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Title: Defense Waste Repository R&D - Inventory and Waste Characterization.

Abstract

Abstract not provided.

Authors:
Publication Date:
Research Org.:
Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
Sponsoring Org.:
USDOE National Nuclear Security Administration (NNSA)
OSTI Identifier:
1367258
Report Number(s):
SAND2017-5285PE
653411
DOE Contract Number:
AC04-94AL85000
Resource Type:
Conference
Resource Relation:
Conference: Proposed for presentation at the SFWST Annual Working Group Meeting held May 23-25, 2017 in Las Vegas, NV.
Country of Publication:
United States
Language:
English

Citation Formats

Sassani, David. Defense Waste Repository R&D - Inventory and Waste Characterization.. United States: N. p., 2017. Web.
Sassani, David. Defense Waste Repository R&D - Inventory and Waste Characterization.. United States.
Sassani, David. 2017. "Defense Waste Repository R&D - Inventory and Waste Characterization.". United States. doi:. https://www.osti.gov/servlets/purl/1367258.
@article{osti_1367258,
title = {Defense Waste Repository R&D - Inventory and Waste Characterization.},
author = {Sassani, David},
abstractNote = {Abstract not provided.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = 2017,
month = 5
}

Conference:
Other availability
Please see Document Availability for additional information on obtaining the full-text document. Library patrons may search WorldCat to identify libraries that hold this conference proceeding.

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  • This paper describes the results of the analyses of High Level Waste (HLW) sludge slurry samples and of the calculations necessary to decay the radionuclides to meet the reporting requirement in the Waste Acceptance Product Specifications (WAPS) [1]. The concentrations of 45 radionuclides were measured. The results of these analyses provide input for radioactive decay calculations used to project the radionuclide inventory at the specified index years, 2015 and 3115. This information is necessary to complete the Production Records at Savannah River Site's Defense Waste Processing Facility (DWPF) so that the final glass product resulting from Macrobatch 5 (MB5) canmore » eventually be submitted to a Federal Repository. Five of the necessary input radionuclides for the decay calculations could not be measured directly due to their low concentrations and/or analytical interferences. These isotopes are Nb-93m, Pd-107, Cd-113m, Cs-135, and Cm-248. Methods for calculating these species from concentrations of appropriate other radionuclides will be discussed. Also the average age of the MB5 HLW had to be calculated from decay of Sr-90 in order to predict the initial concentration of Nb-93m. As a result of the measurements and calculations, thirty-one WAPS reportable radioactive isotopes were identified for MB5. The total activity of MB5 sludge solids will decrease from 1.6E+04 {micro}Ci (1 {micro}Ci = 3.7E+04 Bq) per gram of total solids in 2008 to 2.3E+01 {micro}Ci per gram of total solids in 3115, a decrease of approximately 700 fold. Finally, evidence will be given for the low observed concentrations of the radionuclides Tc-99, I-129, and Sm-151 in the HLW sludges. These radionuclides were reduced in the MB5 sludge slurry to a fraction of their expected production levels due to SRS processing conditions.« less
  • The main characteristics, physical, chemical as well as radiological of the waste intended to be disposed of in the planned NSR are described. This description is mainly based on the waste inventory investigations performed by the Ignalina Nuclear Power Plant (INPP). The four different waste streams to be disposed of in the NSR are described and investigated. (authors)
  • The Waste Isolation Pilot Plant (WIPP) located in southeastern New Mexico, USA, is being constructed to be a geologic repository in salt beds for the disposal of defense transuranic waste. Site investigation for the WIPP began in 1974. The characteristics of regional geology, hydrology and underground geomechanics are now fairly well understood. Performance assessment to predict the long-term containment capability of the site has identified some additional issues of site characterization that need to be resolved. There is a plan to temporarily emplace some waste at the WIPP for experiments to measure gas generation from waste, but that may notmore » contribute much to assess the suitability of the project for containment of the waste for 10,000 years or more. The facility was designed for a 25 year operation and excavation of the shafts and the major tunnels started in 1982. It is recommended that assessment of the repository`s long-term suitability be accelerated, robust engineered barriers be included in the design, and the project should proceed to make the decision whether to use it as a repository. It is not necessary to first temporarily emplace some waste at the site to make this decision.« less
  • Abstract not provided.