Microgamma Scan System for analyzing radial isotopic profiles of irradiated transmutation fuels

PDF Version Also Available for Download.

Description

The U. S. Global Nuclear Energy Partnership / Advanced Fuel Cycle Initiative (GNEP/AFCI) is developing metallic transmutation alloys as a fuel form to transmute the long-lived transuranic actinide isotopes contained in spent nuclear fuel into shorter-lived fission products. The AFCI program has irradiated and examined eleven metallic alloy transmutation fuel specimens to evaluate the feasibility of actinide transmutation in advanced sodium-cooled fast reactors and thermal reactor implementation. Initial results of postirradiation examinations indicated the irradiation performance of the actinide-bearing compositions is similar to uranium-plutonium-zirconium ternary metallic alloy fuels (U-xPu-10Zr). Further studies to characterize radial burnup profile, constituent migration, and fuel ... continued below

Creation Information

Hilton, Bruce A. & McGrath, Christopher A. May 1, 2008.

Context

This article 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 article can be viewed below.

Who

People and organizations associated with either the creation of this article 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 article. Follow the links below to find similar items on the Digital Library.

Description

The U. S. Global Nuclear Energy Partnership / Advanced Fuel Cycle Initiative (GNEP/AFCI) is developing metallic transmutation alloys as a fuel form to transmute the long-lived transuranic actinide isotopes contained in spent nuclear fuel into shorter-lived fission products. The AFCI program has irradiated and examined eleven metallic alloy transmutation fuel specimens to evaluate the feasibility of actinide transmutation in advanced sodium-cooled fast reactors and thermal reactor implementation. Initial results of postirradiation examinations indicated the irradiation performance of the actinide-bearing compositions is similar to uranium-plutonium-zirconium ternary metallic alloy fuels (U-xPu-10Zr). Further studies to characterize radial burnup profile, constituent migration, and fuel cladding chemical interaction (FCCI) are in progress. A microgamma scan system is being developed to analyze the radial distribution of fission products, such as Cs-137, Cs-134, Ru-106, and Zr-95, in irradiated fuel cross-sections. The microgamma scan system consists of a set of indexed sample collimator blocks and a sample holder, which interfaces with the INL Analytical Laboratory Hot Cell (ALHC) Gamma Scan System high purity germanium detector, multichannel analyzer, and removable collimators. The microgamma scan results will be used to evaluate radial burnup profile, cesium migration to the sodium bond and constituent migration within the fuel. These data will further clarify the comparative irradiation performance of actinide-bearing metallic transmutation fuel forms and uranium-plutonium-zirconium alloys. Preliminary measurements of the microgamma scan system will be discussed. A simplified model of the microgamma scan system was developed in MCNP and used to investigate the system performance and to interpret data from the scoping studies. Recommendations for improving the MCGS analyses are discussed.

Source

  • Atalante 2008,Montpellier, France,05/19/2008,05/23/2008

Language

Item Type

Identifier

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

  • Report No.: INL/CON-07-13400
  • Grant Number: DE-AC07-99ID-13727
  • Office of Scientific & Technical Information Report Number: 948592
  • Archival Resource Key: ark:/67531/metadc899479

Collections

This article 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 article?

When

Dates and time periods associated with this article.

Creation Date

  • May 1, 2008

Added to The UNT Digital Library

  • Sept. 27, 2016, 1:39 a.m.

Description Last Updated

  • Nov. 7, 2016, 4:25 p.m.

Usage Statistics

When was this article last used?

Yesterday: 0
Past 30 days: 0
Total Uses: 1

Interact With This Article

Here are some suggestions for what to do next.

Start Reading

PDF Version Also Available for Download.

Citations, Rights, Re-Use

Hilton, Bruce A. & McGrath, Christopher A. Microgamma Scan System for analyzing radial isotopic profiles of irradiated transmutation fuels, article, May 1, 2008; [Idaho Falls, Idaho]. (digital.library.unt.edu/ark:/67531/metadc899479/: accessed December 13, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.