Flammable gas project: Criteria for flammable gas watch list tanks (open access)

Flammable gas project: Criteria for flammable gas watch list tanks

The Flammable Gas Watch List is the listing of tanks that are subject to the provisions of Public Law 101-510, Section 3137, ``Safety Measures for Waste Tanks at Hanford Nuclear Reservation`` (Appendix A). Tanks on the Flammable Gas Watch List are judged to have a serious potential for release of high-level waste due to the ignition of flammable gases released from the waste in the tank. The purpose of this document is to provide criteria for identifying and categorizing the Hanford Site high4evel waste tanks to be included on the Flammable Gas Watch List. This document also provides criteria on which to base a recommendation to remove tanks from the Flammable Gas Watch List.
Date: January 29, 1997
Creator: Cash, R.J.
Object Type: Report
System: The UNT Digital Library
Preliminary tank characterization report for single-shell tank 241-BX-111: best-basis inventory (open access)

Preliminary tank characterization report for single-shell tank 241-BX-111: best-basis inventory

An effort is underway to provide waste inventory estimates that will serve as standard characterization source terms for the various waste management activities. As part of this effort, an evaluation of available information for single-shell tank 241-BX-111 was performed, and a best-basis inventory was established. This work follows the methodology that was established by the standard inventory task.
Date: August 29, 1997
Creator: Kupfer, M. J.
Object Type: Report
System: The UNT Digital Library
Project W-314 sn-634 transfer line a-b to ax-b acceptance for beneficial use (open access)

Project W-314 sn-634 transfer line a-b to ax-b acceptance for beneficial use

Program/Project Title: Project W-314, Tank Farm Restoration and Safe Operation, Phase I Component/System: SN-630 Transfer Line (AZ-02A to AN-B) September 15, 1997.
Date: September 29, 1997
Creator: Warnick, T.L., Westinghouse Hanford, Richland, WA
Object Type: Report
System: The UNT Digital Library
Waste management project fiscal year 1998 multi-year work plan WBS 1.2 (open access)

Waste management project fiscal year 1998 multi-year work plan WBS 1.2

The MYWP technical baseline describes the work to be accomplished by the Project and the technical standards which govern that work. The Waste Management Project manages and integrates (non-TWRS) waste management activities at the site. Activities include management of Hanford wastes as well as waste transferred to Hanford from other DOE, Department of Defense, or other facilities. This work includes handling, treatment, storage, and disposition of radioactive, nonradioactive, hazardous, and mixed solid and liquid wastes. Major Waste Management Projects are the Solid Waste Project (SW), Liquid Effluents Project (LEP), and Analytical Services. Existing facilities (e.g., grout vaults and canyons) shall be evaluated for reuse for these purposes to the maximum extent possible. The paper tabulates the major facilities that interface with this Project, identifying the major facilities that generate waste, materials, or infrastructure for this Project and the major facilities that will receive waste and materials from this Project.
Date: August 29, 1997
Creator: Slaybaugh, R.R.
Object Type: Report
System: The UNT Digital Library
Advanced sluicing system test report for single shell tank waste retrieval integrated testing (open access)

Advanced sluicing system test report for single shell tank waste retrieval integrated testing

This document describes the testing performed by ARD Environmental, Inc., and Los Alamos Technical Associates of the LATA/ARD Advanced Sluicing System, in support of ACTR Phase 1 activities. Testing was to measure the impact force and pressures of sluicing streams at three different distances, as measured by the Government supplied load cell. Simulated sluicing of large simulated salt cake and hard pan waste coupons was also performed. Due to operational difficulties experienced with the Government supplied load cell, no meaningful results with respect to sluice stream impact pressure distribution or stream coherence were obtained. Sluice testing using 3000 psi salt cake simulants measured waste retrieval rates of approximately 12 Ml/day (17.6 ft{sup 3}/hr). Rates as high as 314 m{sup 3}/day (463 ft{sup 3}/hr) were measured against the lower strength salt cake simulants.
Date: May 29, 1997
Creator: Berglin, E.J.
Object Type: Report
System: The UNT Digital Library
Preoperational test report, raw water system (open access)

