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Chemical modeling of backfill composed of quartz sand, lime and an Fe-phase

Description: The area adjacent to the waste package is an important component of the engineered barrier system in a high level radioactive waste repository. The combination of lime, quartz sand, and a phase containing reduced iron is investigated whether it can achieve reduction of oxygen in the waste emplacement drift (thereby reducin corrosion rates) and increase the pH. The simulations conducted to date have examined the following backfill options: Fe metal only, Fe metal and lime, and iron metal/lime/quartz sand in equal volume ratios. Each option was simulated under two environments: limited and unlimited air exchange with the atmosphere. Results suggest that the most important variable during the process of chemical conditioning is the amount of air exchange that occurs in the emplacement drift. The desired chemical conditioing (both oxidation potential and pH) will be far less effective in an emplacement that experiences an unlimited exchange of air with the atmosphere.
Date: January 1, 1997
Creator: Meike, A. & Glassley, W.E.
Partner: UNT Libraries Government Documents Department

In Situ Void Fraction and Gas Volume in Hanford Tank 241-SY-101 as Measured with the Void Fraction Instrument

Description: The void fraction instrument (WI) was deployed in Tank 241-SY-101 three times in 1998 to confm and locate the retained gas (void) postulated to be causing the accelerating waste level rise observed since 1995. The design, operation, and data reduction model of the WI are described along with validation testing and potential sources of uncertainty. The test plans, field observations and void measurements are described in detail, including the total gas volume calculations and the gas volume model. Based on 1998 data, the void fraction averaged 0.013 i 0.001 in the mixed slurry and 0.30 ~ 0.04 in the crust. This gives gas volumes (at standard pressure and temperature) of 87 t 9 scm in the slurry and 138 ~ 22 scm in the crust for a total retained gas volume of221 *25 scm. This represents an increase of about 74 scm in the crust and a decrease of about 34 scm in the slurry from 1994/95 results. The overall conclusion is that the gas retention is occurring mainly in the crust layer and there is very little gas in the mixed slurry and loosely settled layers below. New insights on crust behavior are also revealed.
Date: November 10, 1998
Creator: Stewart, CW; Chen, G; Alzheimer, JM & Meyer, PA
Partner: UNT Libraries Government Documents Department

Nuclear Waste Policy Act

Description: The Nuclear Waste Policy Act (NWPA) supports the use of deep geologic repositories for the safe storage and/or disposal of radioactive waste. The Act establishes procedures to evaluate and select sites for geologic repositories and for the interaction of state and federal governments. It also provides a timetable of key milestones the federal agencies must meet in carrying out the program. The NWPA assigns the Department of Energy (DOE) the responsibility to site, build, and operate a deep geologic repository for the disposal of high-level waste and spent nuclear fuel. It directs EPA to develop standards for protection of the general environment from offsite releases of radioactive material in repositories. The Act directs the Nuclear Regulatory Commission (NRC) to license DOE to operate a repository only if it meets EPA's standards and all other relevant requirements.
Date: January 7, 1983
Creator: United States. Congress.
Partner: UNT Libraries

Tank 241-AP-108 grab sampling and analysis plan

Description: This Sampling and Analysis Plan (SAP) will identify characterization objectives for sample collection, laboratory analytical evaluation, and reporting requirements for tank 241-AP-108 (AP 108). It is written in accordance with the Tank 241-AP-108 Tank Characterization Plan, the Tank Safety Screening Data Quality Objective, the 242-A Evaporator Liquid Effluent Retention Facility Data Quality Objectives, and the Data Quality Objectives for Tank Farms Waste Compatibility Program.
Date: February 7, 1997
Creator: Baldwin, J.H., Fluor Daniel Hanford
Partner: UNT Libraries Government Documents Department

Tank waste remediation system baseline tank waste inventory estimates for fiscal year 1995

Description: A set of tank-by-tank waste inventories is derived from historical waste models, flowsheet records, and analytical data to support the Tank Waste Remediation System flowsheet and retrieval sequence studies. Enabling assumptions and methodologies used to develop the inventories are discussed. These provisional inventories conform to previously established baseline inventories and are meant to serve as an interim basis until standardized inventory estimates are made available.
Date: December 6, 1996
Creator: Shelton, L. W.
Partner: UNT Libraries Government Documents Department

The Sort on Radioactive Waste Type Model: A method to sort single-shell tanks into characteristics groups

