Evaluation of U10MO Fuel Plate Irradiation Behavior Via Numerical and Experimental Benchmarking
Evaluation of U10MO Fuel Plate Irradiation Behavior Via Numerical and Experimental Benchmarking

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Publisher:

Published: 2012

Total Pages:

ISBN-13:

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This article analyzes dimensional changes due to irradiation of monolithic plate-type nuclear fuel and compares results with finite element analysis of the plates during fabrication and irradiation. Monolithic fuel plates tested in the Advanced Test Reactor (ATR) at Idaho National Lab (INL) are being used to benchmark proposed fuel performance for several high power research reactors. Post-irradiation metallographic images of plates sectioned at the midpoint were analyzed to determine dimensional changes of the fuel and the cladding response. A constitutive model of the fabrication process and irradiation behavior of the tested plates was developed using the general purpose commercial finite element analysis package, Abaqus. Using calculated burn-up profiles of irradiated plates to model the power distribution and including irradiation behaviors such as swelling and irradiation enhanced creep, model simulations allow analysis of plate parameters that are either impossible or infeasible in an experimental setting. The development and progression of fabrication induced stress concentrations at the plate edges was of primary interest, as these locations have a unique stress profile during irradiation. Additionally, comparison between 2D and 3D models was performed to optimize analysis methodology. In particular, the ability of 2D and 3D models account for out of plane stresses which result in 3-dimensional creep behavior that is a product of these components. Results show that assumptions made in 2D models for the out-of-plane stresses and strains cannot capture the 3-dimensional physics accurately and thus 2D approximations are not computationally accurate. Stress-strain fields are dependent on plate geometry and irradiation conditions, thus, if stress based criteria is used to predict plate behavior (as opposed to material impurities, fine micro-structural defects, or sharp power gradients), unique 3D finite element formulation for each plate is required.

Fuel Plate Failure Experiments and Analyses in Irradiated U-10Mo Alloy
Fuel Plate Failure Experiments and Analyses in Irradiated U-10Mo Alloy

Author: Francine Joyce Rice

Publisher:

Published: 2017

Total Pages: 0

ISBN-13:

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The Materials Management and Minimization (M3) Program intends to qualify a new high-density low-enriched-uranium (LEU) U--Mo monolithic fuel to enable conversion of six US high-performance research reactors (USHPRRs). This thesis presents the preliminary results and discussions related to post-irradiation blister anneal studies and fission product release scoping studies performed on U--Mo monolithic fuel plates. Blister anneal testing on irradiated fuel plates is a temperature-resolved failure-threshold measurement technique historically used to assess fuel plate stability under off-normal operating conditions. The effects of fuel composition, geometry, fission density, and irradiation conditions are presented herein as parameters that were investigated for their impact on blister-threshold temperatures. The fission-product-transport scoping study successfully characterized the release, transport and temperature-resolved deposition behavior of iodine and cesium. Two failure temperatures were evaluated: 600 and 1250°C. Testing was performed in the main hot cell at the Materials and Fuels Complex located at Idaho National Laboratory.

Effects of the Shape of the Foil Corners on the Irradiation Performance of U10Mo Alloy Based Monolithic Mini-plates
Effects of the Shape of the Foil Corners on the Irradiation Performance of U10Mo Alloy Based Monolithic Mini-plates

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Published: 2015

Total Pages:

ISBN-13:

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Monolithic plate-type fuel is a fuel form being developed for high performance research and test reactors to minimize the use of enriched material. These fuel elements are comprised of a high density, low enrichment, U-Mo alloy based fuel foil, sandwiched between Zirconium liners and encapsulated in Aluminum cladding. The use of a high density fuel in a foil form presents a number of fabrication and operational concerns, such as: foil centering, flatness of the foil, fuel thickness variation, geometrical tilting, foil corner shape etc. To benchmark this new design, effects of various geometrical and operational variables on irradiation performance have been evaluated. As a part of these series of sensitivity studies, the shape of the foil corners were studied. To understand the effects of the corner shapes of the foil on thermo-mechanical performance of the plates, a behavioral model was developed for a selected plate from RERTR-12 experiments (Plate L1P785). Both fabrication and irradiation processes were simulated. Once the thermo-mechanical behavior the plate is understood for the nominal case, the simulations were repeated for two additional corner shapes to observe the changes in temperature, displacement and stress-strain fields. The results from the fabrication simulations indicated that the foil corners do not alter the post-fabrication stress-strain magnitudes. Furthermore, the irradiation simulations revealed that post-fabrication stresses of the foil would be relieved very quickly in operation. While, foils with chamfered and filleted corners yielded stresses with comparable magnitudes, they are slightly lower in magnitudes, and provided a more favorable mechanical response compared with the foil with sharp corners.

