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Structural analysis of hatch cover plates on FMEF high bay mezzanine

Description: In order to move the Idaho National Engineering Laboratory (INEL) Light Duty Utility Arm (LDUA) trailer into position for testing on the Fuels and Materials Examination Facility (FMEF) 42 ft level mezzanine one of the trailer`s wheels will have to sit on a circular hatch cover fabricated from one-inch thick steel plate. The attached calculations verify that the hatch cover plate is strong enough to support the weight of the INEL LDUA trailer`s wheel.
Date: May 29, 1997
Creator: Dixson, G. E.
Partner: UNT Libraries Government Documents Department
open access

Evaluation of copper for divider subassembly in MCO Mark IA and Mark IV scrap fuel baskets

Description: The K Basin Spent Nuclear Fuel (SNF) Project Multi-Canister Overpack (MCO) subprojection eludes the design and fabrication of a canister that will be used to confine, contain, and maintain fuel in a critically safe array to enable its removal from the K Basins, vacuum drying, transport, staging, hot conditioning, and interim storage (Goldinann 1997). Each MCO consists of a shell, shield plug, fuel baskets (Mark IA or Mark IV), and other incidental equipment. The Mark IA intact and scrap fuel ba… more
Date: September 29, 1997
Creator: Graves, C. E.
Partner: UNT Libraries Government Documents Department
open access

Radioactive air emissions notice of construction fuel removal for 105-KW Basin

Description: This document serves as a Notice of Construction (NOC), pursuant to the requirements of Washington Administrative Code (WAC) 246-247-060, and as a request for approval to construct, pursuant to 40 Code of Federal Regulations (CFR) 61.96, for the modifications, installation of new equipment, and fuel removal and sludge relocation activities at 105-KW Basin. The purpose of the activities described in this NOC is to enable the eventual retrieval and transport of the fuel for processing. The fuel r… more
Date: May 29, 1997
Creator: Hays, C. B.
Partner: UNT Libraries Government Documents Department
open access

The 324 building radiochemical engineering scales and high-level vault closure plan

Description: This closure plan incorporates the requirements and decisions made during a Data Quality Objectives process held in 1996 by the State of Washington Department of Ecology, US Department of Energy Richland Operations Office, and contractors associated with closure of the 324 Building.
Date: May 29, 1997
Creator: Prignano, A. L.
Partner: UNT Libraries Government Documents Department
open access

Control Dewar and VLPC Bayonet Can Platform Connection Design and Analysis

Description: The four connections for the control dewar and VLPC bayonet can platform are designed, using finite element analysis, to carry all dead weight and live loads. Based on the loads applied to the platform, two 1 inch thick plates and two 3/4 inch thick brackets made of ASTM A572-Grade 42 are required. The 1 inch thick plate requires a 3/8 inch thick intermediate steel material, between the 8-inch x 4-inch x 1/4-inch boom and the plate, for load reinforcement as well as weld area reinforcement. Bot… more
Date: July 29, 1997
Creator: Kuwazaki, A.
Partner: UNT Libraries Government Documents Department
open access

TRANSPORT AND EMPLACEMENT EQUIPMENT DESCRIPTIONS

Description: The objective and the scope of this document are to list and briefly describe the major mobile equipment necessary for waste package (WP) Transport and Emplacement in the proposed subsurface nuclear waste repository at Yucca Mountain. Primary performance characteristics and some specialized design features of the equipment are explained and summarized in the individual subsections of this document. The Transport and Emplacement equipment described in this document consists of the following: (1)… more
Date: September 29, 1997
Creator: NA
Partner: UNT Libraries Government Documents Department
open access

Quarterly Technical Progress Report

Description: Methane oxidative coupling experiments were conducted in a porous gamma alumina membrane reactor using Mn-W-Na/SiOz catalyst, and its performance was compared with a packed reactor. By varying the helium flow rate and keeping the temperature, methane flow rate, and oxygen flow rate constant, the membrane reactor gave 10% higher Cz yield and 30% higher C2 selectivity than the co-feed reactor operated at the same methane conversion. At similar C2 yield and C2 selectivity, the methane conversion o… more
Date: August 29, 1997
Creator: Ma, Yi Hua
Partner: UNT Libraries Government Documents Department
open access