Description: The Sort on Radioactive Waste Type (SORWT) Model is a method to categorize Hanford Site single-shell tanks (SSTS) into groups of tanks expected to exhibit similar chemical and physical characteristics based on their major waste types and processing histories. The model has identified 24 different waste-type groups encompassing 133 of the 149 SSTs and 93% of the total waste volume in SSTS. The remaining 16 SSTs and associated wastes could not be grouped. according to the established criteria and were placed in an ungrouped category. A detailed statistical verification study has been conducted that employs analysis of variance (ANOVA) and the core sample analysis data collected since 1989. These data cover eight tanks and five SORWT groups. The verification study showed that these five SORWT groups are highly statistically significant; they represent approximately 10% of the total waste volume and 26% of the total sludge volume in SSTS. Future sampling recommendations based on the SORWT Model results include 32 core samples from 16 tanks and 18 auger samples from six tanks. Combining these data with the existing body of information will form the basis for characterizing 98 SSTs (66%). These 98 SSTs represent 78% of the total waste volume, 61% of the total sludge volume, and 88 % of the salt cake volume.
Date: February 1, 1995
Creator: Hill, J.G.; Anderson, G.S. & Simpson, B.C.
Partner: UNT Libraries Government Documents Department

Calculation notes that support accident scenario and consequence of the in-tank fuel fire/deflagration

Description: The purpose of this calculation note is to provide the basis for In-Tank Fuel Fire/Deflageration consequence for the Tank Farm Safety Analysis Report (FSAR). Tank Fuel Fire/Deflageration scenario is developed and details and description of the analysis methods are provided.
Date: September 27, 1996
Creator: Crowe, R.D.
Partner: UNT Libraries Government Documents Department

Single-shell tank system waste analysis plan

Description: The Single-Shell Tank (SST) system is a waste management unit within the Hanford Facility. The SST system is operating under interim status pending removal of the tank contents to the DST System and the closure of all SSTS. Storage is the principal function of the SST system and waste is no longer added to the tanks for storage. This document provides a single-shell tank system waste analysis plan.
Date: September 19, 1996
Creator: Mulkey, C.H.
Partner: UNT Libraries Government Documents Department

Calculation notes that support accident scenario and consequence determination of a waste tank criticality

Description: The purpose of this calculation note is to provide the basis for criticality consequences for the Tank Farm Safety Analysis Report (FSAR). Criticality scenario is developed and details and description of the analysis methods are provided.
Date: September 27, 1996
Creator: Crowe, R.D.
Partner: UNT Libraries Government Documents Department

High level waste storage tank farms/242-A evaporator standards/requirements identification document phase 1 assessment report

Description: This document, the Standards/Requirements Identification Document (S/RID) Phase I Assessment Report for the subject facility, represents the results of an Administrative Assessment to determine whether S/RID requirements are fully addressed by existing policies, plans or procedures. It contains; compliance status, remedial actions, and an implementing manuals report linking S/RID elements to requirement source to implementing manual and section.
Date: September 30, 1996
Creator: Biebesheimer, E., Westinghouse Hanford Co.
Partner: UNT Libraries Government Documents Department

Tank farm restoration and safe operation, project W-314, upgrade scope summary report

Description: This revision of the Project W-314 Upgrade Scope Summary Report (USSR) represents a refinement of the project scope and supporting justification from which the Conceptual Design Report (CDR) was developed. It defines the actual upgrades and provides traceability to the requirement or driver for the activity.
Date: January 8, 1997
Creator: Jacobson, R. W.
Partner: UNT Libraries Government Documents Department

FY 1996 Tank waste analysis plan

Description: This Tank Waste Analysis Plan (TWAP) describes the activities of the Tank Waste Remediation System (TWRS) Characterization Project to plan, schedule, obtain, and document characterization information on Hanford waste tanks. This information is required to meet several commitments of Programmatic End-Users and the Hanford Federal Facility Agreement and Consent Order, also known as the Tri-Party Agreement. This TWAP applies to the activities scheduled to be completed in fiscal year 1996.
Date: September 18, 1996
Creator: Homi, C. S.
Partner: UNT Libraries Government Documents Department

Analytical services Organization Union Valley sample Preparation facility Polychlorinated Biphenyl (PCB) Annual Inventory Document

Description: The Analytical Services Organization (ASO), Union Valley Sample Preparation Facility (UVSPF), provides analytical testing in support of the Department of Energy (DOE), Oak Ridge Operations (ORO), and associated sites. Samples generated on the Oak Ridge Reservation (ORR) are routinely received at the WSPF for analytical evaluatiotiidentification. Many of these samples are polychlorinated biphenyl (PCB) regulated from a source or being sent to the facility to determine PCB content. PCB laboratory wastes in solid and liquid form are generated during the evaluation of these materials, requiring the WSPF staff to maintain formal storage areas for staging the materials prior to off-site shipment for disposal. The purpose of this report is to fulfill the requirements set forth in Title 40, Code of Federal Regulations (CFR), Part 761.180(a), Subpart J, which requires owners or operators of a facility using or storing PCBS to prepare an annual inventory document by July 1 of the current year which covers the previous calendar year. This report provides documentation of the inventory of PCB materials/wastes that were generated, stored for dispos~ and shipped off site for disposal for the period January 1, 1997, to January 1, 1998. The following is a summary of materials/wastes subject to the aforementioned reporting requirements.
Date: June 1, 1998
Creator: Brown, B. J.
Partner: UNT Libraries Government Documents Department

