Daniel M. Wachs

Idaho National Laboratory — United States

Materials Science · Physical Sciences

23h-index2.1kcitations160works0.02yr avg
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Research Topics

Nuclear Materials and Properties(128), Nuclear reactor physics and engineering(127), Nuclear and radioactivity studies(44), Fusion materials and technologies(33), Nuclear Physics and Applications(19)

Publications160 total

A Design and Fabrication Options Trade Study for Metallic Fuel without Internal Sodium Bonding
2023· 1 citedOpen Access
Resumption of water capsule reactivity-initiated accident testing at TREAT
Nuclear Engineering and Design·2023· 3 citedOpen Access
Design and Modeling of Magnetic Power and Signal Transmission Mechanism for Sensors in Nuclear Reactors
IEEE Sensors Journal·2023
Consensus DOE Advanced Fuels Campaign TREAT/SATS Test Plan [Slides]
2022Open Access
Combined TREAT-LOC and SATS LOCA Experiment Plan: Integral LOCA Experiments on High-Burnup Fuels
2022· 1 citedOpen Access
Design of separate-effects In-Pile transient boiling experiments at the TREAT Facility
Nuclear Engineering and Design·2022· 7 citedOpen Access
FAST irradiations and initial post irradiation examinations – Part I
Nuclear Engineering and Technology·2022· 8 citedOpen Access
Detailed characterization of a PWR fuel rod at high burnup in support of LOCA testing
Journal of Nuclear Materials·2022· 25 citedOpen Access
High-burnup Experiments in Reactivity Initiated Accidents (HERA)
2022· 8 citedOpen Access
Dry in-pile fracture test (DRIFT) for separate-effects validation of ceramic fuel fracture models
Journal of Nuclear Materials·2022· 9 citedOpen Access
Microstructural Development in Inconel 718 Nickel-Based Superalloy Additively Manufactured by Laser Powder Bed Fusion
Metallography Microstructure and Analysis·2022· 57 citedOpen Access
Post-transient examination of performance of uranium silicide fuel and silicon-carbide composite cladding under reactivity-initiated accident conditions
Journal of Nuclear Materials·2022· 16 citedOpen Access
Pellet Cladding Interaction In-Reactor Ramp Testing in a World Without the Halden Boiling Water Reactor
2022· 3 cited
Fuel Performance Distortion Evaluation Under Reactivity Insertion Accidents Conditions with Dynamical System Scaling
2022
The NEA Framework for Irradiation Experiments (FIDES): A New Future for International Collaboration on Nuclear Fuel Research
2022· 3 cited
A Review of Cladding Failure Thresholds in RIA Conditions Based on Transient Reactor Test Data and the Need for Continued Testing
2022· 1 citedOpen Access
The U.S. Accident Tolerant Fuels Program -- Transforming the Future of LWR Fuels
2022· 2 cited
Mechanical Behavior Assessment of Ti-6Al-4V ELI Alloy Produced by Laser Powder Bed Fusion
Metals·2021· 38 citedOpen Access
Water-based Ria Testing in TREAT: Commissioning and Early Results
2021Open Access
Behavior of metallic fast reactor fuels during an overpower transient
Journal of Nuclear Materials·2021· 12 citedOpen Access
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Frequent Co-authors

Adam Robinson(21), Dennis D. Keiser(16), Nicolas Woolstenhulme(14), Jian Gan(9), G.L. Hofman(9), Jan‐Fong Jue(8), Brandon Miller(8), Colby Jensen(8), Pavel Medvedev(6), Douglas E. Burkes(6), D. Devin Imholte(5), M. K. Meyer(4), Yeon Soo Kim(4), David Kamerman(4), M. A. Lillo(4), Y.S. Kim(3), Abhishek Mehta(3), Le Zhou(3), Thinh Huynh(3), Holden Hyer(3)