reactor (FHR) Methods and Experiments Program White Paper,” Department of Nuclear Engineering, U.C. Berkeley, May, 2013.
Fluoride-Salt-Cooled, High-Temperature Reactor (FHR) Subsystems Definition, Functional Requirement Definition, and Licensing Basis Event (LBE) Identification White Paper (UCBTH-12-001)
A. Cisneros, et al., “Fluoride-Salt-Cooled, High-Temperature Reactor (FHR) Subsystems Definition, Functional Requirement Definition, and Licensing Basis Event (LBE) Identification White Paper,” Department of Nuclear Engineering, U.C. Berkeley, August 2013.
Status Update: Pebble Insertion and Extraction Methods for a Pebble Bed Salt Cooled Reactor Using Surrogate Materials (UCBTH-10-003)
M.R. Laufer J.E. Bickel, P.F. Peterson, “Status Update: Pebble Insertion and Extraction Methods for a Pebble Bed Salt Cooled Reactor Using Surrogate Materials,” Department of Nuclear Engineering, U.C. Berkeley, July 31, 2010.
Design of Fuel Testing and Qualification Capsules for the Pebble Bed Advanced High Temperature Reactor (UCBTH-10-002)
J. Gomez, M. Hay, J. Lee, B. Tam, “Design of Fuel Testing and Qualification Capsules for the Pebble Bed Advanced High Temperature Reactor,” Department of Nuclear Engineering, U.C. Berkeley, May 14, 2010.
Fluidic Diode Development and Optimization (UCBTH-10-001)
R. Burnett, D. Caso, and J. Tang, ” Fluidic Diode Development and Optimization,” Department of Nuclear Engineering, U.C. Berkeley, May 14, 2010.
Conceptual Design of the Intermediate Heat Exchanger (IHX) for the PB-AHTR (UCBTH-09-005)
H.J. Lim and P.F. Peterson, “Conceptual Design of the Intermediate Heat Exchanger (IHX) for the PB-AHTR,” Department of Nuclear Engineering, U.C. Berkeley, May 20, 2009.
Advanced Seismic Base Isolation Methods for Modular Reactors (UCBTH-09-004)
E. Blandford, E. Keldrauk, M. Laufer, M. Mieler, J. Wei, B. Stojadinovic, and P.F. Peterson, “Advanced Seismic Base Isolation Methods for Modular Reactors,” Departments of Civil and Environmental Engineering and Nuclear Engineering, U.C. Berkeley, September 30, 2009.
Utilization of Decoupled External Events Shield for Blast Load Protection of Nuclear Power Plants (UCBTH-09-003)
J. Wei, “Utilization of Decoupled External Events Shield for Blast Load Protection of Nuclear Power Plants,” Dept. of Civil and Environmental Engineering, U.C. Berkeley, May 21, 2009.
Neutronic and Fuel Cycle Analysis for the Annular Pebble-Bed Advanced High Temperature Reactor (UCBTH-09-002)
B. Frisbie, J. La Barba, F. Rangel, C. Schopke, V. Singh, and R. Stroberg, “Neutronic and Fuel Cycle Analysis for the Annular Pebble-Bed Advanced High Temperature Reactor,” 2009 NE 170 Senior Design Project, U.C. Berkeley, May 19, 2009.
Reactor Safety and Mechanical Design for the Annular Pebble-Bed Advanced High-Temperature Reactor (UCBTH-09-001)
R. Hong, S. Huber, K. Lee, P. Purcell, S. Margossian, and J.D. Seelig, “Reactor Safety and Mechanical Design for the Annular Pebble-Bed Advanced High Temperature Reactor,” 2009 NE 170 Senior Design Project, U.C. Berkeley, May 19, 2009.
Risk-informed Design Guidance for Advanced Reactor Concepts: A Case Study of the Pebble Bed Advanced High Temperature Reactor (UCBTH-08-003)
E. Blandford, “Risk-informed Design Guidance for Advanced Reactor Concepts: A Case Study of the Pebble Bed Advanced High Temperature Reactor” Masters Report, U.C. Berkeley, 2008.
