Carol Smidts Professor The Ohio State University Nuclear Reactor - - PowerPoint PPT Presentation

▶
carol smidts
SMART_READER_LITE
LIVE PREVIEW

Carol Smidts Professor The Ohio State University Nuclear Reactor - - PowerPoint PPT Presentation

Feb 27, 2024 141 likes •245 views

Carol Smidts Professor The Ohio State University Nuclear Reactor for in-situ testing of sensors Laser lab for development of non-destructive evaluation of materials properties Molten Salt Laboratory, Materials corrosion laboratory,

slide-1
SLIDE 1

Carol Smidts

Professor The Ohio State University

slide-2
SLIDE 2

 Nuclear Reactor for in-situ testing of sensors  Laser lab for development of non-destructive evaluation

  • f materials properties

 Molten Salt Laboratory, Materials corrosion laboratory,

and Fuel-Cladding-Chemical Interaction facilities

 Thermal Hydraulics in High-temperature Reactors,

including both HTGRs and FHRs

 Two-phase Flow Experimentation, Modeling and

Simulation

 High-temperature Compact Heat Exchanger Testing and

Modeling (Helium, Fluoride Salts, Supercritical CO2, and Water)

 Probability Risk Assessment, Software Reliability,

Human Reliability, Digital Instrumentation and Control

2

slide-3
SLIDE 3

Jinghui Wang, Padhraic Mulligan, Leonard Brillson, and Lei R. Cao, 2015, "Review

  • f using gallium nitride for ionizing radiation detection." Applied Physics Reviews

2, no. 031102, 1 - 11.

J.H. Wang, P. Mulligan, L. R. Cao, Transient Current Analysis of a GaN Radiation Detector by TCAD. Nuclear Instruments and Methods in Physics Research Section A:. Vol. 761, no. 11: 7-12. 2014.

Padhraic Mulligan, Jie Qiu, Jinghui Wang, Lei R. Cao, Study of GaN Radiation Sensor after In-core Neutron Irradiation. IEEE Transaction on Nuclear Science. Vol. 61, no. 4: 2040 - 2044. 2014

  • Evan. J. Katz, Chung-Han Lin, Jie Qiu, Zhichun Zhang, Umesh K. Mishra, Lei Cao,

Leonard J. Brillson, Neutron Irradiation Effects on Metal-Gallium Nitride Contacts, Journal of Applied Physics, 115, 123705, 2014.

Chung-Han Lin, Evan J. Katz, Jie Qiu, Zhichun Zhang, Umesh K. Mishra, Lei Cao and Leonard J. Brillson, Neutron irradiation effects on gallium nitride-based Schottky diodes. Applied Physics Letters, Vol. 103, no. 16: 1-9. 2013.

In collaboration with INL but not supported by NUC

“Subsurface imaging of grain microstructure using picosecond ultrasonics”, M. Khafizov, J. Pakarinen, L. He, H.B. Henderson, M.V. Manuel, A.T. Nelson, B.J. Jaques, D.P. Butt, D.H. Hurley, Acta Materialia 112, 209 (2016)

“Local measurement of thermal conductivity and diffusivity”, D. H. Hurley, R. S. Schley, M. Khafizov, B. L. Wendt, Rev. Sci. Instrum. 86, 123901 (2015)

3

slide-4
SLIDE 4

Jie Qiu, Evan Katz, Chung-Han Lin, Lei Cao, Leonard J. Brillson, The Effect of Neutron Irradiation on Semi-insulating GaN. Radiation Effects and Defects in

  • Solids. Vol. 168, 1- 9. 2013.

  • P. Mulligan, J.H. Wang, L. R. Cao, Evaluation of Freestanding GaN as an Alpha and

Neutron Detector". Nuclear Instruments and Methods in Physics Research Section A:. Vol. 719, 13-16. 2013.

  • M. Chen, J.E. O’Brien, S.J. Yoon, R.N. Christensen, P. Sabharwall, and X. Sun,

“Thermal-Hydraulic Performance of a High-Temperature Zigzag-Channel Printed Circuit Heat Exchanger,” International Topical Meeting on High Temperature Reactor Technology (HTR2016), Las Vegas, November 6-10, 2016.

Chen, M., Sun, X., Christensen, R.N., Shi, S., Skavdahl, I., Utgikar, V., and Sabharwall, P., November 2016, “Experimental and Numerical Study of a Printed Circuit Heat Exchanger,” Annals of Nuclear Energy, 97, pp. 221-232.

Ham, T.K., Arcilesi Jr., D.J., Kim, I.H., Sun, X., Christensen, R.N., Oh, C.H., and Kim, E.S., April 2016, “Computational Fluid Dynamics Analysis of the Initial Stages of a VHTR Air-Ingress Accident using a Scaled-down Model,” Nuclear Engineering and Design, 300, pp. 517-529.

Skavdahl, I., Utgikar, V.P., Christensen, R., Sabharwall, P., Chen, M., and Sun, X., April 2016, “Modeling and Simulation of Control System Response to Temperature Disturbances in a Coupled Heat Exchangers-AHTR System,” Nuclear Engineering and Design, 300, pp. 161-172.

4

slide-5
SLIDE 5

Sabharwall, P., O’Brien, J.E., Yoon, S.J., and Sun, X., December 2015, “Experimental Facility for Development of High-Temperature Reactor Technology: Instrumentation Needs and Challenges,” European Physical Journal (EPJ) N: Nuclear Sciences and Technologies, 1, 14.

