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.

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 baskets are a safety class item for criticality control and components necessary for criticality control will be constructed from 304L stainless steel. It is proposed that a copper divider subassembly be used in both Mark IA and Mark IV scrap baskets to increase the safety basis margin during cold vacuum drying. The use of copper would increase the heat conducted away from hot areas in the baskets out to the wall of the MCO by both radiative and conductive heat transfer means. Thus copper subassembly will likely be a safety significant component of the scrap fuel baskets. This report examines the structural, cost and corrosion consequences associated with using a copper subassembly in the stainless steel MCO scrap fuel baskets.

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 retrieval and transport will require an integrated water treatment system for which performance specifications have been developed. These specifications are currently in the procurement process. Following procurement (and before installation of this system and the handling of fuel) design details will be provided to Washington State Department of Health (WDOH). The 105-K West Reactor (105-KW) and its associated spent nuclear fuel (SNF) storage basin were constructed in the early 1950s and are located on the Hanford Site in the 100-K Area about 1,400 feet from the Columbia River. The 105-KW Basin contains 964 Metric Tons of SNF stored under water in approximately 3,800 closed canisters. This SNF has been stored for varying periods of time ranging from 8 to 17 years. The 105-KW …

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.

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. Both the plates and the brackets require 3/4 inch steel bolt connections.

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) WP Transporter; (2) Reusable Rail Car; (3) Emplacement Gantry; (4) Gantry Carrier; and (5) Transport Locomotive.

We propose a new approach for deriving the string field equations from a general sigma model on the world-sheet. This approach leads to an equation which combines some of the attractive features of both the renormalization group method and the covariant beta function treatment of the massless excitations. It has the advantage of being covariant under a very general set of both local and non-local transformations in the field space. We apply it to the tachyon, massless and first massive level, and show that the resulting field equations reproduce the correct spectrum of a left-right symmetric closed bosonic string.

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 of the membrane reactor was 15% lower than that of a co-feed reactor. By varying the oxygen flow rate and keeping the temperature, methane flow rate, and helium flow rate constant, at the same methane conversion, the membrane reactor gave about 3% higher C2 yield and C2 selectivity than the co-feed reactor. Higher helium flow rate gave higher C2 selectivity and yield, whereas changing methane flow rate did not significantly affect the reactor performance.

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 incremental value of this method as an alternative to cyclic steaming. Other economically marginal Class III reservoirs having similar producibility problems will benefit from insight gained in this project. The objectives of the project are: (1) to return the shut-in portion of the reservoir to optimal commercial production; (2) to accurately describe the reservoir and the recovery process; and (3) to convey the details of this activity to the domestic petroleum industry, especially to other producers in California, through an aggressive technology transfer program.

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 unusual codon usage; they also report correct assemblies for the genes with more than 10 exons provided a homologous protein is already known. On a test sample of human genes with known mammalian relatives the average overlap between the predicted and the actual genes was 99%, which is remarkably well as compared to other existing methods. At that, the algorithm absolute correctly reconstructed 87% of genes. The rare discrepancies between the predicted and real axon-intron structures were restricted either to extremely short initial or terminal exons or proved to be results of alternative splicing. Moreover, the algorithm performs reasonably well with non-vertebrate and even prokaryote targets. The spliced alignment software PROCRUSTES has been in extensive use by the academic community since …

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 pulled low; slot 21 will have the value 10100. See Appendix A; (4) Route a differential 1553 signal from a triaxial bulkhead connector to slots 2 through 11. This differential signal is bussed as a daisy chain. A 75 ohm resistor to ground shall be located near the last destination slot for each of these two signals; (5) Route a second differential 1553 signal from a triaxial bulkhead connector to slots 12 through 21. This differential signal is bussed as a daisy chain. A 75 ohm resistor to ground shall be located near the last destination slot for each of these two signals; (6) Route two NRZ signals …

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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 to calculate the requested dose rate(s) and document the calculation in a fashion to allow comparisons to other waste forms and WP designs at a future time.