Development and applications of methodologies for the neutronic design of the Pebble Bed Advanced High Temperature Reactor (PB-AHTR) (UCBTH-08-002)
M. Fratoni, “Development and applications of methodologies for the neutronic design of the Pebble Bed Advanced High Temperature Reactor (PB-AHTR),” PhD Dissertation, U.C.Berkeley, December 2008.
A Modular Pebble-Bed Advanced High Temperature Reactor (UCBTH-08-001)
D. Caron, A. Cheng , T. Dhanania, C. Eastridge, K. Evans, T. Fei, M. Foxe, D. Johnson, E. Keldrauk, Z. Kline, A. Mai, J. Mintz, D. Ogata, E. Park, K. Pham, B. Reinhart, J. Rodriguez, M. Solom, T. Visnjic, C. Wootton, C. Zhao, C. Xu, “A Modular Pebble-Bed Advanced High Temperature Reactor,” NE-170 Senior Design Project, UC Berkeley Thermal Hydraulics Laboratory, May 16, 2008.
Deep Burn Modular High Temperature Reactors: Project Summary Report (UCBTH-07-007)
E. Greenspan, P.F. Peterson, M. Fratoni and A. Cisneros, “Deep Burn Modular High Temperature Reactors: Project Summary Report,” U.C. Berkeley, October 31, 2007.
Intermediate Heat Exchanger Dynamic Thermal Response Model (UCBTH-07-006)
Per F. Peterson, and Eugenio Urquiza Fernández, “Intermediate Heat Exchanger Dynamic Thermal Response Model,” U.C. Berkeley, August 31, 2007.
Tritium transport in very high temperature reactors for hydrogen production (UCBTH-07-005)
A. Jousse, “Tritium transport in very high temperature reactors for hydrogen production,” U.C. Berkeley, August 31, 2007.
Intermediate Heat Exchanger Dynamic Thermal Response Model (UCBTH-07-004)
Per F. Peterson, Aurelie Niquille, and Eugenio Urquiza Fernández, “Intermediate Heat Exchanger Dynamic Thermal Response Model,” U.C. Berkeley, May 31, 2007.
Capillary Tube and Shell Heat Exchanger Design for Helium to Liquid Salt Heat Transfer (UCBTH-07-003)
Per F. Peterson. “Capillary Tube and Shell Heat Exchanger Design for Helium to Liquid Salt Heat Transfer,” U.C. Berkeley, May 7, 2007.
Guidelines for Trade-Studies for Comparison of Liquid Salt and Helium Intermediate Coolants for the NGNP (UCBTH-07-002)
Per F. Peterson, “Guidelines for Trade-Studies for Comparison of Liquid Salt and Helium Intermediate Coolants for the NGNP,” U.C. Berkeley, February 20, 2007.
Modeling and Transient Analysis for the Pebble Bed Advanced High Temperature Reactor (PB-AHTR) (UCBTH-07-001)
Alain Griveau, “Modeling and Transient Analysis for the Pebble Bed Advanced High Temperature Reactor (PB-AHTR),” U.C. Berkeley, February, 2007.
Potential Applications for Liquid Silicon Melt Infiltrated (LSI) Composites for the High-Temperature Sulfur-Iodine (S-I) Process (UCBTH-06-004)
Jens Schmidt, “Potential Applications for Liquid Silicon Melt Infiltrated (LSI) Composites to the High-Temperature Sulfur-Iodine (S-I) Process,” U.C. Berkeley, December 2006.
RELAP-5 Loss of Forced Cooling (LOFC) Transient Response Modeling for the PB-AHTR (UCBTH-06-003)
Alain Griveau and Per F. Peterson, “RELAP-5 Loss of Forced Cooling (LOFC) Transient Response Modeling for the PB-AHTR,” U.C. Berkeley, Sept. 17, 2006.
The LM-LS experiment: investigating corrosion control, in Liquid Fluoride Salts, by Liquid Alkali Metal (UCBTH-06-002)
Blandine Laurenty, “The LM-LS experiment: investigating corrosion control, in Liquid Fluoride Salts, by Liquid Alkali Metal,” UC Berkeley, January 2006.
Preliminary study of the Pebble-Bed Advanced High Temperature Reactor (UCBTH-06-001)
François-Paul Fardin and Fabien Koenig, “Preliminary study of the Pebble-Bed Advanced High Temperature Reactor,” U.C. Berkeley, August 2006.
