Published December 1992 | Version v1
Report

RADSOURCE

Description

Waste stream scaling factors based on sampling programs are vulnerable to one or more of the following factors: sample representativeness, analytic accuracy, and measurement sensitivity. As an alternative to sample analyses or as a verification of the sampling results, this project proposes the use of the RADSOURCE code, which accounts for the release of fuel-source radionuclides. Once the release rates of these nuclides from fuel are known, the code develops scaling factors for waste streams based on easily measured Cobalt-60 (Co-60) and Cesium-137 (Cs-137). The project team developed mathematical models to account for the appearance rate of 10CFR61 radionuclides in reactor coolant. They based these models on the chemistry and nuclear physics of the radionuclides involved. Next, they incorporated the models into a computer code that calculates plant waste stream scaling factors based on reactor coolant gamma- isotopic data. Finally, the team performed special sampling at 17 reactors to validate the models in the RADSOURCE code

Availability note (English)

Available from EPRI Distribution Center, 207 Coggins Drive, PO Box 23205, Pleasant Hill, CA 94523.

Additional details

Additional titles

Subtitle (English)
Volume 1, Part 1, A scaling factor prediction computer program technical manual and code validation: Final report

Publishing Information

Imprint Pagination
165 p.
Report number
EPRI-TR--101960-Vol.1-Pt.1

Optional Information