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Fission Systems & Radiation Transport

Understanding the way that atomic nuclei split and how radiation moves through materials is crucial to nuclear power and nuclear nonproliferation.

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  • Research
    • Fission Systems & Radiation Transport
    • Materials & Radiation Effects
    • Plasmas & Nuclear Fusion
    • Policy & Climate
    • Radiation Measurement & Imaging
    • Labs List

Radiation transport and fission systems engineering encompass the broad scientific fields relevant to the application of fission for energy production and to the study and application of radiation interactions and radiation transport through matter.

Included are the areas of nuclear reactor theory such as neutron transport, thermal hydraulics, fuel cycle analysis, reactor kinetics, diagnostics, control, and optimization. Significant effort is devoted to computational simulations of these processes and to applications of these simulations in overlapping areas such as radiation protection, radiation cancer therapy, radiation-hydrodynamics, kinetic theory, and general computational physics.

Faculty

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Adam Burak

Assistant Research Scientist

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Alex Bielajew

Professor Emeritus

Annalisa Manera

Professor

Brendan Kochunas

Assistant Professor

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Brian Kiedrowski

Associate Professor

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Dale Lancaster

Adjunct Professor

Edward-Larsen-portrait

Edward Larsen

Professor Emeritus

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Imre Pázsit

Adjunct Professor

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James Duderstadt

U-M President Emeritus

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John Lee

Professor Emeritus

Majdi Radaideh portrait

Majdi Radaideh (RAD)

Assistant Professor

Piyush Sabharwall portrait

Piyush Sabharwall

Adjunct Professor

Rui Hu portrait

Rui Hu

Adjunct Professor

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Sola Talabi

Adjunct Professor

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Thomas Downar

Professor

Victor Petrov

Associate Research Scientist

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Volkan Seker

Research Area Specialist Lead

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William R. Martin

Professor Emeritus

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Won Sik Yang

Professor

Xiaodong-Sun-portrait

Xiaodong Sun

Professor

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Yang Zhang

Professor

LABS & Groups

Experimental and Computational Multiphase Flow Laboratory (Prof. Annalisa Manera)
High Resolution TH Imaging Laboratory (Prof. Annalisa Manera)
Nuclear Plant Simulation Laboratory (Prof. John Lee and Prof. Brendan Kochunas)
Nuclear Reactor Analysis and Methods Group (Prof. Thomas Downar and Prof. Brendan Kochunas)
Nuclear Reactor Design and Simulation Laboratory (Prof. Won Sik Yang)
Thermal Hydraulics Laboratory (Prof. Xiaodong Sun)
University of Michigan Computational Particle Transport Team (Prof. Brian Kiedrowski)
See Lab & Group Descriptions

NEWS

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Case Study: Conjugate Heat Transfer Simulation for a Fuel Element of an Experimental Nuclear Reactor

NERS researchers Professor Brendan Kochunas and Dr. Yuxuan Liu have created a free online learning resource for those wanting to learn how to do engineering analysis for a nuclear reactor fuel element with ANSYS.

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New Conceptual Molten Salt Nuclear Reactor Simulation and Design

NERS Master’s student O Hwang Kwon’s research relating to the feasibility of a new conceptual molten salt reactor is aimed at improving safety and efficiency.

NERS Professor Brendan Kochunas honored with faculty development professorship

The Charles and Elizabeth Schrock Faculty Development Professorship is awarded in recognition of outstanding contributions to teaching and research.

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Majdi Radaideh, Stephen Raiman, and Yang Zhang join NERS faculty

The new additions to the department point to a positive future and offer a breadth of educational and research experience.

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Brendan Kochunas wins DOE Distinguished Early Career Award

Kochunas’ research seeks to advance our understanding of the digital twins’ concept for nuclear engineering applications.

Select Research projectS

Thermal Hydraulics of Nuclear Reactors
Lead: Prof. Annalisa Manera

  • Development of a capability for predictive maintenance and flexible operation of nuclear power plants (DOE ARPA-E)
  • Development of multi-scale, multi-physics computational tools er models for the simulations of nuclear systems investigation (DOE/US NRC)
  • High-resolution experiments for the validation of Computational Fluid Dynamics (CFD) codes and for gaining more insight in single-phase and two-phase flow phenomena of interest for nuclear power plants applications (DOE/US NRC/EPRI)
  • Experimental investigations of  the behavior of microreactors sodium heat pipes (DOE/US NRC)
  • Void-fractions distribution in fuel bundles using gamma-tomography (US NRC)
  • Two-phase flow regimes in helical coils, using high-speed radiography (DOE)
  • Imaging of two-phase flows in post-CHF conditions at high pressure using high-speed radiography (US NRC)
  • Experimental and computational investigations of thermal fatigue in isolated branch lines of LWRs (EPRI)
  • Experimental investigations of accident scenarios in high-temperature gas reactors (DOE)
  • Development and application of advanced instrumentation for high-resolution measurements (high-resolution gamma-tomography, high-speed X-ray radiography, refractive-index matching techniques for PIV, wire-mesh sensors, fiber optic sensors)

Hammer Transport Framework
Lead: Prof. Brian Kiedrowski
The UMCPT Team is developing its own particle transport capability that supports multigroup and continuous-energy Monte Carlo as well as discrete ordinates (SN) calculations to enable rapid prototyping of methods. One major emphasis right now is the development of the next generation of hybrid deterministic-Monte Carlo transport methods to accelerate particle transport calculations to support research being performed by the Consortium for Monitoring, Technology, and Verification. As the project matures, the plan is to open-source the code.

