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Anaerobic bioprocessing of low rank coals. Quarterly progress report, April 1--June 30, 1991
significant achievements were: (1) Coal decarboxylation was achieved by batch bioreactor systems using adapted anaerobic microbial consortium. (2) Two new isolates with coal decarboxylation potential were obtained from adapted microbial consortia. (3) CHN and TG anaysis of anaerobically biotreated coals have shown an increase in the H/C ratio and evolution rate of volatile carbon which could be a better feedstock for the liquefaction process.
Date:
December 31, 1991
Creator:
Jain, M. K.; Narayan, R. & Han, O.
Object Type:
Report
System:
The UNT Digital Library
Anaerobic bioprocessing of low-rank coals. Quarterly progress report, January 1--March 31, 1991
The objective of this project is to find biological methods to remove carboxylic functionalities from low rank coals under ambient conditions and to assess the properties of these modified coals towards coal decarboxylation. The microbial consortia will be developed using a fermentor system first under batch and then in a continuous system. The main objectives for this quarter were to develop microbial consortia that would decarboxylate coal and isolate potential anaerobic microorganisms with decarboxylating, ability from these enriched microbial consortia, to continue to compare the known cultures with reward to their ability to decarboxylate coal, and to characterize the anaerobically biotreated coal using FTIR to confirm decarboxylation of coal. Significant achievements during the period include: coal decarboxylation was possible only under anaerobic conditions. microbial consortia that can anaerobically decarboxylate coal have been developed using anaerobic vials and batch fermentor system, and loss of carboxyl groups in biotreated coal has been confirmed by FT-IR.
Date:
December 31, 1991
Creator:
Jain, M. K.; Narayan, R. & Han, O.
Object Type:
Report
System:
The UNT Digital Library
Analyses of corium spreading in Mark I containment geometry
An assessment of melt spreading in the Mark I system has been carried out using the MELTSPREAD-1 computer code together with supporting analyses. Application of MELTSPREAD-1 confirms the calculation of shell survival in a wet containment for the most probable melt release conditions from NUREG/CR-5423. According to MELTSPREAD-1, a dry containment also may not be threatened by melt spreading. This reflects the heat losses undergone by the melt in the process of spreading to the shell conservatively neglected in NUREG/CR-5423. However, there exist parameter ranges outside the most probable set where shell failure may be calculated. Accounting for the breakup and quenching of melt relocating through a deep layer of subcooled water also conservatively neglected in NUREG/CR-5423 can reduce the set of parameter variations for which containment failure is calculated in the wet case.
Date:
December 31, 1991
Creator:
Sienicki, J. J.; Chu, C. C. & Farmer, M. T.
Object Type:
Article
System:
The UNT Digital Library
Analyses of SRS waste glass buried in granite in Sweden and salt in the United States
Simulated Savannah River Site (SRS) waste glass forms have been buried in the granite geology of the Stirpa mine in Sweden for two years. Analyses of glass surfaces provided a measure of the performance of the waste glasses as a function of time. Similar SRS waste glass compositions have also been buried in salt at the WIPP facility in Carlsbad, New Mexico for a similar time period. Analyses of the SRS waste glasses buried in-situ in granite will be presented and compared to the performance of these same compositions buried in salt at WIPP.
Date:
December 31, 1991
Creator:
Williams, J. P.; Wicks, G. G.; Clark, D. E. & Lodding, A. R.
Object Type:
Article
System:
The UNT Digital Library
Analysis of a high brightness photo electron beam with self field and wake field effects
High brightness sources are the basic ingredients in the new accelerator developments such as Free-Electron Laser experiments. The effects of the interactions between the highly charged particles and the fields in the accelerating structure, e.g. R.F., Space charge and Wake fields can be detrimental to the beam and the experiments. We present and discuss the formulation used, some simulation and results for the Brookhaven National Laboratory high brightness beam that illustrates effects of the accelerating field, space charge forces (e.g. due to self field of the bunch), and the wake field (e.g. arising from the interaction of the cavity surface and the self field of the bunch).
Date:
December 31, 1991
Creator:
Parsa, Z.
