Brenden Heidrich Department Manager for Irradiation Testing Research Areas:
Energy; Gamma and X-ray spectroscopy; High Temperature Test Laboratory; Materials Characterization; Materials Properties and Performance; Monte Carlo Simulations; Neutron diffraction and imaging; Neutron/ion irradiation damage of nuclear materials; Nuclear; Nuclear Engineering; Nuclear fuel cycle; Nuclear Fuel Performance, Management and Disposition; Nuclear Fuels; Nuclear instrumentation; Nuclear Physics; Radiation interaction with materials; Radiation Measurements; Radiation Tolerant Materials; Reactor Physics (Neutron Transport); Space Nuclear Power and Isotope Technologies; University Partnerships Biography:
Dr. Heidrich is a senior nuclear engineer at the Idaho National Laboratory (INL) focusing on neutron irradiation experiment management at the Advanced Test Reactor (ATR) and the Transient REActor Test facility (TREAT). Currently, he manages the Irradiation Testing Department for the Nuclear Fuels and Materials Division and serves as the irradiation chief scientist for the Nuclear Science User Facilities (NSUF). Past responsibilities at INL include managing the Post-Irradiation Examination Department, leading the in-pile instrumentation development program, and performing R&D technology analysis. Dr. Heidrich also advises the university scientific infrastructure funding program for the Department of Energy, Office of Nuclear Energy.
Before coming to INL in 2014, he was the assistant director at the Radiation Science and Engineering Center, Pennsylvania State University. While at PSU he taught reactor physics and nuclear security courses and supervised graduate students. Before Penn State, he served in the U.S. Navy as a nuclear reactor operator on the USS Enterprise.
Education: Ph.D., Energy and Mineral Engineering - Pennsylvania State University M.S., Nuclear Engineering - Pennsylvania State University B.S., Nuclear Engineering - Pennsylvania State University Affiliations: American Nuclear Society - Isotopes and Radiation Division executive committee
- Human Factors, Instrumentation and Control Division executive committee
- Professional Engineering Examination Committee
Also active in the Test, Research, and Training Reactor community (TRTR). Publications: Peer-Reviewed Articles
Garrett, S.L.; Smith, J.A.; Smith, R.W.M.; Heidrich, B.J.; Heibel, M.D.; and Agarwal, V., Fission-Powered In-Core Thermoacoustic Sensor (INL/JOU-16-37610), Applied Physics Letters, vol. 108, 2016.
Garrett, S.L.; Smith, J.A.; Smith, R.W.M.; Heidrich, B.J.; and Heibel, M.D., Using the Sound of Nuclear Power (INL/JOU-15-37508), Nuclear Technology, vol. 195, 353–362, 2016.
Bender, S.; Heidrich, B.J.; and Ünlü, K., Compton Suppressed LaBr3 for Use in Nondestructive Spent Fuel Assay, Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, vol. 784, 474–481, 2015.
Bender, S.; Heidrich, B.J.; and Ünlü, K., Compton Suppressed LaBr3 Detection Sytem for Use in Nondestructive Spent Fuel Assay, Penn State Breazeale Nuclear Reactor: 60 Years of Nuclear Research, Teaching, Outreach, and Service, 50–53, 2015.
Heidrich, B.J.; Johnsen, A.M.; Bascom, A.J.; Krizmanich, J.; and Wargon, M.D., University Research Reactor Production of 67Cu via Long-Term Irradiation, Penn State Breazeale Nuclear Reactor: 60 Years of Nuclear Research, Teaching, Outreach, and Service, 79–82, 2015.
Johnsen, A.M.; Heidrich, B.J.; Durrant, C.B.; Bascom, A.J.; and Ünlü, K., Reactor Production of 64Cu and 67Cu Using Enriched Zinc Target Material, Journal of Radioanalytical and Nuclear Chemistry, vol. 305, 61–71, 2015.
Johnsen, A.M.; Heidrich, B.J.; Durrant, C.B.; Bascom, A.J.; and Ünlü, K., Research Reactor Production and Purification of 64Cu and 67Cu Using Enriched Zinc Target Materials, Penn State Breazeale Nuclear Reactor: 60 Years of Nuclear Research, Teaching, Outreach, and Service, 75–78, 2015.