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. The objective of this analysis is to provide SAS2H generated isotopic compositions for each fuel assembly's depleted fuel and depleted burnable poison materials. These SAS2H generated isotopic compositions are acceptable for use in CRC benchmark reactivity calculations containing the various fuel assemblies.

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 decrease in surface area of the supports is due to pore filling and blocking during the impregnation of supports with iron and promoters. During the current reporting period one slurry reactor test (SB-2337) was performed with an alumina supported catalyst with nominal composition 100 Fe/5 Cu/9 K/139 Al{sub 2}0{sub 3}, which was synthesized in our laboratory during the last quarter. The performance of this catalyst was inferior in comparison to our catalysts B (100 Fe/5 Cu/6 K/24 SiO{sub 2}) and C (100 Fe/3 Cu/4 K/16 SiO{sub 2}). Activity of the alumina supported catalyst was lower, and its catalyst deactivation rate was higher than that of the baseline catalysts B and C. The work on testing of …

The simple nuclear Ramsauer model has been used successfully to fit neutron cross sections for three decades, but has not been widely used because the foundations of the model seem to be so unrealistic. We have shown that the Glauber calculations with the inclusion of refraction and optical model calculations essentially validate this simple model for neutron total cross sections in the neutron energy range of 5-50 MeV. This model yields a simple formula for parameterizing the energy dependence of the neutron cross section. We have applied the model to nuclei ranging from vanadium to bismuth. With the addition of a single parameter, we can improve these fits to less than 1.5%.

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 5.4.28. Update FXTPTM corrects a trip pointer error in subroutine TIMCHK that prevented the trip-initiated, problem-termination feature from functioning in TRAC-P.

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.

The Chemistry & Materials Sciences (C&MS) Directorate is in the third year of a four-year space consolidation plan. In 1994, approximately half of the total directorate square footage was comprised of 40-year old wet chemistry research buildings that had exceeded their useful life and were viewed a legacy facilities to the program. This mix of old vs. new laboratory space was not properly aligned nor suited for future needs of C&MS, from both the cultural or economic position, thus change was needed. C&MS instituted an aggressive, strategic, business-driven space consolidation initiative, called SAT (Space Action Team), to optimize space utilization, reduce annual costs, meet strategic program needs, and consolidate activities by functional area. The plan called for a 4-year process beginning in FY95 to realign the directorate`s facility portfolio through relocations, consolidations, transfer of facility ownership, demolition of trailers and new construction with a 20% sq/ft reduction as an end goal. As with all business driven initiatives, existing operating costs, implementation costs, cost avoidance and future operating costs were key metrics to measure against the strategic goal. Where P2 was not an essential element in the strategic planning process, it played a key role in the continuing success of the …

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 that 50 m, would require an expensive, very finely sampled survey ({lt} 1 m receiver spacing). Extensive image processing of the LLNL 2-D test line indicated that the only reliable reflection was from the top of the water table. Surprisingly, these results were very different than recent 3-D seismic work recorded at other sites, where high quality, high frequency surface (up to 300 Hz) reflection images were obtained as shallow as 20m. We believe that the differences are primarily due to the comparatively deep vadose zone at LLNL (15 to 30m) as compared to 0-5m at other sites. The thick vadose zone attenuates the reflection signals, particularly at the high frequencies (above 100 @). In addition, the vadose zone …

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 record gives the curies for 46 key radionuclides, decayed to a common reference date of January 1, 1994.

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.

Project W-314 sn-632 transfer line ax-b to az-02a acceptance for beneficial use.

Single-shell W C-106 is on an accelerated schedule for partial retrieval of its softer, high-he-at sludge. The sludge is being transferred to a double-shell tank because they have the capacity to handle more heat-bearing materials than do single-shell tanks. Also, unlike single-shell tanks, they have not shown any tendency to leak. This transfer will eliminate the need to add water to C-106, thus lowering the risk of waste leaching to the environment. The transfer also will allow obligations to the Washington State Department of Ecology regarding removal of drainable liquid from all single-shell tanks to be met. Current schedules show the soft-sludge retrieval starting in September 1997. To prepare for retrieval, issues related to the risk from potential propagating reactions caused by the organic chemistry of tank C-106 were evaluated.