Object Type:
Article
System:
The UNT Digital Library
Analysis of benchmark critical experiments with ENDF/B-VI data sets
Several clean critical experiments were analyzed with ENDF/B-VI data to assess the adequacy of the data for U{sup 235}, U{sup 238} and oxygen. These experiments were (1) a set of homogeneous U{sup 235}-H{sub 2}O assemblies spanning a wide range of hydrogen/uranium ratio, and (2) TRX-1, a simple, H{sub 2}O-moderated Bettis lattice of slightly-enriched uranium metal rods. The analyses used the Monte Carlo program RCP01, with explicit three-dimensional geometry and detailed representation of cross sections. For the homogeneous criticals, calculated k{sub crit} values for large, thermal assemblies show good agreement with experiment. This supports the evaluated thermal criticality parameters for U{sup 235}. However, for assemblies with smaller H/U ratios, k{sub crit} values increase significantly with increasing leakage and flux-spectrum hardness. These trends suggest that leakage is underpredicted and that the resonance eta of the ENDF/B-VI U{sup 235} is too large. For TRX-1, reasonably good agreement is found with measured lattice parameters (reaction-rate ratios). Of primary interest is rho28, the ratio of above-thermal to thermal U{sup 238} capture. Calculated rho28 is 2.3 ({+-} 1.7) % above measurement, suggesting that U{sup 238} resonance capture remains slightly overpredicted with ENDF/B-VI. However, agreement is better than observed with earlier versions of ENDF/B.
Date:
December 31, 1991
Creator:
Hardy, J. Jr. & Kahler, A. C.
Object Type:
Report
System:
The UNT Digital Library
Analysis of embedded waste storage tanks subjected to seismic loading
At the Savannah River Site, High Activity Wastes are stored in carbon steel tanks that are within reinforced concrete vaults. These soil-embedded tank/vault structures are approximately 80 ft. in diameter and 40 ft. deep. The tanks were studied to determine the essentials of governing variables, to reduce the problem to the least number of governing cases to optimize analysis effort without introducing excessive conservatism. The problem reduced to a limited number of cases of soil-structure interaction and fluid (tank contents) -- structure interaction problems. It was theorized that substantially reduced input would be realized from soil structure interaction (SSI) but that it was also possible that tank-to-tank proximity would result in (re)amplification of the input. To determine the governing seismic input motion, the three dimensional SSI code, SASSI, was used. Significant among the issues relative to waste tanks is to the determination of fluid response and tank behavior as a function of tank contents viscosity. Tank seismic analyses and studies have been based on low viscosity fluids (water) and the behavior is quite well understood. Typical wastes (salts, sludge), which are highly viscous, have not been the subject of studies to understand the effect of viscosity on seismic response. The …
Date:
December 31, 1991
Creator:
Zaslawsky, M.; Sammaddar, S. & Kennedy, W. N.
Object Type:
Article
System:
The UNT Digital Library
Analysis of mercury diffusion pumps
Several mercury diffusion pump stages in the Tritium Purification process at the Savannah River Site (SRS) have been removed from service for scheduled preventive maintenance. These stages have been examined to determine if failure has occurred. Evidence of fatigue around the flange portion of the pump has been seen. In addition, erosion and cavitation inside the throat of the venturi tube and corrosion on the other surface of the venturi tube has been observed. Several measures are being examined in an attempt to improve the performance of these pumps. These measures, as well as the noted observations, are described. 4 refs.
Date:
December 31, 1991
Creator:
Dunn, K. A.
Object Type:
Article
System:
The UNT Digital Library
Analysis of mercury in simulated nuclear waste
Mercury, Hg, is a non-radioactive component in the High Level Waste at the Savannah River Site (SRS). Thus, it is a component of the Defense Waste Processing Facility`s (DWPF) process streams. It is present because mercuric nitrate (Hg(NO{sub 3}){sub 2}) is used to dissolve spent fuel rods. Since mercury halides are extremely corrosive, especially at elevated temperatures such as those seen in a melter (1150{degrees}C), its concentration throughout the process needs to be monitored so that it is at an acceptable level prior to reaching the melter off-gas system. The Hg can be found in condensates and sludge feeds and throughout the process and process lines, i.e., at any sampling point. The different samples types that require Hg determinations in the process streams are: (1) sludges, which may be basic or acidic and may or may not include aromatic organics, (2) slurries, which are sludges with frit and will always contain organics (formate and aromatics), and (3) condensates, from feed prep and melter off-gas locations. The condensates are aqueous and the mercury may exist as a complex mixture of halides, oxides, and metal, with levels between 10 and 100 ppm. The mercury in the sludges and slurries can be Hg{sup …
Date:
December 31, 1991
Creator:
Policke, T. A.; Johnson, L. C. & Best, D. R.
