Evaluation of gamma radiation shielding for nuclear waste shipping casks

PDF Version Also Available for Download.

Description

A method has been developed for evaluating gamma radiation shielding of shipping casks that are used to transport nuclear waste with ill-defined radionuclide contents. The method is based on calculations that establish individual limits for a comprehensive list of radionuclides in the waste, assuming that each radionuclide is uniformly distributed in a volumetric source in the cask. For multiple radionuclide mixtures, a linear fraction rule is used to restrict the total amount of radionuclides such that the sum of the fractions does not exceed 1. As long as the radionuclide limits and the linear fraction rule are followed, it can ... continued below

Physical Description

10 p.

Creation Information

Liu, Y.Y.; Carlson, R.D.; Primeau, S.J. & Wangler, M.E. May 1, 1998.

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.

Authors

  • Liu, Y.Y.
  • Carlson, R.D. Argonne National Lab., IL (United States). Energy Technology Div.
  • Primeau, S.J. Eagle Research Group, Inc., Germantown, MD (United States)
  • Wangler, M.E. Dept. of Energy, Germantown, MD (United States). Office of Transportation, Emergency Management and Analytical Services

Sponsor

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

A method has been developed for evaluating gamma radiation shielding of shipping casks that are used to transport nuclear waste with ill-defined radionuclide contents. The method is based on calculations that establish individual limits for a comprehensive list of radionuclides in the waste, assuming that each radionuclide is uniformly distributed in a volumetric source in the cask. For multiple radionuclide mixtures, a linear fraction rule is used to restrict the total amount of radionuclides such that the sum of the fractions does not exceed 1. As long as the radionuclide limits and the linear fraction rule are followed, it can be shown that the regulatory dose rate requirements for a cask will be satisfied under normal conditions of transport and in a hypothetical accident during which the shielding thickness of the cask has been reduced by 40%.

Physical Description

10 p.

Notes

INIS; OSTI as DE98050530

Source

  • PATRAM `98: 12. international conference on packaging and transportation of radioactive material, Paris (France), 10-15 May 1998

Language

Item Type

Identifier

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

  • Other: DE98050530
  • Report No.: ANL/ET/CP--94812
  • Report No.: CONF-980507--
  • Grant Number: W-31109-ENG-38
  • Office of Scientific & Technical Information Report Number: 645503
  • Archival Resource Key: ark:/67531/metadc692464

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, 1998

Added to The UNT Digital Library

  • Aug. 14, 2015, 8:43 a.m.

Description Last Updated

  • June 14, 2016, 3:08 p.m.

Usage Statistics

When was this article last used?

Yesterday: 0
Past 30 days: 0
Total Uses: 6

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

Liu, Y.Y.; Carlson, R.D.; Primeau, S.J. & Wangler, M.E. Evaluation of gamma radiation shielding for nuclear waste shipping casks, article, May 1, 1998; Illinois. (digital.library.unt.edu/ark:/67531/metadc692464/: accessed October 23, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.