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Dive into the research topics where Joel Lee McDuffee is active.

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Featured researches published by Joel Lee McDuffee.


international conference on fuel cell science engineering and technology fuelcell collocated with asme international conference on energy sustainability | 2013

Heat Transfer Through Small Moveable Gas Gaps in a Multi-Body System Using the ANSYS Finite Element Software

Joel Lee McDuffee

The Thermal Hydraulics and Irradiation Engineering (THIE) Group at Oak Ridge National Laboratory (ORNL) designs and builds capsules in which to irradiate advanced fuels and materials that are typically inserted into ORNL’s High Flux Isotope Reactor. Experiments are designed to achieve a target temperature that ranges from 250°C to 1200°C. Most capsules do not have active temperature measurement or control, which puts an imperative on accurate temperature simulation. Temperature control in these capsules is accomplished by designing specific gaps between adjacent parts and filling the capsules with an inert gas: helium, neon, or argon.Most any finite element solver will do an excellent job estimating temperatures within individual parts, but the simulation challenge for these complex, multi-body systems is to accurately predict the heat transfer through contact surfaces or interstitial gas gaps. The gas gaps are on the order of 150 μm, so accurate simulation must include thermal expansion of the adjacent parts, the thermal jump effect on the part surfaces, and the possibility the parts will touch or break contact during expansion. This paper will discuss the limitations in thermal contact modeling in finite element modelers and the algorithms the THIE Group uses to overcome these limitations.Copyright


Archive | 2015

Delivery of completed irradiation vehicles and the quality assurance document to the High Flux Isotope Reactor for irradiation

Christian M. Petrie; Joel Lee McDuffee; Yutai Katoh; Kurt A. Terrani

This report details the initial fabrication and delivery of two Fuel Cycle Research and Development (FCRD) irradiation capsules (ATFSC01 and ATFSC02), with associated quality assurance documentation, to the High Flux Isotope Reactor (HFIR). The capsules and documentation were delivered by September 30, 2015, thus meeting the deadline for milestone M3FT-15OR0202268. These irradiation experiments are testing silicon carbide composite tubes in order to obtain experimental validation of thermo-mechanical models of stress states in SiC cladding irradiated under a prototypic high heat flux. This document contains a copy of the completed capsule fabrication request sheets, which detail all constituent components, pertinent drawings, etc., along with a detailed summary of the capsule assembly process performed by the Thermal Hydraulics and Irradiation Engineering Group (THIEG) in the Reactor and Nuclear Systems Division (RNSD). A complete fabrication package record is maintained by the THIEG and is available upon request.


Archive | 2015

Milestone M3FT-15OR0203112. Build redesigned HFIR rabbit capsules and make ready for insertion for irradiation in HFIR

Richard H Howard; Joel Lee McDuffee; Maria A. Okuniewski

This report details the fabrication and delivery of two Fuel Cycle Research and Development irradiation capsules (FCRP20 and FCRP03), with associated quality assurance documentation, to the High Flux Isotope Reactor. The capsules and documentation were delivered by September 30, 2015, thus meeting the deadline for milestone M3FT-15OR0203112. These irradiation experiments irradiate metal parallelepiped specimens that may consist of various compositions including uranium metal, steel, etc. This document contains a copy of the completed capsule fabrication request sheets, which detail all constituent components, pertinent drawings, etc., along with a detailed summary of the capsule assembly process performed by the Thermal Hydraulics and Irradiation Engineering Group (THIEG) in the Reactor and Nuclear Systems Division. A complete fabrication package record is maintained by THIEG and is available upon request.


Journal of Nuclear Materials | 2017

Experimental design and analysis for irradiation of SiC/SiC composite tubes under a prototypic high heat flux

Christian M. Petrie; Takaaki Koyanagi; Joel Lee McDuffee; Christian P. Deck; Yutai Katoh; Kurt A. Terrani


Journal of Nuclear Materials | 2013

Principles and practice of a bellows-loaded compact irradiation vehicle

Thak Sang Byun; Meimei Li; Lance Lewis Snead; Yutai Katoh; Timothy D. Burchell; Joel Lee McDuffee


Journal of Nuclear Materials | 2018

Dimensional stability and anisotropy of SiC and SiC-based composites in transition swelling regime

Yutai Katoh; Takaaki Koyanagi; Joel Lee McDuffee; Lance Lewis Snead; Ken Yueh


Archive | 2014

Design, Fabrication, and Modeling of a Two-Phase Thermosyphon Experimental Facility for Fuels and Materials Irradiation

Joel Lee McDuffee; Juan J. Carbajo; David K Felde


Archive | 2008

Analysis of a Fast Spectrum Irradiation Facility in the High Flux Isotope Reactor

Ronald James Ellis; Jess C Gehin; Joel Lee McDuffee; Randy W Hobbs


Archive | 2008

Development of Fast Spectrum Irradiation Facility for Fuels Development in the High Flux Isotope Reactor

Jess C Gehin; Ronald James Ellis; Joel Lee McDuffee; Randy W Hobbs; Lance Lewis Snead


Journal of Nuclear Materials | 2008

Experimental plan and design of two experiments for graphite irradiation at temperatures up to 1500 °C in the target region of the high flux isotope reactor

Joel Lee McDuffee; Timothy D. Burchell; Dennis Wayne Heatherly; Kenneth R Thoms

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Larry J. Ott

Oak Ridge National Laboratory

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Ronald James Ellis

Oak Ridge National Laboratory

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Yutai Katoh

Oak Ridge National Laboratory

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Christian M. Petrie

Oak Ridge National Laboratory

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Jess C Gehin

Oak Ridge National Laboratory

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Juan J. Carbajo

Oak Ridge National Laboratory

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Lance Lewis Snead

Oak Ridge National Laboratory

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Timothy D. Burchell

Oak Ridge National Laboratory

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David K Felde

Oak Ridge National Laboratory

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Kenneth R Thoms

Oak Ridge National Laboratory

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