Object Type:
Article
System:
The UNT Digital Library
Analysis of organic sulfur and nitrogen in coal via tandem degradation methods. Technical report, 1 September--30 November 1991
With the recent increase in concern for environmental issues and the implication of sulfur and nitrogen in coal combustion products as prime causes of acid rain, it has become clear that there is an urgent need for alternative methods for determining the nature of organic sulfur and nitrogen compounds in coal. The present study couples mold oxidative and reductive procedures to enhance the depolymerization of coal and its constituent macerals and the quantities of produces amenable to analysis. The study also seeks to apply the degradative techniques to coal asphaltenes, since they are believed to be polymeric structures similar to the whole coal, but smaller and more readily analyzed. While the research effort will focus on Illinois coal, additional samples with even higher sulfur contents will also used, allowing for much easier detection and characterization of organic sulfur structures. A preliminary tests of this hypothesis indicates that many of the same sulfur compounds are present in both the Illinois and in an extremely sulfur-rich coal and that the more complex sulfur compounds are indeed more concentrated in the sulfur-rich sample.
Date:
December 31, 1991
Creator:
Kruge, M. A.
Object Type:
Report
System:
The UNT Digital Library
Analysis of postulated events for the revised ALMR/PRISM design
The Nuclear Regulatory Commission (NRC) is continuing a pre-application review of the 471 MWt, Liquid Metal Reactor, PRISM by General Electric, with Brookhaven National Laboratory providing technical support. The revised design has been evaluated, using the SSC code, for an unscrammed loss of heat sink (ULOHS), an unscrammed loss of flow (ULOF) with and without the Gas Expansion Modules (GEMs), and a 40{cents} unscrammed transient overpower (UTOP) event. The feedback effects for U-27Pu-10Zr metal fuel were modeled in SSC. The ULOHS accident was determined to be a benign event for the design, with the reactor power transitioning down to a decay heat level within 500s. The power during the postulated ULOF events, with the GEMs functioning, transitioned to decay heat levels without fuel damage, and included a 300K margin to sodium saturation. The case without the GEMs had only a 160K margin to sodium saturation and higher fuel temperatures. In addition, the clad was predicted to quickly pass through the eutectic phase (between fuel and clad), and some clad wastage would result. The 40{cents} UTOP was predicted to raise the power to 1.8 rated, which later stabilized near 1.2 times full power. SSC predicted some localized fuel melting for the …
Date:
December 31, 1991
Creator:
Slovik, G. C. & Van Tuyle, G. J.
Object Type:
Article
System:
The UNT Digital Library
Analysis of slot cutting methods for the Yucca Mountain heated block test using a compliant-joint model
Pretest analysis of a heated block test, proposed for the Exploratory Studies Facility at Yucca Mountain, Nevada, was conducted in this investigation. Specifically, the study focuses on the evaluation of the various designs to drill holes and cut slots for the block. The thermal/mechanical analysis was based on the finite element method and a compliant-joint rock-mass constitutive model. Based on the calculated results, relative merits of the various test designs are discussed.
Date:
December 31, 1991
Creator:
Chen, E.P. & Costin, L.S.
Object Type:
Article
System:
The UNT Digital Library
Analysis of sweeping heat loads on divertor plate materials
The heat flux on the divertor plate of a fusion reactor is probably one of the most limiting constraints on its lifetime. The current heat flux profile on the outer divertor plate of a device like ITER is highly peaked with narrow profile. The peak heat flux can be as high as 30--40 MW/m{sup 2} with full width at half maximum (FWHM) is in the order of a few centimeters. Sweeping the separatrix along the divertor plate is one of the options proposed to reduce the thermomechanical effects of this highly peaked narrow profile distribution. The effectiveness of the sweeping process is investigated parametrically for various design values. The optimum sweeping parameters of a particular heat load will depend on the design of the divertor plate as well as on the profile of such a heat load. In general, moving a highly peaked heat load results in substantial reduction of the thermomechanical effects on the divertor plate. 3 refs., 8 figs.
Date:
December 31, 1991
Creator:
Hassanein, A.