Preoperational test report, raw water system

This represents the preoperational test report for the Raw Water System, Project W-030. Project W-030 provides a ventilation upgrade for the four Aging Waste Facility tanks. The system supplies makeup water to the W-030 recirculation evaporative cooling towers for tanks AY1O1, AY102, AZ1O1, AZ102. The Raw Water pipe riser and associated strainer and valving is located in the W-030 diesel generator building. The tests verify correct system operation and correct indications displayed by the central Monitor and Control System.
Date: October 29, 1997
Creator: Clifton, F.T.
Object Type: Report
System: The UNT Digital Library
Pseudomoment fluid modeling: ion-acoustic landau damping and non-equilibrium temperature (open access)

Pseudomoment fluid modeling: ion-acoustic landau damping and non-equilibrium temperature

This paper introduces a hierarchy of electron pseudomoment fluid equations that is used to derive electron Landau damping of ion acoustic waves.
Date: May 29, 1997
Creator: Amendt, P.
Object Type: Article
System: The UNT Digital Library
Design requirements document for the phase 1 privatization electrical power system (open access)

Design requirements document for the phase 1 privatization electrical power system

The electrical system for the Phase 1 privatization facilities will support the TWRS mission by providing the electrical power to the Phase 1 privatized facilities. This system will receive power from the Department of Energy-Richland Operations (RL) A4-8 230 kV transmission system powered from Bonneville Power Administration (BPA) Ashe and Midway 230 kV Substations. The existing RL 230 kV transmission line will be modified and looped 1021 into the new 230 kV substation bus. The new substation will be located in the vicinity of the privatized facilities, approximately 3.2 km (2 mi) south of the existing RL A4-8 230 kV transmission line. The substation will be capable of providing up to 40 MW of electrical power to support the Phase 1 privatization facilities and has space for accommodating future expansions. The substation will require at least two 230-13.8 kV transformers, 13.8 kV split bus switchgear, switchgear building, grounding transformers, instrument transformers, control and monitoring equipment, associated protection and isolation devices, lightning protection, yard lighting, cable and raceways, and infrastructure needed to provide desired availability and reliability. The power from the 13.8 kV switchgear located in the switchgear building will be delivered at the privatization facilities site boundaries. The 13.8 kV …
Date: October 29, 1997
Creator: Singh, G.
Object Type: Report
System: The UNT Digital Library
Tank characterization report for double-shell tank 241-AW-102 (open access)

Tank characterization report for double-shell tank 241-AW-102

This document summarizes the information on the historical uses, present status, and the sampling and analysis results of waste stored in Tank 241-AW-102. This report supports the requirements of the Tri-Party Agreement Milestone M-44-05.
Date: May 29, 1997
Creator: Bell, K. E.
Object Type: Report
System: The UNT Digital Library
Task completion report for update SUMNMULN (open access)

Task completion report for update SUMNMULN

New ``Sum N`` and ``Multiply N`` control blocks have been programmed by update SUMNMULN in TRAC-P Version 5.4.28. They define N signal variables and/or control blocks whose values are to be summed with optional weighting factors or multiplied, respectively.
Date: August 29, 1997
Creator: Steinke, R.G.
Object Type: Report
System: The UNT Digital Library
On a class of nonlinear dispersive-dissipative interactions (open access)

On a class of nonlinear dispersive-dissipative interactions

The authors study the prototypical, genuinely nonlinear, equation; u{sub t} + a(u{sup m}){sub x} + (u{sup n}){sub xxx} = {mu}(u{sup k}){sub xx}, a, {mu} = consts., which encompasses a wide variety of dissipative-dispersive interactions. The parametric surface k = (m + n)/2 separates diffusion dominated from dissipation dominated phenomena. On this surface dissipative and dispersive effects are in detailed balance for all amplitudes. In particular, the m = n + 2 = k + 1 subclass can be transformed into a form free of convection and dissipation making it accessible to theoretical studies. Both bounded and unbounded oscillations are found and certain exact solutions are presented. When a = (2{mu}3/){sup 2} the map yields a linear equation; rational, periodic and aperiodic solutions are constructed.
Date: July 29, 1997
Creator: Rosenau, P.
Object Type: Article
System: The UNT Digital Library
Two examples of the impact of partitioning with Chaco and Metis on the convergence of additive Schwarz-preconditioned FGMRES (open access)