Uçar, D.; Ünlü, K.; and Heidrich, B.J., Thermal-Hydraulics Analysis of a New Core-Moderator Assembly Design for the Penn State Breazeale Reactor Using the ANSYS Fluent Code, Penn State Breazeale Nuclear Reactor: 60 Years of Nuclear Research, Teaching, Outreach, and Service, 66–74, 2015.
Uçar, D.; Ünlü, K.; Heidrich, B.J.; Ivanov, K. N.; and Avramova, M.N., Neutronic Design and Analyses of a New Core-Moderator Assembly and Neutron Beam Ports for the Penn State Breazeale Reactor, Penn State Breazeale Nuclear Reactor: 60 Years of Nuclear Research, Teaching, Outreach, and Service, 54–62, 2015.
Ünlü, K.; Vijaykrishnan, N.; Irwin, M. J.; Heidrich, B.J.; Ramakrishnan, K., Testing Fast Neutron-Induced Soft Errors in Semiconductor Memories, Penn State Breazeale Nuclear Reactor: 60 Years of Nuclear Research, Teaching, Outreach, and Service, 20–23, 2015.
Bender, S.; Durrant, C.; Heidrich, B.; and Ünlü, K., Determination of Penn State Breazeale Reactor Fuel Element Burnup by Non-Destructive Assay, Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, June 2014.
Olawoyin, R.; Heidrich, B.; Oyewole, S.; Okareh, O.; and McGlothlin, C., Chemometric Analysis of Ecological Toxicants in Petrochemical and Industrial Environments, Chemosphere, vol. 112, 114–119, 2014.
Olawoyin, R.; Oyewole, S. A.; McGlothlin, C. W.; Heidrich, B.; Abegunde, S. O.; Nieto, A.; and Okareh, O.T., Characteristic Fingerprints of Polycyclic Aromatic Hydrocarbons & Total Petroleum Hydrocarbons Pollution in Petrochemical Areas, International Journal of Environmental Pollution and Solutions, vol. 2, 1–19, 2014.
Ünlü, K.; and Heidrich, B.J., The Penn State Breazeale Reactor, History, Development and Future of TRIGA Research Reactors, IAEA Technical Report no. 482, 45–60, 2014.
Heidrich, B.; Oyewole, S.; and Olawoyin, R., An Assessment of the Efficiency of Extended Power Up-Rates at US Boiling Water Reactors, Nuclear Technology, vol. 182, 13–25, 2013.
Conference Proceedings and Transactions
Smith, J.A.; Garrett, S.L.; Heidrich, B.J.; and Heibel, M.D., Nuclear Powered Thermoacoustic Sensor Unfortunate Event Made Right (Smelly???), presented at the 173rd meeting of the Acoustical Society of America and the 8th Forum Acusticum, Boston, MA, June 25, 2017.
Heidrich, B.J., Research and Development Capabilities available through the Nuclear Science User Facilities (INL/CON-16-37582), Transactions of the American Nuclear Society, presented at the annual meeting, New Orleans, LA, June 12–16, 2016.
Heidrich, B.J., The Role of the Nuclear Science User Facilities Program in Nuclear Energy Research & Development (INL/CON-16-37584), Transactions of the American Nuclear Society, presented at the annual meeting, New Orleans, LA, June 12–16, 2016.
Smith, J.A.; Garrett, S.L.; Heibel, M.D.; Agarwal, V.; and Heidrich, B.J., Progress in Developing An In-Pile Acoustically Telemetered Sensor Infrastructure (INL/CON-16-37719), presented at the Top Fuel Meeting (ANS), Boise, ID, September 16, 2016.
Smith, J.A.; Garrett, S.L.; Heibel, M.D.; Agarwal, V.; and Heidrich, B.J., Wireless In-Core Acoustic Telemetry and Self-Powered Sensing, presented at the Top Fuel Meeting (ANS), Boise, ID, September 16, 2016.
Smith, J.A.; Heidrich, B.J.; Agarwal, V.; Heibel, M.D.; Smith, R.W.M.; and Garrett, S.L., Using the Sound of Nuclear Power (INL/CON-15-37502), presented at the 171st meeting of the Acoustical Society of America, Salt Lake City, UT, May 23, 2016.
