College of Engineering
Displaying works 1 - 20 of 53 in total
Sorted by most recent date added to the index first, which may not be the same as publication date order.
2007 journal article
Burn-up characteristics of a light-water-cooled nuclear reactor of natural uranium and beryllium
Journal of Physical & Natural Science, 1(2), 1–11.
2007 journal article
Correlation between Ingot Diameter and Crystal Properties of CdZnTe:In Grown by the Modified Bridgman Method
Crystal Growth & Design, 7(2), 435–438.
2007 journal article
Effect of annealing on the residual stress and strain distribution in CdZnTe wafers
Journal of Crystal Growth, 305(1), 50–54.
2007 journal article
Study on the behaviors of impurities in cadmium zinc telluride
Journal of Crystal Growth, 304(2), 313–316.
2007 journal article
Utilization of two-dimensional deterministic transport methods for analysis of pebble-bed reactors
Annals of Nuclear Energy, 34(5), 396–405.
2007 journal article
Challenges in coupled thermal–hydraulics and neutronics simulations for LWR safety analysis
Annals of Nuclear Energy, 34(6), 501–513.
2007 journal article
Comparison via parallel performance models of angular and spatial domain decompositions for solving neutral particle transport problems
Progress in Nuclear Energy, 49(1), 37–60.
2007 journal article
Mechanical behavior of nanocrystalline copper
Materials Science and Engineering: A, 463(1-2), 14–21.
2007 journal article
WITHDRAWN: Structural materials for Gen-IV nuclear reactors: Challenges and opportunities
Journal of Nuclear Materials.
2007 conference paper
Steady-state nuclear analysis methods at global nuclear fuel, invited
Transactions of the American Nuclear Society, 97, 557–558. http://www.scopus.com/inward/record.url?eid=2-s2.0-55349115707&partnerID=MN8TOARS
2007 conference paper
Material property effect in steam explosion energetics: Revisited
Proceedings - 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12. http://www.scopus.com/inward/record.url?eid=2-s2.0-42249093642&partnerID=MN8TOARS
2007 conference paper
Thermal-hydraulic performance of lead-bismuth eutectic in a straight-tube and a U-tube heat exchangers
Proceedings - 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12. http://www.scopus.com/inward/record.url?eid=2-s2.0-44349134568&partnerID=MN8TOARS
2007 conference paper
Simulation of core melt pool formation in a reactor pressure vessel lower head using an effective convectivity model
Proceedings - 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12. http://www.scopus.com/inward/record.url?eid=2-s2.0-44449162101&partnerID=MN8TOARS
2007 conference paper
RELAP5 and TRACE codes comparison and validation under steady-state and transient conditions on the basis of NUPEC data
Proceedings - 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12. http://www.scopus.com/inward/record.url?eid=2-s2.0-44349127315&partnerID=MN8TOARS
2007 conference paper
Evaluation of coupled codes RELAP5/PARCS capability for BWR global stability prediction
Proceedings - 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12. http://www.scopus.com/inward/record.url?eid=2-s2.0-44349116232&partnerID=MN8TOARS
2007 journal article
Aerobreakup in disturbed subsonic and supersonic flow fields
Journal of Fluid Mechanics, 593, 131–170.
2007 conference paper
A study on effects of debris bed prototypicality on coolability
Proceedings - 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12. http://www.scopus.com/inward/record.url?eid=2-s2.0-44349091618&partnerID=MN8TOARS
2007 conference paper
Dynamics and preconditioning in a single drop vapor explosion
Proceedings - 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12. http://www.scopus.com/inward/record.url?eid=2-s2.0-44349165747&partnerID=MN8TOARS
2007 conference paper
An analytical study of mechanisms that govern debris packing in a LWR severe accident
Proceedings - 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12. http://www.scopus.com/inward/record.url?eid=2-s2.0-44349098203&partnerID=MN8TOARS
2007 patent
Plasma Generation And Control Using A Dual Frequency Rf Source
https://www.lens.org/001-723-961-714-703