Two examples of the impact of partitioning with Chaco and Metis on the convergence of additive Schwarz-preconditioned FGMRES

Algebraic graph partitioning packages that require no geometric or physical information are often used to partition sparse linear systems for solution on parallel computers using Krylov-space iterative methods with domain decomposition-type preconditioning methods. The authors show through a couple of examples that this can have a substantial impact on the convergence of the iterative methods.
Date: September 29, 1997
Creator: DeLong, M.
Object Type: Report
System: The UNT Digital Library
Corrosion resistance of inconel 690 to sodium carbonate, calcium carbonate, and sodium meta silicate at 900 and 1100{degrees}C (open access)

Corrosion resistance of inconel 690 to sodium carbonate, calcium carbonate, and sodium meta silicate at 900 and 1100{degrees}C

Corrosive attack of Inconel 690 coupons was not observed following 3 day exposure tests to calcium carbonate, sodium carbonate, and sodium meta silicate at 900 {degrees}C. However, melt line attack was evident on coupons exposed to sodium meta silicate and sodium carbonate tested for 3 days at 1100 {degrees}C. In addition, intergranular attack (IGA), approximately 0.67 mils/day, was observed on the Inconel 690 coupon exposed to calcium carbonate at 1100 {degrees}C. Calcium carbonate did not completely remove the glass coating at 950 {degrees}C. In fact, it was comparable to the results obtained by exposing a glass coated coupon at 950 {degrees}C in air. Therefore, calcium carbonate is not recommended for cleaning the DWPF melter pour spout. Both sodium carbonate and sodium meta silicate appear to remove most of the glass. However, these cleaning agents will remain on the metal surface following exposure at 950 {degrees}C resulting in very rough surface and a potential for corrosive attack when heated to 1100 {degrees}C.
Date: January 29, 1997
Creator: Imrich, K. J.
Object Type: Report
System: The UNT Digital Library
Task completion report for update FXTIME (open access)

Task completion report for update FXTIME

The DSTEP = {minus}99 and TIMET {ge} 0.0 s feature in TRAC-P has been tested on the W4LOOP and W4LOOPR standard test problems and was found to give different W4LOOPR solutions for different values of TIMET when all these cases should have given the same solution. Update FXTIME has corrected part of the cause of that difference and reduced the difference by an order of magnitude. The error associated with the remaining difference has been documented in Trouble Report 238.
Date: August 29, 1997
Creator: Steinke, R.G.
Object Type: Report
System: The UNT Digital Library
Project W-314 az-02a pump pit upgrade acceptance for beneficial use (open access)

Project W-314 az-02a pump pit upgrade acceptance for beneficial use

Project W-314 az-02a pump pit upgrade acceptance for beneficial use.
Date: September 29, 1997
Creator: Warnick, T.L., Westinghouse Hanford, Richland, WA
Object Type: Report
System: The UNT Digital Library
Project W-314 AN-B valve pit upgrade acceptance for beneficial use (open access)

Project W-314 AN-B valve pit upgrade acceptance for beneficial use

None
Date: September 29, 1997
Creator: Warnick, T.L., Westinghouse Hanford, Richland, WA
Object Type: Report
System: The UNT Digital Library
SNAKES manipulator and ARD sluicer testing -- April 1997 (open access)

SNAKES manipulator and ARD sluicer testing -- April 1997

Long reach arms represent one of the options available for deployment of end effectors which can be used in the retrieval of radioactive waste, from the Hanford single shell tanks. The versatility of an arm based deployment system is such that it has the potential to improve the performance of a wide range of end effectors compared with stand-alone or other deployment methods. The long term reliability and availability of the deployment system is central to the timely completion of a waste retrieval program. However, concerns have been expressed over the dynamic performance of long reach arms and it is essential that an arm based system can cope with operational dynamic loads generated by end effectors. The test program conducted set out to measure static and dynamic loads and responses from a representative arm and sluicer, with the objective of extrapolating the data to a long reach arm system, that can be used for in-tank waste retrieval. As an arm with an appropriate reach was not available, the test program was undertaken to measure dynamic characteristics of a Magnox Electric 18 ft multi-link, hydraulically actuated SNAKES manipulator. This is the longest reach unit in service, albeit only one third of …
Date: May 29, 1997
Creator: Berglin, E.J.
Object Type: Report
System: The UNT Digital Library
Tank characterization report for single-shell tank 241-B-109 (open access)

