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Title: Characterization of Filters Loaded With Reactor Strontium Carbonate - 13203

Abstract

A collection of three highly radioactive filters containing reactor strontium carbonate were being prepared for disposal. All three filters were approximately characterized at the time of manufacture by gravimetric methods. The first filter had been partially emptied, and the quantity of residual activity was uncertain. Dose rate to activity modeling using the Monte-Carlo N Particle (MCNP) code was selected to confirm the gravimetric characterization of the full filters, and to fully characterize the partially emptied filter. Although dose rate to activity modeling using MCNP is a common technique, it is not often used for Bremsstrahlung-dominant materials such as reactor strontium. As a result, different MCNP modeling options were compared to determine the optimum approach. This comparison indicated that the accuracy of the results were heavily dependent on the MCNP modeling details and the location of the dose rate measurement point. The optimum model utilized a photon spectrum generated by the Oak Ridge Isotope Generation and Depletion (ORIGEN) code and dose rates measured at 30 cm. Results from the optimum model agreed with the gravimetric estimates within 15%. It was demonstrated that dose rate to activity modeling can be successful for Bremsstrahlung-dominant radioactive materials. However, the degree of success is heavilymore » dependent on the choice of modeling techniques. (authors)« less

Authors:
 [1];  [2]
  1. Worley Parsons Polestar, 601 Williams Boulevard, Suite 4A, Richland WA 99352 (United States)
  2. Pacific Northwest National Laboratory, P.O. Box 999, Richland WA 99352 (United States)
Publication Date:
Research Org.:
WM Symposia, 1628 E. Southern Avenue, Suite 9-332, Tempe, AZ 85282 (United States)
OSTI Identifier:
22230953
Report Number(s):
INIS-US-13-WM-13203
TRN: US14V0409052038
Resource Type:
Conference
Resource Relation:
Conference: WM2013: Waste Management Conference: International collaboration and continuous improvement, Phoenix, AZ (United States), 24-28 Feb 2013; Other Information: Country of input: France; 10 refs.
Country of Publication:
United States
Language:
English
Subject:
61 RADIATION PROTECTION AND DOSIMETRY; 12 MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; ACCURACY; APPROXIMATIONS; BREMSSTRAHLUNG; COMPARATIVE EVALUATIONS; DOSE RATES; FILTERS; MONTE CARLO METHOD; OAK RIDGE; PHOTONS; RADIOACTIVE MATERIALS; SIMULATION; STRONTIUM; STRONTIUM CARBONATES

Citation Formats

Josephson, Walter S., and Steen, Franciska H. Characterization of Filters Loaded With Reactor Strontium Carbonate - 13203. United States: N. p., 2013. Web.
Josephson, Walter S., & Steen, Franciska H. Characterization of Filters Loaded With Reactor Strontium Carbonate - 13203. United States.
Josephson, Walter S., and Steen, Franciska H. Mon . "Characterization of Filters Loaded With Reactor Strontium Carbonate - 13203". United States.
@article{osti_22230953,
title = {Characterization of Filters Loaded With Reactor Strontium Carbonate - 13203},
author = {Josephson, Walter S. and Steen, Franciska H.},
abstractNote = {A collection of three highly radioactive filters containing reactor strontium carbonate were being prepared for disposal. All three filters were approximately characterized at the time of manufacture by gravimetric methods. The first filter had been partially emptied, and the quantity of residual activity was uncertain. Dose rate to activity modeling using the Monte-Carlo N Particle (MCNP) code was selected to confirm the gravimetric characterization of the full filters, and to fully characterize the partially emptied filter. Although dose rate to activity modeling using MCNP is a common technique, it is not often used for Bremsstrahlung-dominant materials such as reactor strontium. As a result, different MCNP modeling options were compared to determine the optimum approach. This comparison indicated that the accuracy of the results were heavily dependent on the MCNP modeling details and the location of the dose rate measurement point. The optimum model utilized a photon spectrum generated by the Oak Ridge Isotope Generation and Depletion (ORIGEN) code and dose rates measured at 30 cm. Results from the optimum model agreed with the gravimetric estimates within 15%. It was demonstrated that dose rate to activity modeling can be successful for Bremsstrahlung-dominant radioactive materials. However, the degree of success is heavily dependent on the choice of modeling techniques. (authors)},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2013},
month = {7}
}

Conference:
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