Garrett, S.L.; Smith, R.W.M.; Smith, J.A.; and Heidrich, B.J., Design and Fabrication of a Fission-Powered Thermoacoustic In-Core Sensor (INL/CON-15-37503), presented at the 171st meeting of the Acoustical Society of America, Salt Lake City, UT, May 23, 2016.
Johnsen, A.M.; Heidrich, B.J.; Durrant, C.B.; Bascom, A.J.; and Ünlü, K., Research Reactor Production and Purification of 64Cu and 67Cu using Enriched Zinc Isotopes, presented at the 8th International Conference on Isotopes, Chicago, IL, August 24–29, 2014.
Heidrich, B.J.; Trump, M.; and Bascom, A.J., Operational Impacts of High-Reactivity In-Core Irradiation Samples, Transactions of the American Nuclear Society, presented at the November 2013 conference, Washington, DC.
Heidrich, B.J.; Johnsen, A.M.; and Bascom, A.J., Fast Neutron Irradiation Fixture Design for a Mark III TRIGA Reactor, Transactions of the American Nuclear Society, presented at the November 2013 conference, Washington, DC.
Heidrich, B.J., Advances in Radioargon Production at the Radiation Science and Engineering Center at Penn State University, Transactions of the American Nuclear Society, presented at the June 2012 conference, Chicago, IL.
Sahin, D.; Heidrich, B.J.; and Ünlü, K., Penn State Online Reactor Experiments Software, Transactions of the American Nuclear Society, presented at the June 2012 conference, Chicago, IL.
Johnsen, A.M.; Durrant, C.B.; Heidrich, B.J.; and Ünlü, K., Reactor Based Production and Purification of 64Cu and 67Cu, Transactions of the American Nuclear Society, presented at the June 2012 conference, Chicago, IL.
Fanton, M.; Robinson, J.; LaBella, M.; Cavalero, R.; Heidrich, B.J.; Hollander, M.; Hughes, Z.; and Trumbull, K., Response of Graphene-Based Field Effect Devices Exposed to Gamma and Neutron Irradiation, presented at the Electronic Materials Conference, The Minerals, Metals and Materials Society, University of California, Santa Barbara, CA, June 22–24, 2011.
Heidrich, B.J., Twenty Years of Experience with a Digital Control System at The Pennsylvania State University Research Reactor, Transactions of the American Nuclear Society, presented at the November 2011 conference, Washington, DC.
Heidrich, B.J., Radiation Science and Engineering Center Upgrades at The Pennsylvania State University, Transactions of the American Nuclear Society, presented at the June 2011 conference, Miami, FL.
Heidrich, B.J., A Reliability Impact Analysis of Extended Power Up-Rates at US Boiling Water Reactors, Transactions of the American Nuclear Society, presented at the June 2011 conference, Miami, FL.
Ünlü, K.; and Heidrich, B.J., Development of Innovative Methods of Radioactive Isotope Production at the Penn State University Radiation Science and Engineering Center, presented at the annual meeting of the American Chemical Society, Boston, MA, August 23–26, 2010.
Ünlü, K.; Heidrich, B.J.; and Trump, M., Challenges and Lessons-Learned During the Reactor Pool Repair at the Penn State Breazeale Reactor, presented at the technical meeting of the International Atomic Energy Agency: Assessment of Core Structural Materials and Surveillance Programme of Research Reactors, Vienna, Austria, June 14–18, 2010.
Ünlü, K.; and Heidrich, B.J., Relicensing and Utilization of the Penn State Breazeale Reactor, presented at the technical meeting of the International Atomic Energy Agency: Assessment of Core Structural Materials and Surveillance Programme of Research Reactors, Vienna, Austria, June 14–18, 2010.
Karriem, V.; Puente Espel, F.; Avramova, M.; Heidrich, B.J.; and Ünlü, K., Further Development of TRIGSIMS Code System for Penn State Breazeale Reactor Fuel Management, Transactions of the American Nuclear Society, presented at the June 2010 conference, San Diego, CA.
Karriem, V.; Puente Espel, F.; Avramova, M.; Heidrich, B.J.; and Ünlü, K., Thermal-Hydraulic Modeling of Penn State Breazeale Reactor for Safety and Fuel Management Analysis, Transactions of the American Nuclear Society, presented at the June 2010 conference, San Diego, CA.