Reactivation of an Idle Lease to Increase Heavy Oil Recovery Through Application of Conventional Steam Drive Technology in a Low Dip Slope and Basin Reservoir in the Midway-Sunset Field, San Jaoquin Basin, California

Description: This project reactivates ARCO�s idle Pru Fee property in the Midway-Sunset field, California and conducts a continuous steamflood enhanced oil recovery demonstration aided by an integration of modern reservoir characterization and simulation methods. Cyclic steaming was used to reestablish baseline production within the reservoir characterization phase of the project. During the demonstration phase begun in January 1997, a continuous steamflood enhanced oil recovery was initiated to test the in… more
Date: July 29, 1997
Creator: Schamel, Steven
Partner: UNT Libraries Government Documents Department
open access

Combinatorial methods for gene recognition

Description: The major result of the project is the development of a new approach to gene recognition called spliced alignment algorithm. They have developed an algorithm and implemented a software tool (for both IBM PC and UNIX platforms) which explores all possible exon assemblies in polynomial time and finds the multi-exon structure with the best fit to a related protein. Unlike other existing methods, the algorithm successfully performs exons assemblies even in the case of short exons or exons with unus… more
Date: October 29, 1997
Creator: Pevzner, Pavel A.
Partner: UNT Libraries Government Documents Department
open access

Kenya: The Challenges Ahead

Description: No Description Available.
Date: July 29, 1997
Partner: UNT Libraries Government Documents Department
open access

SVX Sequence Crate Custom J1 Backplane

Description: The Custom J1 Backplane is a full length (21 slot) user specified custom 3U backplane to be used in the J1 position. Slot spacing is identical to that used for VME (0.8-inch), and each backplane shall fit into a standard Eurocard VME style crate. The purpose of the Custom J1 Backplane is to: (1) Provide +5 volt power to slots 1 through 21; (2) Provide -5.2 volt power to slots 1 through 21; (3) Provide five bits of geographic addressing to slots 2 through 21. Slot 2 will have all five bits pulle… more
Date: October 29, 1997
Creator: Utes, M.
Partner: UNT Libraries Government Documents Department
open access

DOSE RATES FOR WESTINGHOUSE 17X17 MOX PWR SNF IN A WASTE PACKAGE (SCPB: N/A)

Description: This analysis is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development Department (WPDD) to estimate the dose rate on and near the surface a Multi-Purpose Canister (MPC) PWR waste package (WP) which is loaded with Westinghouse 17 x 17 mixed oxide (MOX) PWR fuel. The 21 PWR MPC WP is used to provide an upper bound for waste package designs since the 12 PWR MPC WP will have a smaller source term and an equivalent amount of shielding. the objectives of this evaluation are… more
Date: January 29, 1997
Creator: Lotz, T.L.
Partner: UNT Libraries Government Documents Department
open access

CRC DEPLETION CALCULATIONS FOR THE NON-RODDED ASSEMBLIES IN BATCHES 1, 2, AND 3 OF CRYSTAL RIVER UNIT 3

Description: The purpose of this design analysis is to document the SAS2H depletion calculations of certain non-rodded fuel assemblies from batches 1, 2, and 3 of the Crystal River Unit 3 pressurized water reactor (PWR) that are required for Commercial Reactor Critical (CRC) evaluations to support development of the disposal criticality methodology. A non-rodded assembly is one which never contains a control rod assembly (CRA) or an axial power shaping rod assembly (APSRA) during its irradiation history. Th… more
Date: July 29, 1997
Creator: Wright, Kenneth D.
Partner: UNT Libraries Government Documents Department
open access

Dolphin Protection and Tuna Seining

Description: From its inception in 1972, one of the goals of the Marine Mammal Protection Act (MMPA) was to reduce the incidental mortality of dolphins in the ETP tuna fishery. Regulations promulgated under MMPA authority set standards for tuna seining and motivated technological improvements that reduced dolphin mortalities in this fishery -- by 1977, annual dolphin mortality by U.S. tuna seiners had declined to about 25,450 animals. Despite the extensive mortalities, no ETP dolphin population has been lis… more
Date: August 29, 1997
Creator: Buck, Eugene H.
Partner: UNT Libraries Government Documents Department
open access

Development of Precipitated Iron Fischer-Tropsch Catalysts.

