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in publisher: "Savannah River Site S.C."  
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Adsorption of Pu(IV) Polymer onto 304L Stainless Steel

Description: 'The report, Technical Basis for Safe Operations with Pu-239 Polymer in NMS S Operating Facilities (F H Areas), (WSRC-TR-99-00008) was issued in an effort to upgrade the Authorization Basis (AB) for H Area facilities relative to nuclear criticality. At the time, insufficient data were found in the literature to quantify the adsorption of Pu polymer onto the surfaces of stainless steel tanks. Additional experimental or literature information on the adsorption of Pu(IV) polymer and its removal wa… more
Date: July 16, 1999
Creator: Bronikowski, M.G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Phase C Flygt Mixer Test Results

Description: The Savannah River Site (SRS) teamed with the Pacific Northwest National Laboratory (PNNL), Oak Ridge National Laboratory (ORNL), and ITT Flygt Corporation to conduct a test program evaluating shrouded axial propeller mixers (Flygt mixers) for heel removal in SRS Tank 19. SRS is identifying and investigating techniques to remove sludge heels from waste tanks such as Tank 19.
Date: June 8, 1999
Creator: Poirier, M.R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

FY99 Status Report on the HSV

Description: 'The HSV in storage in MTF has been monitored during FY99, and its overpressure has been sampled and analyzed. The HSV''s internal pressure continues to rise slowly, and the overpressure still analyzes as 100 percent 3He. The titanium tritide sample that was to be monitored annually and which had developed a leak last year has been repaired and isotherms measured. Unfortunately the sample was showing significant unexpected 3He release, so the isotherm data is corrupted by unknown levels of 3He.… more
Date: October 15, 1999
Creator: Shanahan, K. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Performance of Vacuum Pumps to be Used in Tritium Extraction Facility

Description: The goal of this test was to measure pump operating characteristics for three different gases and a wider range of conditions than for the vendor data. Test results will be used by Engineering Development Section for incorporation in a computer model of the pump train.
Date: April 6, 1999
Creator: Steimke, J. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

SAVANNAH RIVER TECHNOLOGY CENTER MONTHLY REPORT AUGUST 1992

Description: 'This monthly report summarizes Programs and Accomplishments of the Savannah River Technology Center in support of activities at the Savannah River Site. The following categories are addressed: Reactor, Tritium, Separations, Environmental, Waste Management, General, and Items of Interest.'
Date: June 21, 1999
Creator: Ferrell, J.M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Defense In-Depth Accident Analysis Evaluation of Tritium Facility Bldgs. 232-H, 233-H, and 234-H

Description: 'The primary purpose of this report is to document a Defense-in-Depth (DID) accident analysis evaluation for Department of Energy (DOE) Savannah River Site (SRS) Tritium Facility Buildings 232-H, 233-H, and 234-H. The purpose of a DID evaluation is to provide a more realistic view of facility radiological risks to the offsite public than the bounding deterministic analysis documented in the Safety Analysis Report, which credits only Safety Class items in the offsite dose evaluation.'
Date: May 10, 1999
Creator: Blanchard, A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Enhanced Waste Tank Level Model

Description: 'With the increased sensitivity of waste-level measurements in the H-Area Tanks and with periods of isolation, when no mass transfer occurred for certain tanks, waste-level changes have been recorded with are unexplained.'
Date: June 24, 1999
Creator: Duignan, M.R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Acceptable Knowledge Summary Report for Waste Stream: SR-T001-221F-HET/Drums

Description: This report is fully responsive to the requirements of Section 4.0 Acceptable Knowledge from the WIPP Transuranic Waste Characterization Quality Assurance Plan, CAO-94-1010, and provides a sound, (and auditable) characterization that satisfies the WIPP criteria for Acceptable Knowledge.
Date: June 14, 1999
Creator: Lunsford, G. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Plutonium Immobilization Can Loading Conceptual Design

Description: 'The Plutonium Immobilization Facility will encapsulate plutonium in ceramic pucks and seal the pucks inside welded cans. Remote equipment will place these cans in magazines and the magazines in a Defense Waste Processing Facility (DWPF) canister. The DWPF will fill the canister with glass for permanent storage. This report discusses the Plutonium Immobilization can loading conceptual design and includes a process block diagram, process description, preliminary equipment specifications, and sev… more
Date: May 13, 1999
Creator: Kriikku, E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Corrosion Evaluation of Tank 40 Leak Detection Box

Description: 'Leak detection from the transfer lines in the tank farm has been a concern for many years because of the need to minimize exposure of personnel and contamination of the environment. The leak detection box (LDB) is one line of defense, which must be maintained to meet this objective. The evaluation of a failed LDB was one item from an action plan aimed at minimizing the degradation of LDBs. The Tank 40 LDB, which failed in service, was dug up and shipped to SRTC for evaluation. During a video i… more
Date: July 29, 1999
Creator: Mickalonis, J.I.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Resolving Radiological Classification and Release Issues for Many DOE Solid Wastes and Salvageable Materials

Description: The cost effective radiological classification and disposal of solid materials with potential volume contamination, in accordance with applicable U.S. Department of Energy (DOE) Orders, suffers from an inability to unambiguously distinguish among transuranic waste, low-level waste, and unconditional-release materials. Depending on the classification, disposal costs can vary by a hundred-fold. But in many cases, the issues can be easily resolved by a combination of process information, some simp… more
Date: June 14, 1999
Creator: Hochel, R. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Thermal Analysis of LANL Ion Exchange Column

