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Tank 41H Salt-Well Sample Analysis

Description: The High Level Waste (HLW) division plans to dissolve at least 100,000 gallons of salt in Tank 41H for use as a feed to the Low Curie Salt process. The planned dissolution and removal methods are not covered by the existing Nuclear Criticality Safety Evaluation (NCSE) for Tank 41H. This sample analysis provides results to support the NCSE needed to qualify the entire contents of the tank for dissolution and removal. This report provides results of the analysis of the Tank 41H salt-well critical… more
Date: September 24, 2002
Creator: Martino, C.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Simulated Waste Testing Of Glycolate Impacts On The 2H-Evaporator System

Description: Glycolic acid is being studied as a total or partial replacement for formic acid in the Defense Waste Processing Facility (DWPF) feed preparation process. After implementation, the recycle stream from DWPF back to the high-level waste tank farm will contain soluble sodium glycolate. Most of the potential impacts of glycolate in the tank farm were addressed via a literature review, but several outstanding issues remained. This report documents the non-radioactive simulant tests impacts of glycol… more
Date: August 13, 2013
Creator: Martino, C. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Analysis Of Tank 38H (HTF-38-14-6, 7) And Tank 43H (HTF-43-14-8, 9) Samples For Support Of The Enrichment Control And Corrosion Control Programs

Description: SRNL performed analysis on Tanks 38H and 43H surface and subsurface supernate samples to support ECP and CCP. The U-235 mass divided by the total U mass ranged from 0.0059 to 0.0060. Uranium concentration ranged from 53.1 mg/L in the Tank 43H surface sample to the 85.1 mg/L in the Tank 38H subsurface sample. The U-235/U and uranium concentration are in line with the prior 2H-Evaporator System ECP samples.
Date: February 27, 2014
Creator: Martino, C. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Tank 41H Drained Saltcake Core Sample Analysis (HTF-E-03-033 - HTF-E-03-035)

Description: The Savannah River Site (SRS) has 49 carbon steel tanks that currently house 37 million gallons of High Level Waste (HLW) in the form of salt supernate, saltcake, and sludge solids. The saltcake in several of the SRS tanks was identified as candidates for the Low Curie Salt (LCS) process. LCS involves removing supernatant liquid, draining the saltcake interstitial liquid, and dissolving the remaining saltcake as a feed for the Saltstone Processing Facility. Three samples were received that corr… more
Date: March 3, 2004
Creator: Martino, C.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Saltcake Dissolution Simulant Tests

Description: Small-scale (15 to 50 mL) dissolution equilibrium tests were performed on surrogate waste representing typical saltcake at the Savannah River and Hanford Sites. The primary objectives of this study were to gain a better understanding of the solid-liquid equilibrium of simulated-waste saltcakes and chemistry of the dissolved salt solutions. These tests were performed in preparation for similar dissolution tests with actual-waste saltcakes. Two types of tests (single-wash and multiple-wash) were … more
Date: February 18, 2003
Creator: Martino, C.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Tank 31H Saltcake Dissolution Tests

Description: This study provides data useful to understanding the salt equilibrium thermodynamics and the transient physical and chemical properties of the dissolved salt solutions.
Date: April 2, 2003
Creator: Martino, C.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Evaporator Feed Qualification Analysis Of Tank 38H And 43H Samples: January 2010 Through April 2013

Description: This report provides the results of analyses that focused on the chemical species that pertain to the sodium aluminosilicate formation potential for archived Tank 38H and 43H subsurface samples from January 2010 through April 2013. Analyses included warm acid strike preparation followed by analysis of silicon, aluminum, and sodium and water dilution preparation followed by analysis for anions. The Tank 43H and 38H supernatant liquid silicon measurements for the January 2010 through April 2013 t… more
Date: August 21, 2013
Creator: Martino, C. J. & Coleman, C. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Rheology Of MonoSodium Titanate (MST) And Modified Mst (mMST) Mixtures Relevant To The Salt Waste Processing Facility

Description: The Savannah River National Laboratory performed measurements of the rheology of suspensions and settled layers of treated material applicable to the Savannah River Site Salt Waste Processing Facility. Suspended solids mixtures included monosodium titanate (MST) or modified MST (mMST) at various solid concentrations and soluble ion concentrations with and without the inclusion of kaolin clay or simulated sludge. Layers of settled solids were MST/sludge or mMST/sludge mixtures, either with or wi… more
Date: July 31, 2013
Creator: Koopman, D. C.; Martino, C. J.; Shehee, T. C. & Poirier, M. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Tank 12H Acidic Chemical Cleaning Sample Analysis And Material Balance

Description: A process of Bulk Oxalic Acid (BOA) chemical cleaning was performed for Tank 12H during June and July of 2013 to remove all or a portion of the approximately 4400 gallon sludge heel. Three strikes of oxalic acid (nominally 4 wt % or 2 wt %) were used at 55 �C and tank volumes of 96- to 140-thousand gallons. This report details the sample analysis of a scrape sample taken prior to BOA cleaning and dip samples taken during BOA cleaning. It also documents a rudimentary material balance for the Tan… more
Date: November 8, 2013
Creator: Martino, C. J.; Reboul, S. H.; Wiersma, B. J. & Coleman, C. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Hanford Supplemental Treatment: Literature and Modeling Review of SRS HLW Salt Dissolution and Fractional Crystallization

Description: In order to accelerate waste treatment and disposal of Hanford tank waste by 2028, the Department of Energy (DOE) and CH2M Hill Hanford Group (CHG), Inc. are evaluating alternative technologies which will be used in conjunction with the Waste Treatment Plant (WTP) to safely pretreat and immobilize the tank waste. Several technologies (Bulk Vitrification and Steam Reforming) are currently being evaluated for immobilizing the pretreated waste. Since the WTP does not have sufficient capacity to pr… more
Date: March 23, 2005
Creator: Choi, A. S.; Flach, G. P.; Martino, C. J.; Zamecnik, J. R.; Harris, M. K.; Wilmarth, W. R. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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