Yoon, S.-J., Wegman, K., O’Brien, J., Sabharwall, P., and Sun, X., “An Analytical Methodology to Evaluate Thermal-Hydraulic Performance of Compact Heat Exchangers, Accounting for Heat Loss,” Proceedings of the 2016 International Congress on Advances in Nuclear Power Plants (ICAPP 2016), San Francisco, CA, April 17 – 20, 2016, pp. 1081-1090.

Muzhi Zhu, April 2016, “Design of an Online Monitoring System for Degrading Hardware Components Using Failure Modes and Effects Analysis,” Undergraduate Thesis, The Ohio State University, Columbus, Ohio.

Huijuan Li, Shannon Bragg-Sitton, Carol Smidts, 2016, “Failure Diagnosis for the Holdup Tank System via ISFA,” ANS Winter Meeting 2016, Las Vegas, Nevada, accepted

Muzhi Zhu, Rachit Aggarwal, Shannon Bragg-Sitton, Carol Smidts, 2016, “Effect of Aging and Demand for Reliability Analysis of Degrading Components,” ANS Winter Meeting 2016, Las Vegas, Nevada, accepted

  • Q. Guo, M. Pietrykowski, R. Aggarwal, C. Liu, C. Smidts, "A Distributed Test Facility

for Cyber-Physical Systems: Part I. Fundamental Principles," IEEE Transactions on Control of Network Systems, to be submitted 2016

5

slide-6
SLIDE 6

NUC Worksho kshop: : “Accident Management: Emerging R&D Needs and Approaches” Participant(s) : Xiaodong Sun, Carol Smidts and Tunc Aldemir

MOOSE OSE Train inin ing g Worksho kshop: (April 5-7, 2016) Participant(s): Dr. Shanbin Shi

NUC Revie iew w Meetin eting: Participant(s): Raymond Cao, Marat Khafizov, Carol Smidts, Xiaodong Sun, Jinsuo Zhang, Shanbin Shi, Rachit Aggarwal, Huijuan Li and Sha Xue

Stud udent ents s bein ing g funded: Rachit Aggarwal, M.S. in ME Huijuan Li, Ph.D. in ME Bobak Rashidnia, B.S. in CS Sha Xue, Ph.D. in NE Xiaoqin Zhang, Partially funded, Ph.D. in NE

Stud udent ents s funded to PhD: Qingti Guo, Ph.D. in ME, Aug 2015

6

slide-7
SLIDE 7

7

Title Descript criptio ion INL & Universit rsity y Collab abora rators rs

Studies of Lanthanide Transport in Metallic Nuclear Fuels Focusing on understanding the transport mechanisms of lanthanide transport in fuel, then to understand on how to minimize the FCCIs

  • Jinsuo

suo Zhang ng – OSU

  • C. Unal - LANL
  • Robert

bert Marriani ni - INL Alloys Agents to Stabilize Lanthanides Against Fuel Cladding Chemical Focuses on development on new additives develop to minimize the FCCIs

  • Jinsu

suo Zhang ng - OSU OSU

  • Mike Short - MIT
  • Mich

chael ael Benso son - INL

  • Robert

bert Mariani ani - INL NL

  • Yongfeng

feng Zhang ng – INL NL

slide-8
SLIDE 8

8

Title Descr cription INL L & Uni niversi ersity y Collab aborato ators Development and application of a data-driven methodology for validation of risk-informed safety margin characterization models (IRP-RC-1 – FY 2016) To develop and demonstrate a data- driven methodology for validation of advanced computer models used in nuclear power plant safety analysis. Specifically, the advanced computer models are those in the toolkit to support risk-informed safety margin characterization (RISMC)

  • Xiao

aodong ng Sun n (co-PI PI) )

  • Nam Dinh (PI) – North Carolina State

University

  • Hany Abdel-Khalik – Purdue University
  • Abhinav Gupta – North Carolina State

University

  • Igor Bolotnov, John Baugh, Maria

Avramova – North Carolina State University

  • Philippe Bardet – George Washington

University

  • Rober

bert Young ngbl blood, Crist stian an Rabi biti, , Steven ven Presco scott – Idaho aho National nal Labo borato atory

  • Weiju Ren – Oak Ridge National

Laboratory

  • Robert Sewell – Structural Integrity

Associates Inc.

  • Ramprasad Sampath – Centroid PIC Inc.
  • Anh Bui – Consultant
  • Jeffery Lane – Zachry Nuclear

Engineering Inc.

slide-9
SLIDE 9

9

Title Descr cription INL L & Uni niversi ersity y Collab aborato ators Support for Reactor Operators in Case of Cyber-Security (NEUP Project 16-10744) This project addresses the need for research informing plant engineers and control room operators faced with cyber-security threats on appropriate

  • responses. The approach taken uses

distinguishing features of safety related events versus cyber-security threats; attack modeling, prediction, game theory and PRA knowledge to update operators procedures; and simulation for validation.​

  • C. Smi

midt dts (PI) ) – The Ohio State University

  • Q. Zhu- New York University
  • I. Ray – Colorado State University
  • T.
  • T. McJunki

unkin- Idaho aho National nal Labo borato atories es

  • J. Hollern- Areva
  • Monitoring of Actinide

Concentrations in Molten LiCl- KCl Salt using Alpha Spectroscopy

  • The objective of this research is to

fabricate a sensor prototype for measurement of actinide concentrations in a molten salt and after successful bench testing, to test the sensor in a salt environment at temperatures up to 500 °C at lab- scale.

  • L.
  • L. Cao (PI)

) – The Ohio State University

  • G.
  • G. Fredr

edrick ckso son - Idaho aho National nal Labo borato atories es

  • M. Simpson – University of Utah
slide-10
SLIDE 10

 Pursue current LDRDs which are planned to

end Sept 30, 2017

 Develop joint research activities in the areas

  • f robotics.

10