3,029 Matching Results

Search Results

Advanced search parameters have been applied.

TRU relocation status report

Description: To meet an internal milestone, 257 containers identified as contact- handled transuranic waste are being relocated from uncovered drum modules in the Low-Level Burial Grounds into covered facilities. The project is not yet complete. This report discusses the project and its status as of December 31, 1996.
Date: January 20, 1997
Creator: Irwin, R.M.
Partner: UNT Libraries Government Documents Department

Tank farm nuclear criticality review

Description: The technical basis for the nuclear criticality safety of stored wastes at the Hanford Site Tank Farm Complex was reviewed by a team of senior technical personnel whose expertise covered all appropriate aspects of fissile materials chemistry and physics. The team concluded that the detailed and documented nucleonics-related studies underlying the waste tanks criticality safety basis were sound. The team concluded that, under current plutonium inventories and operating conditions, a nuclear criticality accident is incredible in any of the Hanford single-shell tanks (SST), double-shell tanks (DST), or double-contained receiver tanks (DCRTS) on the Hanford Site.
Date: September 11, 1996
Creator: Bratzel, D. R.
Partner: UNT Libraries Government Documents Department

Hanford tanks initiative alternatives generation and analysis plan for AX tank farm closure basis

Description: The purpose of this document is: (1) to review the HTI Mission Analysis and related documents to determine their suitability for use in developing performance measures for AX Tank Farm closure, (2) to determine the completeness and representativeness of selected alternative closure scenarios, (3) to determine the completeness of current plans for development of tank end-state criteria, and (4) to analyze the activities that are necessary and sufficient to recommend the end-state criteria and performance measures for the AX Tank Farm and recommend activities not currently planned to support establishment of its end-state criteria.
Date: October 22, 1997
Creator: Schaus, P.S., Westinghouse Hanford, Richland, WA
Partner: UNT Libraries Government Documents Department

Dependance of TWRS FSAR X/Qs on distance and example doses at Highway 240 with stationary and moving receptors

Description: A discussion of the reasons for the dependance of X/Q on receptor distance and compass sector is presented. In addition, X/Qs are calculated for three receptor scenarios on Highway 240 including a moving receptor. Example radiological doses and toxicological exposures at Highway 240 are calculated for two accidents already analyzed in the TWRS FSAR.
Date: September 23, 1996
Creator: Himes, D.A.
Partner: UNT Libraries Government Documents Department

Tank farms pump critical characteristic and specification guide

Description: The Design Authority group for Tank Farms, in conjunction with the Construction Projects organization, have recognized that there is a need to provide consistency in the procurement and testing of pumps and to assure that known critical attributes and features are included with each pump order as well as to reduce potential confusion by pump suppliers. As a result, a panel of pump experts representing Lockheed Martin Hanford Company (LMHC), Fluor Daniel Northwest (FDNW), Numatec Hanford Corporation (NHC), SGN Eurisys Services Corporation (SESC), and ARES Corporation has been assembled to prepare a guide for pump specifications. This document contains the consensus listing of critical characteristics and procurement recommendations of the panel. It is intended to be used as a guide for future pump procurement activities. If followed, it will help reduce cleanup costs at the Hanford Site and promote prompt approval of pumping system designs and procurement specifications. Alternate criteria may be specified on a case by case basis if deviation from the requirements contained herein is merited due to special circumstances.
Date: January 17, 1997
Creator: Titzler, P. A.
Partner: UNT Libraries Government Documents Department

Tank 241-T-110 tank characterization plan

Description: This Tank Characterization Plan (ICP) identifies the information needed to address issues related to short-term and long-term safe storage and long-term management of single shell tank 241-T-1,10 (T- 110). It should be understood that needs and issues surrounding tank T-110 are evolving as new information becomes available. As a result, this TCP addresses only issues that have been identified to date. It is expected that changes may be necessary as additional issues or needs arise which impact the management of tank T-110. As necessary, this TCP will be revised to reflect changes. This plan reflects the best information available as of August 1996. Tank T-110 entered into service in the first quarter of 1945. The tank began receiving second- cycle decontamination waste in the first quarter of 1945 (Agnew et al. 1995). The tank began to cascade overflow to Tank 241-T-111 in October 1945. In the second quarter of 1952, the tank began receiving 224 waste in addition to the second-cycle waste. The tank contained second-cycle and 224 waste until the first quarter of 1976. During the third quarter of 1974, the tank received waste water. The tank was removed from service in 1976. A level adjustment was made in April of 1982. The tank was primarily stabilized in 1978 and partially isolated in December 1982. The tank is classified as a sound, non-stabilized tank (Brevick et al. 1995). Tank T-110 currently contains a total volume of 14351789 kL. (379 kgal ) of waste, which is equivalent to 338.5 cm (133 in) of waste as measured from the baseline of the tank (Hanlon 1996). Tank T-110 is on the Flammable Gas Watch List. Near-term sampling and analysis activities are focused on verifying or changing the Watch List tank status, and identifying any new safety issues. If new safety issues are ...
Date: September 19, 1996
Creator: Mccain, D.J.
Partner: UNT Libraries Government Documents Department