Description: This document reports results from an ion exchange column heat transfer analysis requested by Los Alamos National Laboratory (LANL). The object of the analysis is to demonstrate that the decay heat from the Pu-238 will not cause resin bed temperatures to increase to a level where the resin significantly degrades.
Date: June 16, 1999
Creator: Laurinat, J.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

EXPERIMENTAL STUDY TO EVALUATE CORROSION OF THE F-CANYON DISSOLVER DURING THEUNIRRADIATED MARK-42 CAMPAIGN

Description: Unirradiated Mark 42 fuel tubes are to be dissolved in an upcoming campaign in F-canyon. Savannah River Technology Center (SRTC)/Chemical & Hydrogen Technology Section (CHTS) identified a flow sheet for the dissolution of these Mark 42 fuel tubes which required a more aggressive dissolver solution than previously required for irradiated Mark 42 fuel tubes. Subsequently, SRTC/MTS was requested to develop and perform a corrosion testing program to assess the impact of new flow sheets on corrosion… more
Date: August 1, 1999
Creator: Mickalonis, J & Kerry Dunn, K
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Thermal Analysis of the 9975 Package with the 3013 Configuration During Normal Conditions of Transport

Description: Thermal analysis of the 9975 package with three configurations of the BNFL 3013 outer container (with Rocky Flats, SRS, and BNFL inner containers) have been performed for Normal Conditions of Transport (NCT) of plutonium oxide and metal. The NCT is defined in 10 CFR 71.71(c)(1) s an ambient of 100 F (38 C) in still air with 800 W/m{sup 2} and 400 W/m{sup 2} of solar heating on the drum top and sides, respectively. The 9975 drum package is considered to be in an upright position, and the drum bo… more
Date: February 22, 1999
Creator: Hensel, S
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Hanford Immobilized Low-Activity Waste Product Acceptance Test Plan

Description: 'The Hanford Site has been used to produce nuclear materials for the U.S. Department of Energy (DOE) and its predecessors. A large inventory of radioactive and mixed waste, largely generated during Pu production, exists in 177 underground single- and double-shell tanks. These wastes are to be retrieved and separated into low-activity waste (LAW) and high-level waste (HLW) fractions. The DOE is proceeding with an approach to privatize the treatment and immobilization of Handord''s LAW and HLW.'
Date: June 22, 1999
Creator: Peeler, D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

FY99 Status Report on the HSV

Description: 'The HSV in storage in MTF has been monitored during FY99, and its overpressure has been sampled and analyzed. The HSV''s internal pressure continues to rise slowly, and the overpressure still analyzes as 100 percent 3He. The titanium tritide sample that was to be monitored annually and which had developed a leak last year has been repaired and isotherms measured. Unfortunately the sample was showing significant unexpected 3He release, so the isotherm data is corrupted by unknown levels of 3He.… more
Date: October 15, 1999
Creator: Shanahan, K. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Hydrogeological Analysis and Groundwater Flow for C-Reactor Area with Contaminant Transport for C-Reactor Seepage Basins (CRSB) and C-Area Burning/Rubble Pit (CBRP)

Description: A groundwater flow model encompassing approximately 4 mi2 within C Reactor area has been developed. The objectives and goals of the C Reactor Area groundwater model are to: Provide a common hydrogeologic and groundwater flow modeling framework for C Area that can be easily updated as additional field data is collected from waste site investigations. Provide a baseline groundwater flow model for use in subsequent flow and transport simulations for remedial/feasibility studies for C Area waste si… more
Date: December 1, 1999
Creator: FLACH, GREGORYP.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

An Evaluation of Liquidus Temperature as a Function of Waste Loading for a Tank 42 "Sludge Only"/Frit 200 Flowsheet

Description: 'The waste glass produced in the SRS Defense Waste Processing Faiclity (DWPF) process must comply with Waste Acceptance Product Specifications (WAPS) and process control requirements by demonstrating, to a high degree of confidence, that melter feed will produce glass satisfying all quality and processing requirements.'
Date: May 10, 1999
Creator: Peeler, D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Glass Waste Forms for Oak Ridge Tank Wastes: Fiscal Year 1998 Report for Task Plan SR-16WT-31, Task B

Description: Using ORNL information on the characterization of the tank waste sludges, SRTC performed extensive bench-scale vitrification studies using simulants. Several glass systems were tested to ensure the optimum glass composition (based on the glass liquidus temperature, viscosity and durability) is determined. This optimum composition will balance waste loading, melt temperature, waste form performance and disposal requirements. By optimizing the glass composition, a cost savings can be realized dur… more
Date: May 10, 1999
Creator: Andrews, M.K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Subcritical Measurements Research Program for Fresh and Spent Materials Test Reactor Fuels

Description: 'A series of subcritical noise measurements were performed on fresh and spent University of Missouri Research Reactor fuel assemblies. These experimental measurements were performed for the purposes of providing benchmark quality data for validating transport theory computer codes and nuclear cross-section data used to perform criticality safety analyses for highly enriched, uranium-aluminum Material Test Reactor fuel assemblies. A mechanical test rig was designed and built to hold up to four f… more
Date: May 13, 1999
Creator: Blanchard, A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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