Functional Requirements Overview For a 50-MW(t) Liquid-Salt Intermediate Loop for NGNP (UCBTH-05-007)
Per F. Peterson, H. Zhao, and G. Fukuda, “Functional Requirements Overview For a 50-MW(t) Liquid-Salt Intermediate Loop for NGNP,” U.C. Berkeley, December 29, 2005.
C/SiC Heat Exchanger Heat Transfer and Safety Analysis (UCBTH-05-006)
Per F. Peterson, Haihua Zhao, Blandine Laurenty, and Grant Fukuda, “C/SiC Heat Exchanger Heat Transfer and Safety Analysis,” U.C. Berkeley, September 30, 2005.
Preliminary Design Description for a First-Generation Liquid-Salt VHTR with Metallic Vessel Internals (AHTR-MI) (UCBTH-05-005)
Per F. Peterson and Haihua Zhao, “Preliminary Design Description for a First-Generation Liquid-Salt VHTR with Metallic Vessel Internals (AHTR-MI),” U.C. Berkeley, December 29, 2005.
C/SiC HX Thermal and Mechanical Analysis (UCBTH-05-004)
Wensheng Huang, Per F. Peterson, and Haihua Zhao, “C/SiC HX Thermal and Mechanical Analysis,” U.C. Berkeley, September 30, 2005.
An Optimized System for Advanced Multi-Effect Distillation (AMED) Using Waste Heat from Closed Gas Brayton Cycles (UCBTH-05-003)
Per F. Peterson and Haihua Zhao, “An Optimized System for Advanced Multi-Effect Distillation (AMED) Using Waste Heat from Closed Gas Brayton Cycles,” U.C. Berkeley, January 31, 2006.
Interstage Heating and Cooling Options for High Temperature Helium Brayton Cycles (UCBTH-05-002)
Haihua Zhao and Per F. Peterson, “Interstage Heating and Cooling Options for High Temperature Helium Brayton Cycles, U.C. Berkeley, May 10, 2005.
Metal and Concrete Inputs for Several Nuclear Power Plants (UCBTH-05-001)
Per F. Peterson, Haihua Zhao, and Robert Petroski, “Metal And Concrete Inputs For Several Nuclear Power Plants,” U.C. Berkeley, February 4, 2005.
Conceptual Design for a 50 MW(t) Metallic Intermediate Heat Exchanger for the Next Generation Nuclear Plant (UCBTH-04-001)
Per F. Peterson, H. Zhao, D. Huang, and G. Fukuda, “Conceptual Design for a 50 MW(t) Metallic Intermediate Heat Exchanger for the Next Generation Nuclear Plant,” U.C. Berkeley, December 20, 2004.
Passive Decay Heat Removal for the Advanced High Temperature Reactor (UCBTH-03-005)
Per F. Peterson and Haihua Zhao, “Passive Decay Heat Removal for the Advanced High Temperature Reactor,” U.C. Berkeley, February 12, 2004.
Comparison of Molten Salt and High-Pressure Helium for the NGNP Intermediate Heat Transfer Fluid (UCBTH-03-004)
Per F. Peterson, H. Zhao, and G. Fukuda, “Comparison of Molten Salt and High-Pressure Helium for the NGNP Intermediate Heat Transfer Fluid,” U.C. Berkeley, December 5, 2003.
Development approaches for the Advanced High Temperature Reactor (UCBTH-03-003)
Per F. Peterson, “Development approaches for the Advanced High Temperature Reactor,” U.C. Berkeley, December 4, 2003.
A Reference 2400 MW(t) Power Conversion System Point Design for Molten-Salt-Cooled Fission and Fusion Energy Systems (UCBTH-03-002)
H. Zhao and Per F. Peterson, “A Reference 2400 MW(t) Power Conversion System Point Design for Molten-Salt-Cooled Fission and Fusion Energy Systems,” U.C. Berkeley, February 25, 2004.
Development of liquid-silicon-impregnated C/C-SiC composites for high-temperature heat transport (UCBTH-03-001)
Per F. Peterson, “Development of liquid-silicon-impregnated C/C-SiC composites for high-temperature heat transport, U.C. Berkeley, October 1, 2003.