Preliminary safety evaluation for the plutonium stabilization and packaging system

Description: This Preliminary Safety Evaluation (PSE) describes and analyzes the installation and operation of the Plutonium Stabilization and Packaging System (SPS) at the Plutonium Finishing Plant (PFP). The SPS is a combination of components required to expedite the safe and timely storage of Plutonium (Pu) oxide. The SPS program will receive site Pu packages, process the Pu for storage, package the Pu into metallic containers, and safely store the containers in a specially modified storage vault. The location of the SPS will be in the 2736- ZB building and the storage vaults will be in the 2736-Z building of the PFP, as shown in Figure 1-1. The SPS will produce storage canisters that are larger than those currently used for Pu storage at the PFP. Therefore, the existing storage areas within the PFP secure vaults will require modification. Other modifications will be performed on the 2736-ZB building complex to facilitate the installation and operation of the SPS.
Date: March 14, 1997
Creator: Shapley, J.E., Fluor Daniel Hanford
Partner: UNT Libraries Government Documents Department

General Heat Transfer Characterization and Empirical Models of Material Storage Temperatures for the Los Alamos Nuclear Materials Storage Facility

Description: The Los Alamos National Laboratory's Nuclear Materials Storage Facility (NMSF) is being renovated for long-term storage of canisters designed to hold heat-generating nuclear materials. A fully passive cooling scheme, relying on the transfer of heat by conduction, free convection, and radiation has been proposed as a reliable means of maintaining material at acceptable storage temperatures. The storage concept involves placing radioactive materials, with a net heat-generation rate of 10 W to 20 W, inside a set of nested steel canisters. The canisters are, in placed in holding fixtures and positioned vertically within a steel storage pipe. Several hundred drywells are arranged in a linear array within a large bay and dissipate the waste heat to the surrounding air, thus creating a buoyancy driven airflow pattern that draws cool air into the storage facility and exhausts heated air through an outlet stack. In this study, an experimental apparatus was designed to investigate the thermal characteristics of simulated nuclear materials placed inside two nested steel canisters positioned vertically on an aluminum fixture plate and placed inside a section of steel pipe. The heat-generating nuclear materials were simulated with a solid aluminum cylinder containing .an embedded electrical resistance heater. Calibrated type T thermocouples (accurate to ~ O.1 C) were used to monitor temperatures at 20 different locations within the apparatus. The purposes of this study were to observe the heat dissipation characteristics of the proposed `canister/fixture plate storage configuration, to investigate how the storage system responds to changes in various parameters, and to develop and validate empirical correlations to predict material temperatures under various operating conditions
Date: October 1, 1998
Creator: Bernardin, J. D. & Gregory, W. S.
Partner: UNT Libraries Government Documents Department

Record of Technical Change - Corrective Action Plan for Corrective Action Unit 204: Storage Bunkers, Nevada Test Site, Nevada, Revision 0

Description: Record of Technical Change, Technical Change No. CAP-1, dated April 13, 2005 for Corrective Action Plan for Corrective Action Unit 204: Storage Bunkers, Nevada Test Site, Nevada, Revision 0, September 2004, DOE/NV--1003.
Date: April 13, 2005
Creator: U.S. Department of Energy, National Nuclear Security Administration, Nevada Site Office
Partner: UNT Libraries Government Documents Department

Slant Borehole Demonstration Summary Report

Description: This report provides a summary of the demonstration project for development of a slant borehole to retrieve soil samples from beneath the SX-108 single-shell tank. It provides a summary of the findings from the demonstration activities and recommendations for tool selection and methods to deploy into the SX Tank Farm. Daily work activities were recorded on Drilling and Sampling Daily Work Record Reports. The work described in this document was performed during March and April 2000.
Date: July 19, 2000
Creator: GARDNER, M.G.
Partner: UNT Libraries Government Documents Department

Appendix D-21 Building 696S Consolidation Waste Accumulation Area

Description: This appendix is designed to provide information specific to the Building 696S Consolidation Waste Accumulation Area (B-696S CWAA), a waste storage area. The appendix is not designed to be used as a sole source of information. All general information that is not specific to the B-696S CWAA is included in the Contingency Plan for Waste Accumulation Areas, dated July 2004, and should be referenced.
Date: April 15, 2005
Creator: Michalik, R L
Partner: UNT Libraries Government Documents Department

Structural Integrity Program for INTEC Calcined Solids Storage Facilities

Description: This report documents the activities of the structural integrity program at the Idaho Nuclear Technology and Engineering Center relevant to the high-level waste Calcined Solids Storage Facilities and associated equipment, as required by DOE M 435.1-1, “Radioactive Waste Management Manual.” Based on the evaluation documented in this report, the Calcined Solids Storage Facilities are not leaking and are structurally sound for continued service. Recommendations are provided for continued monitoring of the Calcined Solids Storage Facilities.
Date: May 1, 2003
Creator: Bryant, Jeffrey Whealdon; Nenni, Joseph A & Yoder, Timothy S.
Partner: UNT Libraries Government Documents Department