Heidrich, B.J.; Hochreiter, L.; and Sears, C.F., Improvements to the Penn State Reactor Thermal Power Calibration, Transactions of the American Nuclear Society, presented at the November 2002 conference, Washington, DC.
Presentations: Heidrich, B.J., Irradiation Tools for NSUF Materials Research (INL/CON-17-42048), presented at the annual meeting of the National Organization of Test, Research and Training Reactors, San Diego, CA, September 20, 2017.
Heidrich, B.J., The Role of NSUF and Nuclear Research and Development (INL/CON-16-39256), presented at the CAES university collaboration meeting, Idaho Falls, ID, September 11, 2017.
Heidrich, B.J., NSUF R&D Capabilities Activities Review (INL/MIS-17-42781), presented at the NSUF Science Review Board, Idaho Falls, ID, August 2, 2017.
Heidrich, B.J., Thermal Hydraulics Workshop (INL/MIS-17-42058), presented at the NSUF/GAIN Nuclear Thermal Hydraulics Workshop, Idaho Falls, ID, July 13, 2017.
Heidrich, B.J., Infrastructure Management Program Review (INL/MIS-17-42058), presented at the NSUF Partner Facilities Working Group meeting, Idaho Falls, ID, May 24, 2017.
Heidrich, B.J., The Role of NSUF in Nuclear Energy Research and Development (INL/CON-16-39256), videoconference with Montana State University, Idaho Falls, ID, April 3, 2017.
Heidrich, B.J., Ion Beam Irradiation Roadmapping Workshop (INL/CON-16-39644), presented at the Ion Beam Roadmap Workshop, Idaho Falls, ID, March 8, 2017.
Heidrich, B.J., Infrastructure Management Program (INL/MIS-15-35466 rev. 2), presented to the Nuclear Energy Advisory Committee, International Subcommittee, February 22, 2017.
Heidrich, B.J., University Research Capabilities (INL/CON-16-40196), presented at the ANS annual meeting, Las Vegas, NV, November 7, 2016.
Heidrich, B.J., Digital Tools for NSUF Researchers (INL/MIS-16-40195), presented at the ANS annual meeting, Las Vegas, NV, November 5, 2016.
Heidrich, B.J., Ion Beam Investment Options Workshop (INL/CON-16-39644), presented at the Conference on Application of Accelerators in Research and Industry, Fort Worth, TX, November 2, 2016.
Heidrich, B.J., NSUF Irradiation Experiments (INL/LTD-16-40338), presented at the NSUF annual program review, Germantown, MD, November 1, 2016.
Heidrich, B.J., NSUF Plans and Needs for In-Pile Sensors and Characterization (INL/CON-16-39256), presented at the Advanced Sensors and Instrumentation annual review, October 12, 2016.
Heidrich, B.J., Utilization of University Research Reactors to Support Irradiation Testing (INL/CON-16-38605), presented at the annual meeting of the National Organization of Test, Research and Training Reactors, Albuquerque, NM, August 23, 2016.
Heidrich, B.J., Nuclear Fuels & Materials Laboratory and Nuclear Energy Infrastructure Database Overview (INL/CON-16-39256), presented to the NSUF Science Review Board, Idaho Falls, ID, August 17, 2016.
Heidrich, B.J., Research and Development Capabilities available through the Nuclear Science User Facilities (INL/CON-16-39256), presented at the Nuclear Innovation Bootcamp, Berkeley, CA, August 10, 2016.
Heidrich, B.J., Capabilities and Tools for NE Researchers (INL/MIS-16-39260), teleconference with EPRI, Idaho Falls, ID, August 3, 2016.
Herring, N.; and Heidrich, B.J., Web-Based Irradiation Toolkit to Assist NSUF Researchers (INL/CON-16-39408), INL Intern Expo, Idaho Falls, ID, July 21, 2016.
Heidrich, B.J., Research and Development Capabilities available through the Nuclear Science User Facilities (INL/MIS-16-37818), presented at the Modeling, Experiment, and Validation School, Oak Ridge National Laboratory, Idaho Falls, ID, July 20, 2016.
Heidrich, B.J., A Searchable Database of R&D Infrastructure and Capabilities for Nuclear Energy Researchers (INL/CON-15-36406), presented at the annual meeting of the National Organization of Test, Research and Training Reactors, Brewster, MA, October 5–9, 2015.