Improvement and Verification and Validation Test of Modeling and Simulation Capabilities of Griffin
Lead: Prof. Won Sik Yang
The Griffin code is the integrated nuclear reactor physics code for advanced nuclear reactor applications, which is being developed by the ANL and INL Griffin development team based on the ANL/INL physics codes (PROTEUS suite and Mammoth/Rattlesnake) under the DOE-NE NEAMS program. The objectives of this project are (1) to support the ANL team to implement the key capabilities of PROTEUS to Griffin and to improve their performances on the MOOSE framework, (2) to improve the cross-section generation capabilities for advanced reactor applications, including capabilities of modeling TRISO particle fuels, (3) to develop CMFD acceleration schemes for 3D irregular geometry meshes, (4) to improve multi-physics simulation capabilities of Griffin for non-LWR applications including SFR, MSR, HTR, and microreactors, and (5) to support developing and performing verification and validation tests.

Double-heterogeneity Modeling Capability of SCALE-Polaris to Generate Few-group Nodal Cross Sections for Particulate Fuels
Lead: Prof. Won Sik Yang
The objective of this project is to develop resonance self-shielding and transport calculation methods for prismatic block and pebble type high-temperature gas-cooled reactor analysis and to implement the methods into the SCALE-Polaris code in collaboration with the SCALE XSProc and Polaris teams at Oak Ridge National Laboratories. SCALE-Polaris is the NRC transport code that prepares few group nodal cross sections for the NRC core simulator PARCS. This research focuses on developing an accurate and efficient method to generate multi-group cross-sections of TRISO particulate fuels by combining the Sanchez-Pomraning method for double heterogeneity treatment, and the embedded self-shielding method for resonance self-shielding, and the Dancoff based one-dimensional cylindrical cell model for efficient transport calculation.

Development of Neutronics Analysis Methods for Coupled Fast-Thermal Reactor Analysis
Lead: Prof. Won Sik Yang
The objective of this research is to develop an efficient analysis code system for coupled fast-thermal reactor or accelerator-driven subcritical systems, which are recently regaining interest, but legacy analysis tools tailored for either fast or thermal system analysis are not directly applicable to. A new computational procedure is being developed by adding thermal system analysis capabilities in the fast reactor analysis codes of Argonne National Laboratory. The variational nodal transport code VARIANT has been modified to introduce the partial current discontinuity factors (PCDFs) in order to reduce assembly homogenization errors in the thermal zone. The fast reactor fuel cycle analysis code REBUS has been updated to use burnup and temperature-dependent microscopic cross-sections. A thermal-hydraulics module is being added for thermal feedback calculations. A computational procedure to generate homogenized multigroup cross-sections and PCDFs is being developed.

Evaluation of Semi-Autonomous Passive Control Systems for HTGR Type Special Purpose Reactors
Lead: Prof. Brendan Kochunas
Researchers will investigate the use of variable flow controllers and a variable reflector as passive or semi-autonomous reactivity control mechanisms for multi-module HTGR type special purpose reactors. This applies to the commercially developed special-purpose reactor concepts from HolosGen. The incorporation of these systems will reduce the movable parts count and enable a more robust load to follow capabilities over broader power ranges and local and global reactivity control. (In collaboration with Victor Petrov, Nicolas Stauff, and Changho Lee at Argonne National Laboratory, and Claudio Filippone and Alan Wells at Holosgen, LLC.)

Process Constrained Data Analytics for Sensor Assignment and Calibration
Lead: Prof. Brendan Kochunas
This project will develop and demonstrate data-analytic methods to address the problem of how to assign a sensor set in a nuclear facility such that 1) a requisite level of process monitoring capability is realized, and in turn, 2) the sensor set is sufficiently rich to allow analytics to determine the status of the individual sensors with respect to their need for calibration. This approach will allow for automated calibration status, avoiding unneeded calibration activities in the facility. (In collaboration with Richard Vilim (PI) at Argonne National Laboratory and Marc Anderson at Xcel Energy.)

https://youtu.be/umeP-JHfUbg?list=PLmNrnoyQ30KvOEe9lziJ0An037eglrg74

GET INVOLVED

We believe that engaging in research as an undergraduate student is a very important part of the NERS experience, and many of our third- and fourth-year undergraduate students are actively involved and have co-authored papers in scientific journals.

Undergraduate Research Opportunities
Learn About our Graduate Program

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