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Title: DOSE RATE VERIFICATION FOR SNS SPENT STRUCTURES

Abstract

Residual dose rate measurements were conducted on two Spallation Neutron Source spent structures, target vessel #13 and proton beam window #5, after extraction from their service locations. These measurements were used to verify calculation methods for radionuclide inventory assessment that are typically performed for nuclear waste characterization and transportation. Neutronics analyses for predicting residual dose rates were carried out using complex and rigorous geometric models of the structures and their surroundings. Calculational results were analyzed and compared to the measured dose rates

Authors:
ORCiD logo [1];  [1];  [1]; ORCiD logo [1]
  1. ORNL
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
USDOE Office of Science (SC), Basic Energy Sciences (BES) (SC-22)
OSTI Identifier:
1491326
DOE Contract Number:  
AC05-00OR22725
Resource Type:
Conference
Resource Relation:
Conference: Topical Meeting of the Radiation Protection & Shielding Division (ANS RPSD-2018) - Santa Fe, New Mexico, United States of America - 8/26/2018 8:00:00 AM-8/31/2018 8:00:00 AM
Country of Publication:
United States
Language:
English

Citation Formats

Popova, Irina I., Gallmeier, Franz X., Trotter, Steven M., and Dayton, Michael J. DOSE RATE VERIFICATION FOR SNS SPENT STRUCTURES. United States: N. p., 2018. Web.
Popova, Irina I., Gallmeier, Franz X., Trotter, Steven M., & Dayton, Michael J. DOSE RATE VERIFICATION FOR SNS SPENT STRUCTURES. United States.
Popova, Irina I., Gallmeier, Franz X., Trotter, Steven M., and Dayton, Michael J. Wed . "DOSE RATE VERIFICATION FOR SNS SPENT STRUCTURES". United States. https://www.osti.gov/servlets/purl/1491326.
@article{osti_1491326,
title = {DOSE RATE VERIFICATION FOR SNS SPENT STRUCTURES},
author = {Popova, Irina I. and Gallmeier, Franz X. and Trotter, Steven M. and Dayton, Michael J.},
abstractNote = {Residual dose rate measurements were conducted on two Spallation Neutron Source spent structures, target vessel #13 and proton beam window #5, after extraction from their service locations. These measurements were used to verify calculation methods for radionuclide inventory assessment that are typically performed for nuclear waste characterization and transportation. Neutronics analyses for predicting residual dose rates were carried out using complex and rigorous geometric models of the structures and their surroundings. Calculational results were analyzed and compared to the measured dose rates},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2018},
month = {8}
}

Conference:
Other availability
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