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New source term model for the RESRAD-OFFSITE code version 3

Author: C Yu; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research,; U.S. Nuclear Regulatory Commission. Division of Risk Assessment,; Argonne National Laboratory.
Publisher: Washington, DC : Office of Nuclear Regulatory Research, United States Nuclear Regulatory Commission, 2013.
Edition/Format:   eBook : Document : National government publication : EnglishView all editions and formats
Summary:
This report documents the new source term model developed and implemented in Version 3 of the RESRAD-OFFSITE code. This new source term model includes: (1) "first order release with transport" option, in which the release of the radionuclide is proportional to the inventory in the primary contamination and the user-specified leach rate is the proportionality constant, (2) "equilibrium desorption release" option, in  Read more...
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Additional Physical Format: Print version:
Yu, C.
New source term model for the RESRAD-OFFSITE code version 3
(OCoLC)868227882
Material Type: Document, Government publication, National government publication, Internet resource
Document Type: Internet Resource, Computer File
All Authors / Contributors: C Yu; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research,; U.S. Nuclear Regulatory Commission. Division of Risk Assessment,; Argonne National Laboratory.
OCLC Number: 868227793
Notes: "December 2013."
Title from title screen (viewed on Jan. 16, 2014).
"NUREG/CR-7127."
"ANL/EVS/TM/11."
Description: 1 online resource ([355] pages) : illustrations
Responsibility: prepared by C. Yu [and three others].

Abstract:

This report documents the new source term model developed and implemented in Version 3 of the RESRAD-OFFSITE code. This new source term model includes: (1) "first order release with transport" option, in which the release of the radionuclide is proportional to the inventory in the primary contamination and the user-specified leach rate is the proportionality constant, (2) "equilibrium desorption release" option, in which the user specifies the distribution coefficient which quantifies the partitioning of the radionuclide between the solid and aqueous phases, and (3) "uniform release" option, in which the radionuclides are released from a constant fraction of the initially contaminated material during each time interval and the user specifies the duration over which the radionuclides are released.

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