Sloshing response of nonuniform density liquid in a laterally excited tank

Description: A study on the sloshing response of nonuniform density liquid in a tank undergoing lateral base excitations is presented. The system considered is a circular cylindrical tank containing a liquid whose density increases with the liquid depth. The density distribution along the depth can be of any arbitrary continuous function. In the analysis, the liquid field is divided into n layers. The thicknesses of the liquid layers can be different, but the density of each liquid layer is considered to be uniform and its value is assigned to be the value of the original liquid density at the mid-height of that layer. The problem is solved by the transfer matrix technique. The effect of the nonuniform liquid density on the sloshing response is illustrated in a numerical example in which the linear and cosine distributions of the liquid density are assumed. The response functions examined include the sloshing frequencies, surface wave height, and the associated convective hydrodynamic pressure. The results are presented in tabular and graphical forms. It is found that the natural frequencies of the sloshing motion for nonuniform density liquid are lower than those of the uniform density liquid of the same total depth contained in an identical tank. Also, it is shown that for nonuniform density liquid, the maximum sloshing wave height may increase significantly and the magnitude of the convective hydrodynamic pressure may be quite different compared with that of a uniform liquid contained in an identical tank.
Date: January 1, 1995
Creator: Tang, Y.
Partner: UNT Libraries Government Documents Department

Rocking response of tanks containing two liquids

Description: A study on the dynamic response of upright circular cylindrical liquid-storage tanks containing two different liquids under a rocking base motion with an arbitrary temporal variation is presented. Only rigid tanks were studied. The response quantities examined include the hydrodynamic pressure, sloshing wave height and the associated frequencies, base shear and moments. Each of these response quantities is expressed as the sum of the so-called impulsive component and convective component. Unlike the case of tanks containing one liquid, in which the response is controlled by one parameter, height-to-radius ratio, the response of tanks containing two different liquids are controlled by three parameters: height-to-radius ratio, and mass density ratio and height ratio of the two liquids. The interrelationship of the responses of the tank-liquid system to rocking and lateral base excitations is established by examining numerical results extensively. The study shows that some of the response quantities for tank-liquid system under a rocking base motion can be determined from the available data for the response of an identical tank under a horizontal base motion. Base rocking motion can occur in a ground-supported tank or in an elevated tank under earthquake motions.
Date: January 1, 1995
Creator: Tang, Y.
Partner: UNT Libraries Government Documents Department

MCO Monitoring activity description

Description: Spent Nuclear Fuel remaining from Hanford's N-Reactor operations in the 1970s has been stored under water in the K-Reactor Basins. This fuel will be repackaged, dried and stored in a new facility in the 200E Area. The safety basis for this process of retrieval, drying, and interim storage of the spent fuel has been established. The monitoring of MCOS in dry storage is a currently identified issue in the SNF Project. This plan outlines the key elements of the proposed monitoring activity. Other fuel stored in the K-Reactor Basins, including SPR fuel, will have other monitoring considerations and is not addressed by this activity description.
Date: November 9, 1998
Creator: SEXTON, R.A.
Partner: UNT Libraries Government Documents Department

Tank 241-Z-361 process and characterization history

Description: An Unreviewed Safety Question (Wagoner, 1997) was declared based on lack of adequate authorization basis for Tank 241-Z-361 in the 200W Area at Hanford. This document is a summary of the history of Tank 241-Z-361 through December 1997. Documents reviewed include engineering files, laboratory notebooks from characterization efforts, waste facility process procedures, supporting documents and interviews of people`s recollections of over twenty years ago. Records of transfers into the tank, past characterization efforts, and speculation were used to estimate the current condition of Tank 241-Z-361 and its contents. Information about the overall waste system as related to the settling tank was included to help in understanding the numbering system and process relationships. The Plutonium Finishing Plant was built in 1948 and began processing plutonium in mid-1949. The Incinerator (232-Z) operated from December 1961 until May 1973. The Plutonium Reclamation Facility (PRF, 236-Z) began operation in May 1964. The Waste Treatment Facility (242-Z) operated from August 1964 until August 1976. Waste from some processes went through transfer lines to 241-Z sump tanks. High salt and organic waste under normal operation were sent to Z-9 or Z-18 cribs. Water from the retention basin may have also passed through this tank. The transfer lines to 241-Z were numbered D-4 to D-6. The 241-Z sump tanks were numbered D-4 through D-8. The D-4, 5, and 8 drains went to the D-6 sump tank. When D-6 tank was full it was transferred to D-7 tank. Prior to transfer to cribs, the D-7 tank contents was sampled. If the plutonium content was analyzed to be more than 10 g per batch, the material was (generally) reprocessed. Below the discard limit, caustic was added and the material was sent to the cribs via the 241-Z-361 settling tank where solids settled out and the liquid overflowed by gravity ...
Date: August 6, 1998
Creator: Jones, S.A.
Partner: UNT Libraries Government Documents Department