Description: Four (alumina or silica) supported catalysts with nominal compositions (on mass basis) of synthesized catalysts are: (1) 100 Fe/5 Cu/6 K/139 SiO{sub 2} (2) 100 Fe/10 Cu/6 K/134 SiO{sub 2}, (3) 100 Fe/5 Cu/ K/139 Al{sub 2}0{sub 3} and (4) 100 Fe/10 Cu/6 K/134 Al{sub 2}0{sub 3} were char BET surface area measurements. The surface areas of all four catalysts are between 94 and 136 m{sup 2}/g, whereas the surface areas of alumina and silica support are 213 and 252 m{sup 2}/g, respectively. The decr… more
Date: August 29, 1997
Creator: Bukur, D. B.; Ding, Y. & Chokkaram, S.
Partner: UNT Libraries Government Documents Department
open access

Task completion report for update FXTPTM

Description: Knolls Atomic Power Laboratory reported that the trip-initiated, problem-termination feature was not functioning in TRAC-P, Version 5.4.15. A listing of the modified input data for the DRAIN standard test problem and the TRCMSG file output was provided that demonstrated that the TRAC-P calculation did not terminate when the problem-termination designated trip`s set status was set to ON{sub forward}. The assigned task was to investigate and correct this nonfunctioning feature in TRAC-P, Version … more
Date: August 29, 1997
Creator: Steinke, R.G.
Partner: UNT Libraries Government Documents Department
open access

Evaluation of nitrate and nitrite destruction/separation technologies

Description: This report describes and evaluates four types of nitrate and nitrite destruction and separation technologies that could be used to treat the aqueous, alkaline, nitrate-bearing mixed waste that is generated by the In-Tank Precipitation (ITP) process at the Savannah River Site (SRS). The technologies considered in this report include thermal, hydrothermal, chemical, and electrochemical technologies.
Date: August 29, 1997
Creator: Hobbs, D. T.
Partner: UNT Libraries Government Documents Department
open access

3-D vertical seismic profiling at LLNL Site 300

Description: The initial goal of the 3-D Vertical Seismic Profiling (VSP) work at LLNL was to characterize seismic wave velocities and frequencies below the vadose zone to design the acquisition geometry for a 3-D shallow surface seismic reflection survey. VSPs are also used routinely to provide a link between surface seismic data and well logs. However, a test 2-D seismic line recorded at LLNL in the Spring of 1994 indicated that obtaining high quality reflection images below the vadose zone, yet shallower… more
Date: January 29, 1997
Creator: Bainer, R.; Rector, J. & Milligan, P.
Partner: UNT Libraries Government Documents Department
open access

Activity of fuel batches processed through Hanford separations plants, 1944 through 1989

Description: This document provides a printout of the ``Fuel Activity Database`` (version U6) generated by the Hanford DKPRO code and transmitted to the Los Alamos National Laboratory for input to their ``Hanford Defined Waste`` model of waste tank inventories. This fuel activity file consists of 1,276 records--each record representing the activity associated with a batch of spent reactor fuel processed by month (or shorter period) through individual Hanford separations plants between 1944 and 1989. Each re… more
Date: July 29, 1997
Creator: Watrous, R. A. & Wootan, D. W.
Partner: UNT Libraries Government Documents Department
open access

Pressure fluctuations as a diagnostic tool for fluidized beds. Technical progress report, October 1, 1996--December 31, 1996

Description: The viability of matching hydrodynamic conditions in a hot bubbling fluidized bed (BFB) combustor and a cold BFB model are being evaluated. Similitude parameters are being matched in a 20.32 cm diameter BFB combustor and a 5.08 cm diameter cold BFB. In addition, tests are planned to investigate the effect loaded solids above the L-valve have on the flow rate.
Date: January 29, 1997
Creator: Brown, R.C. & Schroeder, J.R.
Partner: UNT Libraries Government Documents Department
open access

Flammable gas project: Criteria for flammable gas watch list tanks

Description: 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 high4e… more
Date: January 29, 1997
Creator: Cash, R.J.
Partner: UNT Libraries Government Documents Department
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