24 Papers
66 Citations
Wei Lu is an academic researcher from Oak Ridge National Laboratory. The author has contributed to research in topics: Neutron & Neutron source. The author has an hindex of 7, co-authored 24 publications. Previous affiliations of Wei Lu include North Carolina State University.
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Papers
The NCSU radiation damage database; proton-induced damage energy and application to radiation damage at SINQ
Wei Lu,M.S. Wechsler,Y. Dai +2 more
TL;DR: The NCSU radiation damage database as discussed by the authors contains proton and neutron cross sections for production of damage energy, displacements, helium, hydrogen, and heavier transmutation products, which can be used to calculate displacement production at SINQ Target 5.
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An environment using nuclear inventory codes in combination with radiation transport code MCNPX for accelerator activation problems
Franz X. Gallmeier,Phillip D. Ferguson,Erik B. Iverson,Irina Popova,Wei Lu +4 more
- 01 Jan 2007
TL;DR: A scripting tool which extracts cell-based material, neutron fluxes and spallation product information from MCNPX output files and drives transmutation calculations using the CINDER’90 code in accelerator-driven systems is written and tested.
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Characterization of mechanical properties and deformation behavior of highly irradiated 316L stainless steel from target modules at the Spallation Neutron Source using digital image correlation analysis
TL;DR: In this article, tensile tests were performed in conjunction with digital image correlation (DIC) characterization, which permitted detailed analysis of the strain distribution and deformation behavior of the specimen gauge sections during testing, and the results showed that, while considerable hardening (500-700 MPa increase in yield strength) occurred in the 316L SNS target material with increasing dose, appreciable ductility (19-23% total elongation) remained in the material after irradiation to 7.6 displacements per atom (dpa).
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The CINDER'90 transmutation code package for use in accelerator applications in combination with MCNPX
Franz X. Gallmeier,Phillip D. Ferguson,Wei Lu,Erik B. Iverson,G. Muhrer,Shannon T. Holloway,Charles T. Kelsey,Eric J. Pitcher,Michael Wohlmuther,Bradley J. Micklich +9 more
- 01 Jan 2010
TL;DR: Since the package release, improvements to CINDER’90 are underway in algorithms, libraries, and interfaces to transport codes.
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Moderator poison design and burn-up calculations at the SNS
TL;DR: In this paper, the authors proposed to replace the Gd poison sheet with Cd poison material from the perspective of lifetime and neutronic performance in the spallation neutron source (SNS) target system.
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