Tank characterization report for single-shell tank 241-B-109

This document summarizes the information on the historical uses, present status, and the sampling and analysis results of waste stored in Tank 241-B-109. This tank has been listed on the Organic Salts Watch List. This-report supports the requirements of the Tri-Party Agreement Milestone M 44-10.
Date: May 29, 1997
Creator: Benar, C.J.
Object Type: Report
System: The UNT Digital Library
Preoperational test report, primary ventilation condenser cooling system (open access)

Preoperational test report, primary ventilation condenser cooling system

This represents the preoperational test report for the Primary Ventilation Condenser Cooling System, Project W-030. Project W-030 provides a ventilation upgrade for the four Aging Waste Facility tanks. The system uses a closed chilled water piping loop to provide offgas effluent cooling for tanks AY101, AY102, AZ1O1, AZ102; the offgas is cooled from a nominal 100 F to 40 F. Resulting condensation removes tritiated vapor from the exhaust stack stream. The piping system includes a package outdoor air-cooled water chiller with parallel redundant circulating pumps; the condenser coil is located inside a shielded ventilation equipment cell. The tests verify correct system operation and correct indications displayed by the central Monitor and Control System.
Date: October 29, 1997
Creator: Clifton, F.T.
Object Type: Report
System: The UNT Digital Library
Project W-314 241-AN-A valve pit upgrade acceptance for beneficial use (open access)

Project W-314 241-AN-A valve pit upgrade acceptance for beneficial use

This report consists of 11 tables.
Date: August 29, 1997
Creator: Warnick, T.L.
Object Type: Report
System: The UNT Digital Library
Preliminary tank characterization report for single-shell tank 241-SX-105: Best-basis inventory (open access)

Preliminary tank characterization report for single-shell tank 241-SX-105: Best-basis inventory

An effort is underway to provide waste inventory estimates that will serve as standard characterization source terms for the various waste management activities. As part of this effort, an evaluation of available information for single-shell tank 241-SX-105 was performed, and a best-basis inventory was established. This work follows the methodology that was established by the standard inventory task.
Date: August 29, 1997
Creator: Kupfer, M.J.
Object Type: Report
System: The UNT Digital Library
Preliminary tank characterization report for single-shell tank 241-SX-112: Best-basis inventory (open access)

Preliminary tank characterization report for single-shell tank 241-SX-112: Best-basis inventory

An effort is underway to provide waste inventory estimates that will serve as standard characterization source terms for the various waste management activities. As part of this effort, an evaluation of available information for single-shell tank 241-SX-112 was performed, and a best-basis, inventory was established. This work follows the methodology that was established by the standard inventory task.
Date: August 29, 1997
Creator: Kupfer, M.J.
Object Type: Report
System: The UNT Digital Library
Preliminary tank characterization report for single-shell tank 241-SX-111: Best-basis inventory (open access)

Preliminary tank characterization report for single-shell tank 241-SX-111: Best-basis inventory

An effort is underway to provide waste inventory estimates that will serve as standard characterization source terms for the various waste management activities. As part of this effort,.an evaluation of available information for single-shell tank 241-SX-111 was performed, and a best-basis inventory was established. This work follows the methodology that was established by the standard inventory task.
Date: August 29, 1997
Creator: Kupfer, M.J.
Object Type: Report
System: The UNT Digital Library
Scoping assessment on medical isotope production at the Fast Flux Test Facility (open access)

Scoping assessment on medical isotope production at the Fast Flux Test Facility

The Scoping Assessment addresses the need for medical isotope production and the capability of the Fast Flux Test Facility to provide such isotopes. Included in the discussion are types of isotopes used in radiopharmaceuticals, which types of cancers are targets, and in what way isotopes provide treatment and/or pain relief for patients.
Date: August 29, 1997
Creator: Scott, S.W.
Object Type: Report
System: The UNT Digital Library