Status of Fast Reactor Research and Technology Development
Status of Fast Reactor Research and Technology Development

Author: International Atomic Energy Agency

Publisher:

Published: 2012

Total Pages: 0

ISBN-13: 9781523130191

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"Based on a recommendation from the Technical Working Group on Fast Reactors, this publication is a regular update of previous publications on fast reactor technology. The publication provides comprehensive and detailed information on the technology of fast neutron reactors. The focus is on practical issues that are useful to engineers, scientists, managers, university students and professors. The main issues of discussion are experience in design, construction, operation and decommissioning, various areas of research and development, engineering, safety and national strategies, and public acceptance of fast reactors. In the summary the reader will find national strategies, international initiatives on innovative (i.e. Generation IV) systems and an assessment of public acceptance as related to fast reactors."--Résumé de l'éditeur.

Material Properties of Unirradiated Uranium-Molybdenum (U-Mo) Fuel for Research Reactors
Material Properties of Unirradiated Uranium-Molybdenum (U-Mo) Fuel for Research Reactors

Author: International Atomic Energy Agency

Publisher:

Published: 2020-10-12

Total Pages: 144

ISBN-13: 9789201157201

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This publication presents the material properties of all unirradiated Uranium-Molybdenum (U-Mo) fuel constituents that are essential for fuel designers and reactor operators to evaluate the fuel's performance and safety for research reactors. Many significant advances in the understanding and development of low enriched uranium U-Mo fuels have been made since 2004, stimulated by the need to understand irradiation behavior and early fuel failures during testing. The publication presents a comprehensive overview of mechanical and physical property data from U-Mo fuel research

Design Features and Operating Experience of Experimental Fast Reactors
Design Features and Operating Experience of Experimental Fast Reactors

Author: International Atomic Energy Agency

Publisher:

Published: 2013

Total Pages: 0

ISBN-13: 9789201364104

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As a part of the IAEA efforts for knowledge preservation and data retrieval, this publication compiles and documents significant aspects of fast reactor engineering development and experience. Its focus is on research and development activities, experience with experimental facilities, and criteria for comparison liquid metal coolants.

Heat Transfer and Fluid Flow in Minichannels and Microchannels
Heat Transfer and Fluid Flow in Minichannels and Microchannels

Author: Satish Kandlikar

Publisher: Elsevier

Published: 2006

Total Pages: 492

ISBN-13: 9780080445274

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&Quot;This book explores flow through passages with hydraulic diameters from about 1 [mu]m to 3 mm, covering the range of minichannels and microchannels. Design equations along with solved examples and practice problems are also included to serve the needs of practicing engineers and students in a graduate course."--BOOK JACKET.

Two-Phase Flow, Boiling, and Condensation
Two-Phase Flow, Boiling, and Condensation

Author: S. Mostafa Ghiaasiaan

Publisher: Cambridge University Press

Published: 2014-08-07

Total Pages: 0

ISBN-13: 9781107431638

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This text is an introduction to gas-liquid two-phase flow, boiling and condensation for graduate students, professionals, and researchers in mechanical, nuclear, and chemical engineering. The book provides a balanced coverage of two-phase flow and phase change fundamentals, well-established art and science dealing with conventional systems, and the rapidly developing areas of microchannel flow and heat transfer. It is based on the author's more than 15 years of teaching experience. Instructors teaching multiphase flow have had to rely on a multitude of books and reference materials. This book remedies that problem by covering all the topics that are essential for a graduate first course. Among the important areas that are discussed in the book, and are not adequately covered by virtually all the available textbooks, are: two-phase flow model conservation equations and their numerical solution; condensation with and without noncondensables; and two-phase flow, boiling, and condensation in mini and microchannels.