Multiscale Simulation of Thermo-mechanical Processes in Irradiated Fission-reactor Materials

PDF Version Also Available for Download.

Description

This report contains a summary of progress made on the subtask area on phase field model development for microstructure evolution in irradiated materials, which was a part of the Computational Materials Science Network (CMSN) project entitled: Multiscale Simulation of Thermo-mechanical Processes in Irradiated Fission-reactor Materials. The model problem chosen has been that of void nucleation and growth under irradiation conditions in single component systems.

Physical Description

85 kb

Creation Information

El-Azab, Anter May 28, 2012.

Context

This text is part of the collection entitled: Office of Scientific & Technical Information Technical Reports and was provided by UNT Libraries Government Documents Department to Digital Library, a digital repository hosted by the UNT Libraries. More information about this text can be viewed below.

Who

People and organizations associated with either the creation of this text or its content.

Publisher

Provided By

UNT Libraries Government Documents Department

Serving as both a federal and a state depository library, the UNT Libraries Government Documents Department maintains millions of items in a variety of formats. The department is a member of the FDLP Content Partnerships Program and an Affiliated Archive of the National Archives.

Contact Us

What

Descriptive information to help identify this text. Follow the links below to find similar items on the Digital Library.

Description

This report contains a summary of progress made on the subtask area on phase field model development for microstructure evolution in irradiated materials, which was a part of the Computational Materials Science Network (CMSN) project entitled: Multiscale Simulation of Thermo-mechanical Processes in Irradiated Fission-reactor Materials. The model problem chosen has been that of void nucleation and growth under irradiation conditions in single component systems.

Physical Description

85 kb

Language

Item Type

Identifier

Unique identifying numbers for this text in the Digital Library or other systems.

  • Report No.: 1
  • Grant Number: FG02-07ER46367
  • Office of Scientific & Technical Information Report Number: 1041194
  • Archival Resource Key: ark:/67531/metadc833925

Collections

This text is part of the following collection of related materials.

Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.

What responsibilities do I have when using this text?

When

Dates and time periods associated with this text.

Creation Date

  • May 28, 2012

Added to The UNT Digital Library

  • May 19, 2016, 3:16 p.m.

Description Last Updated

  • Aug. 3, 2016, 8:34 p.m.

Usage Statistics

When was this text last used?

Yesterday: 0
Past 30 days: 2
Total Uses: 8

Interact With This Text

Here are some suggestions for what to do next.

Start Reading

PDF Version Also Available for Download.

International Image Interoperability Framework

IIF Logo

We support the IIIF Presentation API

El-Azab, Anter. Multiscale Simulation of Thermo-mechanical Processes in Irradiated Fission-reactor Materials, text, May 28, 2012; United States. (digital.library.unt.edu/ark:/67531/metadc833925/: accessed December 9, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.