Heidrich, B.J., The NSUF and the Testing of Irradiated Materials in University Laboratories, presented at the 14th Annual Penn State Radiation Safety Roundtable, University Park, PA, September 14–16, 2015.
Heidrich, B.J., The NSUF and the Role of the University Research Reactor in Nuclear Energy Research and Development, presented at the 1st Annual Penn State Research Reactor Safety Roundtable, University Park, PA, September 17–18, 2015.
Uçar, D.; Ünlü, K.; and Heidrich, B.J., Thermal-Hydraulics Analysis of a New Core-Moderator Assembly Design for the Penn State Breazeale Reactor Using ANSYS Fluent Code, presented at the PHYSOR 2014 meeting in Kyoto, Japan, September 28, 2014.
Uçar, D.; Ünlü, K.; Heidrich, B.J.; Ivanov, K.; and Avramova, M., Neutronic Designs and Analyses of a New Core-Moderator Assembly and Neutron Beam Ports for the Penn State Breazeale Reactor, presented at the PHYSOR 2014 meeting in Kyoto, Japan, September 28, 2014.
Olawoyin, R.; McGlothin, C.; and Heidrich, B.J., Potential Occupational Toxicity of Respirable Crystalline SiO2 from Hydro-Fracturing Operations in the US Shale Plays, presented at the International Congress on Environmental Health, Porto, Portugal, September 24–26, 2014.
Bender, S.; Heidrich, B.J.; and Ünlü, K., Compton Suppressed LaBr3 for Use in Nondestructive Spent Fuel Assay, presented at the Symposium on Radiation Measurements and Applications, University of Michigan, Ann Arbor, MI, June 9–12, 2014.
Bender, S.; Durrant, C.B.; Heidrich, B.J.; and Ünlü, K., Determination of Penn State Breazeale Reactor Fuel Element Burnup by Non-Destructive Assay, presented at the Symposium on Radiation Measurements and Applications, University of Michigan, Ann Arbor, MI, June 9–12, 2014.
Ünlü, K.; and Heidrich, B.J., Research, Education and Service Utilizations of Breazeale Nuclear Reactor at the Radiation Science and Engineering Center at The Pennsylvania State University, presented at the International Group on Research Reactors meeting, Daejeon, South Korea, October 13–18, 2013.
Heidrich, B.J.; and Trump, M., Adverse Operational Impacts of High Reactivity Irradiation Targets, presented at the annual meeting of the National Organization of Test, Research and Training Reactors, St. Louis, MO, September 23–26, 2013.
Bender, S.; Heidrich, B.J.; Durrant, C.B.; Sahin, D.; and Ünlü, K., Experimental Gamma Ray Burnup Analysis of Penn State TRIGA Used Fuel Rods for Validation of Reactor Core Neutronics Simulation, presented at the annual meeting of the Institute for Nuclear Materials Management, Palm Desert, CA, July 14–18, 2013.
Johnsen, A.M.; Durrant, C.B.; Heidrich, B.J.; and Ünlü, K., 64Cu and 67Cu Production and Purification Research at the Radiation Science and Engineering Center at The Pennsylvania State University, poster presentation at the International Conference on Nuclear and Radiochemistry (NRC-8) Como, Italy, September 16–21, 2012.
Heidrich, B.J., A Study of Nuclear Power Plant Reliability, 1987–2009, presented at the Electricity Markets Initiative Conference, University Park, PA, September 8, 2010.
Heidrich, B.J., Reactor Pool Leakage and Repair, presented at the annual meeting of the National Organization of Test, Research and Training Reactors, Cape Cod, MA, September 28–October 2, 2008.
Heidrich, B.J., Lessons Learned from a Stuck Fuel Element, presented at the annual meeting of the Test Research and Training Reactor Group, Lincoln City, OR, September 17–20, 2007.
Tippayakul, C.; Kriangchaiporn, N.; Ivanov, K.; Sears, C.F.; Morlang, G.M.; and Heidrich, B.J., Validation of the MCNP5 Core Model of the PSU Breazeale Research Reactor, presented at the Monte Carlo 2005 Topical Meeting, Chattanooga, TN, April 17–21, 2005.
Heidrich, B.J., TRIGA Reactor Control and Safety System Upgrade, presented at the annual meeting of the Test Research and Training Reactor Group, Germantown, MD, September 12–16, 2005.
|
