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Title: DISSOLVED CONCENTRATION LIMITS OF RADIOACTIVE ELEMENTS

Abstract

The purpose of this study is to evaluate dissolved concentration limits (also referred to as solubility limits) of elements with radioactive isotopes under probable repository conditions, based on geochemical modeling calculations using geochemical modeling tools, thermodynamic databases, field measurements, and laboratory experiments. The scope of this activity is to predict dissolved concentrations or solubility limits for elements with radioactive isotopes (actinium, americium, carbon, cesium, iodine, lead, neptunium, plutonium, protactinium, radium, strontium, technetium, thorium, and uranium) relevant to calculated dose. Model outputs for uranium, plutonium, neptunium, thorium, americium, and protactinium are provided in the form of tabulated functions with pH and log fCO{sub 2} as independent variables, plus one or more uncertainty terms. The solubility limits for the remaining elements are either in the form of distributions or single values. Even though selection of an appropriate set of radionuclides documented in Radionuclide Screening (BSC 2002 [DIRS 160059]) includes actinium, transport of Ac is not modeled in the total system performance assessment for the license application (TSPA-LA) model because of its extremely short half-life. Actinium dose is calculated in the TSPA-LA by assuming secular equilibrium with {sup 231}Pa (Section 6.10); therefore, Ac is not analyzed in this report. The output data frommore » this report are fundamental inputs for TSPA-LA used to determine the estimated release of these elements from waste packages and the engineered barrier system. Consistent modeling approaches and environmental conditions were used to develop solubility models for the actinides discussed in this report. These models cover broad ranges of environmental conditions so they are applicable to both waste packages and the invert. Uncertainties from thermodynamic data, water chemistry, temperature variation, and activity coefficients have been quantified or otherwise addressed.« less

Authors:
Publication Date:
Research Org.:
Yucca Mountain Project, Las Vegas, Nevada
Sponsoring Org.:
USDOE
OSTI Identifier:
883412
Report Number(s):
ANL-WIS-MD-000010 REV 05
DOC.20050713.0006 DC#45029; TRN: US0603355
DOE Contract Number:  
AC28-01RW12101
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
12 MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; 38 RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCLEAR CHEMISTRY; ACTINIUM; AMERICIUM; CARBON; CESIUM; IODINE; LEAD; NEPTUNIUM; PLUTONIUM; PROTACTINIUM; RADIUM; REACTION KINETICS; SOLUBILITY; STRONTIUM; TECHNETIUM; THERMODYNAMICS; THORIUM; URANIUM; GEOCHEMISTRY; RADIOACTIVE WASTE DISPOSAL; RADIONUCLIDE MIGRATION

Citation Formats

P. Bernot. DISSOLVED CONCENTRATION LIMITS OF RADIOACTIVE ELEMENTS. United States: N. p., 2005. Web. doi:10.2172/883412.
P. Bernot. DISSOLVED CONCENTRATION LIMITS OF RADIOACTIVE ELEMENTS. United States. doi:10.2172/883412.
P. Bernot. Wed . "DISSOLVED CONCENTRATION LIMITS OF RADIOACTIVE ELEMENTS". United States. doi:10.2172/883412. https://www.osti.gov/servlets/purl/883412.
@article{osti_883412,
title = {DISSOLVED CONCENTRATION LIMITS OF RADIOACTIVE ELEMENTS},
author = {P. Bernot},
abstractNote = {The purpose of this study is to evaluate dissolved concentration limits (also referred to as solubility limits) of elements with radioactive isotopes under probable repository conditions, based on geochemical modeling calculations using geochemical modeling tools, thermodynamic databases, field measurements, and laboratory experiments. The scope of this activity is to predict dissolved concentrations or solubility limits for elements with radioactive isotopes (actinium, americium, carbon, cesium, iodine, lead, neptunium, plutonium, protactinium, radium, strontium, technetium, thorium, and uranium) relevant to calculated dose. Model outputs for uranium, plutonium, neptunium, thorium, americium, and protactinium are provided in the form of tabulated functions with pH and log fCO{sub 2} as independent variables, plus one or more uncertainty terms. The solubility limits for the remaining elements are either in the form of distributions or single values. Even though selection of an appropriate set of radionuclides documented in Radionuclide Screening (BSC 2002 [DIRS 160059]) includes actinium, transport of Ac is not modeled in the total system performance assessment for the license application (TSPA-LA) model because of its extremely short half-life. Actinium dose is calculated in the TSPA-LA by assuming secular equilibrium with {sup 231}Pa (Section 6.10); therefore, Ac is not analyzed in this report. The output data from this report are fundamental inputs for TSPA-LA used to determine the estimated release of these elements from waste packages and the engineered barrier system. Consistent modeling approaches and environmental conditions were used to develop solubility models for the actinides discussed in this report. These models cover broad ranges of environmental conditions so they are applicable to both waste packages and the invert. Uncertainties from thermodynamic data, water chemistry, temperature variation, and activity coefficients have been quantified or otherwise addressed.},
doi = {10.2172/883412},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2005},
month = {7}
}