Assessment groundwater monitoring plan for single shell tank waste management area B-BX-BY

Description: Single Shell Tank Waste Management Area B-BX-BY has been placed into groundwater quality assessment monitoring under interim-status regulations. This document presents background and an assessment groundwater monitoring plan to evaluate any impacts of risks/spills from these Single Shell Tanks in WMA B-BX-BY on groundwater quality.
Date: September 27, 1996
Creator: Caggiano, J.A.
Partner: UNT Libraries Government Documents Department

Tank characterization report for single-shell tank 241-T-102

Description: A major function of the Tank Waste Remediation System (TWRS) is to characterize wastes in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis, along with other available information about a tank, are compiled and maintained in a tank characterization report (TCR). This report and its appendixes serve as the TCR for single-shell tank 241-T-102. The objectives of this report are to use characterization data in response to technical issues associated with tank 241-T-102 waste; and to provide a standard characterization of this waste in terms of a best-basis inventory estimate. The response to technical issues is summarized in Section 2.0, and the best-basis inventory estimate is presented in Section 3.0. Recommendations regarding safety status and additional sampling needs are provided in Section 4.0. Supporting data and information are contained in the appendixes. This report supports the requirements of the Hanford Federal Facility Agreement and Consent Order milestone M-44-05. Characterization information presented in this report originated from sample analyses and known historical sources. The most recent core sampling of tank 241-T-102 (March 1993) predated the existence of data quality objectives (DQOs). An assessment of the technical issues from the currently applicable DQOs was made using data from the 1993 push mode core sampling event, a July 1994 grab sampling event, and a May 1996 vapor flammability measurement. Historical information for tank 241-T-102, provided in Appendix A, includes surveillance information, records pertaining to waste transfers and tank operations, and expected tank contents derived from a process knowledge model. Appendix B contains further sampling and analysis data from the March 1993 push mode core sampling event and data from the grab sampling event in August 1994 and May 1996 vapor flammability measurement. Of the two push mode cores taken in March of 1993, cores ...
Date: June 24, 1997
Creator: Baldwin, J.H.
Partner: UNT Libraries Government Documents Department

K Basins sludge removal temporary sludge storage tank system

Description: Shipment of sludge from the K Basins to a disposal site is now targeted for August 2000. The current path forward for sludge disposal is shipment to Tank AW-105 in the Tank Waste Remediation System (TWRS). Significant issues of the feasibility of this path exist primarily due to criticality concerns and the presence of polychlorinated biphenyls (PCBS) in the sludge at levels that trigger regulation under the Toxic Substance Control Act. Introduction of PCBs into the TWRS processes could potentially involve significant design and operational impacts to both the Spent Nuclear Fuel and TWRS projects if technical and regulatory issues related to PCB treatment cannot be satisfactorily resolved. Concerns of meeting the TWRS acceptance criteria have evolved such that new storage tanks for the K Basins sludge may be the best option for storage prior to vitrification of the sludge. A reconunendation for the final disposition of the sludge is scheduled for June 30, 1997. To support this decision process, this project was developed. This project provides a preconceptual design package including preconceptual designs and cost estimates for the temporary sludge storage tanks. Development of cost estimates for the design and construction of sludge storage systems is required to help evaluate a recommendation for the final disposition of the K Basin sludge.
Date: June 12, 1997
Creator: Mclean, M.A.
Partner: UNT Libraries Government Documents Department

Single-shell tank ventilation upgrades needs analysis report

Description: This report was written to comply with the objectives of the Hanford Federal Facility Agreement and Consent Order, Tri-Party Agreement Milestone M-43-03 Provide to the Washington State Department of Ecology and Department of Health the Results of the Single-Shell Tank Ventilation Upgrades Needs Analysis. The needs analysis consists of identifying the current type and status of each single-shell tank ventilation system, identifying current and projected authorization basis requirements, and identifying ventilation system compliance deficiencies.
Date: February 3, 1997
Creator: Kriskovich, J.R., Fluor Daniel Hanford
Partner: UNT Libraries Government Documents Department

High level waste storage tanks 242-A evaporator S/RID phase II assessment report

Description: This document, the Standards/Requirements Identification Document (S/RID) Phase 2 Assessment Report for the subject facility, represents the results of a Performance Assessment to determine whether procedures containing S/RID requirements are fully implemented by field personnel in the field. It contains a summary report and three attachments; an assessment schedule, performance objectives, and assessments for selected functional areas.
Date: September 27, 1996
Creator: Biebesheimer, E.
Partner: UNT Libraries Government Documents Department