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Title: Developing a laser shockwave model for characterizing diffusion bonded interfaces

Abstract

The US National Nuclear Security Agency has a Global Threat Reduction Initiative (GTRI) with the goal of reducing the worldwide use of high-enriched uranium (HEU). A salient component of that initiative is the conversion of research reactors from HEU to low enriched uranium (LEU) fuels. An innovative fuel is being developed to replace HEU in high-power research reactors. The new LEU fuel is a monolithic fuel made from a U-Mo alloy foil encapsulated in Al-6061 cladding. In order to support the fuel qualification process, the Laser Shockwave Technique (LST) is being developed to characterize the clad-clad and fuel-clad interface strengths in fresh and irradiated fuel plates. LST is a non-contact method that uses lasers for the generation and detection of large amplitude acoustic waves to characterize interfaces in nuclear fuel plates. However, because the deposition of laser energy into the containment layer on a specimen's surface is intractably complex, the shock wave energy is inferred from the surface velocity measured on the backside of the fuel plate and the depth of the impression left on the surface by the high pressure plasma pulse created by the shock laser. To help quantify the stresses generated at the interfaces, a finite elementmore » method (FEM) model is being utilized. This paper will report on initial efforts to develop and validate the model by comparing numerical and experimental results for back surface velocities and front surface depressions in a single aluminum plate representative of the fuel cladding.« less

Authors:
; ;  [1]
  1. Idaho National Laboratory, Idaho Falls, ID (United States)
Publication Date:
OSTI Identifier:
22391206
Resource Type:
Journal Article
Resource Relation:
Journal Name: AIP Conference Proceedings; Journal Volume: 1650; Journal Issue: 1; Conference: 41. Annual Review of Progress in Quantitative Nondestructive Evaluation, Boise, ID (United States), 20-25 Jul 2014; Other Information: (c) 2015 AIP Publishing LLC; Country of input: International Atomic Energy Agency (IAEA)
Country of Publication:
United States
Language:
English
Subject:
71 CLASSICAL AND QUANTUM MECHANICS, GENERAL PHYSICS; 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; ALUMINIUM; CLADDING; COMPARATIVE EVALUATIONS; DIFFUSION; FINITE ELEMENT METHOD; FUEL PLATES; HIGHLY ENRICHED URANIUM; INTERFACES; LASER-PRODUCED PLASMA; MATHEMATICAL MODELS; MOLYBDENUM ALLOYS; NUCLEAR FUEL CONVERSION; SHOCK WAVES; SLIGHTLY ENRICHED URANIUM; SOUND WAVES; SPENT FUELS; SURFACES; URANIUM ALLOYS

Citation Formats

Lacy, Jeffrey M., E-mail: Jeffrey.Lacy@inl.gov, Smith, James A., E-mail: Jeffrey.Lacy@inl.gov, and Rabin, Barry H., E-mail: Jeffrey.Lacy@inl.gov. Developing a laser shockwave model for characterizing diffusion bonded interfaces. United States: N. p., 2015. Web. doi:10.1063/1.4914752.
Lacy, Jeffrey M., E-mail: Jeffrey.Lacy@inl.gov, Smith, James A., E-mail: Jeffrey.Lacy@inl.gov, & Rabin, Barry H., E-mail: Jeffrey.Lacy@inl.gov. Developing a laser shockwave model for characterizing diffusion bonded interfaces. United States. doi:10.1063/1.4914752.
Lacy, Jeffrey M., E-mail: Jeffrey.Lacy@inl.gov, Smith, James A., E-mail: Jeffrey.Lacy@inl.gov, and Rabin, Barry H., E-mail: Jeffrey.Lacy@inl.gov. Tue . "Developing a laser shockwave model for characterizing diffusion bonded interfaces". United States. doi:10.1063/1.4914752.
@article{osti_22391206,
title = {Developing a laser shockwave model for characterizing diffusion bonded interfaces},
author = {Lacy, Jeffrey M., E-mail: Jeffrey.Lacy@inl.gov and Smith, James A., E-mail: Jeffrey.Lacy@inl.gov and Rabin, Barry H., E-mail: Jeffrey.Lacy@inl.gov},
abstractNote = {The US National Nuclear Security Agency has a Global Threat Reduction Initiative (GTRI) with the goal of reducing the worldwide use of high-enriched uranium (HEU). A salient component of that initiative is the conversion of research reactors from HEU to low enriched uranium (LEU) fuels. An innovative fuel is being developed to replace HEU in high-power research reactors. The new LEU fuel is a monolithic fuel made from a U-Mo alloy foil encapsulated in Al-6061 cladding. In order to support the fuel qualification process, the Laser Shockwave Technique (LST) is being developed to characterize the clad-clad and fuel-clad interface strengths in fresh and irradiated fuel plates. LST is a non-contact method that uses lasers for the generation and detection of large amplitude acoustic waves to characterize interfaces in nuclear fuel plates. However, because the deposition of laser energy into the containment layer on a specimen's surface is intractably complex, the shock wave energy is inferred from the surface velocity measured on the backside of the fuel plate and the depth of the impression left on the surface by the high pressure plasma pulse created by the shock laser. To help quantify the stresses generated at the interfaces, a finite element method (FEM) model is being utilized. This paper will report on initial efforts to develop and validate the model by comparing numerical and experimental results for back surface velocities and front surface depressions in a single aluminum plate representative of the fuel cladding.},
doi = {10.1063/1.4914752},
journal = {AIP Conference Proceedings},
number = 1,
volume = 1650,
place = {United States},
year = {Tue Mar 31 00:00:00 EDT 2015},
month = {Tue Mar 31 00:00:00 EDT 2015}
}