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Title: Development of Pre-processing.


Abstract not provided.

Publication Date:
Research Org.:
Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
Sponsoring Org.:
USDOE Office of Science (SC)
OSTI Identifier:
Report Number(s):
DOE Contract Number:
Resource Type:
Resource Relation:
Conference: Proposed for presentation at the Sandia Intern Symposium.
Country of Publication:
United States

Citation Formats

Caras, Kimberly, and Greathouse, Jeffery A. Development of Pre-processing.. United States: N. p., 2016. Web.
Caras, Kimberly, & Greathouse, Jeffery A. Development of Pre-processing.. United States.
Caras, Kimberly, and Greathouse, Jeffery A. 2016. "Development of Pre-processing.". United States. doi:.
title = {Development of Pre-processing.},
author = {Caras, Kimberly and Greathouse, Jeffery A.},
abstractNote = {Abstract not provided.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = 2016,
month = 7

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  • The Department of Energy's (DOE) Savannah River Site (SRS) high-level waste (HLW) program is responsible for storage, treatment, and immobilization of HLW for disposal. The Salt Processing Project (SPP) is the salt waste (water-soluble) treatment portion of this effort. The overall SPP encompasses the selection, design, construction, and operation of technologies to prepare the salt-waste feed material for immobilization at the site's Saltstone Production Facility (SPF) and vitrification facility (Defense Waste Processing Facility [DWPF]). Major constituents that must be removed from the salt waste and sent as feed to DWPF include cesium (Cs), strontium (Sr), and actinides. In April 2000,more » the DOE Deputy Secretary for Project Completion (EM-40) established the SRS Salt Processing Project Technical Working Group (TWG) to manage technology development of treatment alternatives for SRS high-level salt wastes. The separation alternatives investigated included three candidate Cs-removal processes selected, as well as actinide and Sr removal that are also required as a part of each process. The candidate Cs-removal processes are: crystalline Silicotitanate Non-Elutable Ion Exchange (CST); caustic Side Solvent Extraction (CSSX); and small Tank Tetraphenylborate Precipitation (STTP). The Tanks Focus Area was asked to assist DOE by managing the SPP research and development (R&D), revising roadmaps, and developing down-selection criteria. The down-selection decision process focused its analysis on three levels: (a) identification of goals that the selected technology should achieve, (b) selection criteria that are a measure of performance of the goal, and (c) criteria scoring and weighting for each technology alternative. After identifying the goals and criteria, the TWG analyzed R&D results and engineering data and scored the technology alternatives versus the criteria. Based their analysis and scoring, the TWG recommended CSSX as the preferred alternative. This recommendation was formalized in July 2001 when DOE published the Savannah River Site Salt Processing Alternatives Final Supplemental Environmental Impact Statement (SEIS) and was finalized in the DOE Record of Decision issued in October 2001.« less
  • Irradiated nuclear fuel has been reprocessed at the Idaho Chemical Processing Plant (ICPP), which is a part of the Idaho National Engineering Laboratory (INEL), since 1953 to recover uranium-235 and krypton-85 for the US Department of Energy (DOE). The resulting acidic high-level liquid radioactive waste (HLLW) has been solidified to a high-level waste (HLW) calcine since 1963 and stored in stainless-steel bins enclosed in concrete vaults. Residual HLW and radioactive sodium-bearing waste are stored in stainless-steel underground tanks contained in concrete vaults. Several different types of unprocessed irradiated DOE-owned fuels are also stored at INEL. In April 1992, DOE announcedmore » that spent fuel would no longer be reprocessed to recover enriched uranium. As a result of the decision to curtail reprocessing the ICPP Spent Fuel and Waste Management Technology Development plan has been implemented to identify acceptable options for disposing of the (1) sodium-bearing liquid radioactive waste, (2) radioactive calcine, and (3) irradiated spent fuel stored at the INEL. The plan was developed jointly by DOE and Westinghouse Idaho Nuclear Company, Inc. (WINCO).« less
  • The effect of thermomechanical processing (TMP) by warm rolling, of Al-8Mg-0.4 Cu and Al-10 Mg-0.5 Mn alloys has been investigated with particular attention to the influence of the Cu or Mn addition on homogenization and refinement of the microstructure. Warm rolling of such high Mg, Al-Mg alloys results in refined substructures in conjunction with a fine, uniformly distributed dispersion of the intermetallic {beta} (Al{sub 8}Mg{sub 5}). The Mn addition in particular enhanced refinement attained with the TMP; substructure of 1.0 {mu}m size with submicron intermetallic {beta} was attained in the Al-10Mg-0.5 Mn alloy. Associated with such a structure are strength/ductilitymore » combinations comparable to those of 7075-T6 with enhanced corrosion resistance resulting from the fine structure and absence of continuous grain boundary {beta}. Preliminary fatigue data suggests that these microstructures also result in smooth sample fatigue characteristics also comparable to those of a 7075-T6 comparison alloy.« less
  • The residual thermal stresses developed during processing of fiber-reinforced semicrystalline thermoplastic composites is strongly affected by variations in temperature and degree of crystallinity within a laminate. In order to understand the processes at work, a model predicting the temperature and volume fraction crystallinity distributions over the cross-sectional area of these laminates during processing from the melt has been developed. In this study, emphasis is on the prediction of temperature and crystallinity gradients in the vicinity of free-edges. Results are shown for the case of unidirectional APC-2 laminates for different surface cooling rates. 19 refs.