Object Type:
Article
System:
The UNT Digital Library
Analysis of the NP-MHTGR concept: A comparison of reactor physics methods
Using the MCNP and ONEDANT analysis codes, we investigated basic neutronic characteristics of the NP-MHTGR preconceptual design. Exploratory steady-state analyses of k{sub eff}, neutron reaction rates, andtemperature reactivity coefficients were conducted to check die ability of our reactor physics methods to adequately model the highly heterogeneous NP-MHTGR reactor. Results of unit-fuel-cell analyses indicate that a three-region ONEDANT model adequately approximates the unit-fuel-cell lattice geometry. However, core-block analyses indicate that approximating an hexagonal heterogeneous block by a one-dimensional annular target cell can introduce significant calculational error. Investigating the core-block temperature coefficient of reactivity, we found that all components of the coefficient are negative and the delayed component contributes {approx}85% of the total temperature effect. Investigation of the full reactor temperature coefficient in the NP-MHTGR determined that all contributions from the active core are negative, with prompt effects again contributing {approx}15% of the total core coefficient Temperature-coefficient contributions from each of the reflector regions appear to be positive, but exhibit a smaller magnitude than those in the core. These positive contributions apparently are caused by reduced carbon and boron absorptions at the higher reflector temperatures. From a safety perspective, a conclusion as to the adequacy of the temperature coefficient cannot be drawn …
Date:
December 31, 1991
Creator:
Pelowitz, D B; Sapir, J L & Wing, J E
Object Type:
Article
System:
The UNT Digital Library
An analytical assessment of the chemical form of fission products during postulated severe accidents in the SRS production reactors
An analysis has been performed to determine the principal chemical forms for the structural and fission product elements during a postulated severe core damage accident in tritium powered core in the Savannah River Site (SRS) reactors. These reactors are powered with UAl{sub x} fuel and are used for the production of weapons materials. Six core elements, cesium, iodine, tellurium, strontium, barium, and lithium, were emphasized in this analysis. Other elements also included were aluminum, hydrogen, oxygen, uranium, molybdenum, silicon, zirconium, magnesium, iron, chromium, nickel, cadmium, zinc, cooper, manganese, nitrogen, and argon. The masses of each of the constituents used in the analyses were based on end-or-core life masses for the structural and fission product elements and on core gas volume for steam, N, and Ar. A chemical equilibrium analysis was performed using the Facility for Analysis of Chemical Thermodynamics (FACT) computer code at three temperatures (800, 1100, 1400 K) and two pressures (1 and 10 atmospheres). These temperatures and pressures are typical for postulated severe core accidents in the ATR.
Date:
December 31, 1991
Creator:
Adams, J. P.
Object Type:
Article
System:
The UNT Digital Library
Analytical prediction and experimental verification of reactor safety system injection transient
This paper describes the computer code that was developed for thermal hydraulic transient analysis of mixed phase fluid system and the flow tests that were carried out to validate the Code. A full scale test facility was designed to duplicate the Supplementary Shutdown System (SSS) of Savannah River Production Reactors. Several steady state and dynamic flow tests were conducted simulating the actual reactor injection transients. A dynamic multiphase fluid flow code was developed and validated with experimental results and utilized for system performance predictions and development of technical specifications for reactors. 3 refs.
Date:
December 31, 1991
Creator:
Roy, B. N. & Nomm, E.
Object Type:
Article
System:
The UNT Digital Library
Anion-exchange resin-based desulfurization process. Quarterly technical progress report, October 1, 1991--December 31, 1991
The University of Tennessee Space Institute (UTSI) has a Department of Energy grant to further develop the Institute`s anion-exchange resin-based flue gas, desulfurization concept. The developmental program proposed includes screening of commercially available resins to select three candidate resins for further study. These three resins will undergo a series of experiments designed to test the resins` performance under different process conditions (including the use of spent MHD seed material). The best of these resins will be used in optimizing the regeneration step and in testing the effects of performance enhancers. The process schematic developed from the results will be used to estimate the related economics.
Date:
December 31, 1991
Creator:
Sheth, A. C. & Strevel, S. D.
Object Type:
Report
System:
The UNT Digital Library
Annual dynamics within the active layer. Annual progress report, March 15, 1990--March 14, 1991
We have continued our meteorological and hydrologic data collection in support of our process-oriented research. The six years of data collected to date is unique in its scope and continuity in a North Hemisphere Arctic setting. This valuable data base has allowed us to further our understanding of the interconnections and interactions between the atmosphere/hydrosphere/biosphere/lithosphere. The increased understanding of the heat and mass transfer processes has allowed us to increase our model-oriented research efforts. Examples of applications are the following. (1) Spring snowmelt on the North Slope of Alaska is the dominant hydrologic event of the year. This event provides most of the moisture for use by vegetation in the spring and early summer period. The mechanisms and timing of snowmelt are important factors in predicting runoff, the migrations of birds and large mammals and the diversity of plant communities. It is important globally due to the radical and abrupt change in the surface energy balance over vast areas. (2) We were able to explore the trends and differences in the snowmelt process along a transect from the Brooks Range to the Arctic Coastal plain. Snowpack ablation was monitored at three sites. These data were analyzed along with meteorologic data …
Date:
December 31, 1991
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Annual meeting of the Calorimetry Exchange Program: minutes--April 24-25, 1991
On April 24-25, 1991, people from seven DOE organizations participated in the annual meeting of the Calorimetry Exchange Program. The meeting featured a review of the statistical analysis of the calorimetry and gamma-ray data submitted to the exchange program during 1990. The meeting also enabled the group to review progress of five projects concerning a tritium exchange program, reprogramming of the database, a catalogue of measurement techniques, additional samples, and recharacterization of the current sample. There were presentations on recent advances in calorimetry and gamma-ray measurements.
Date:
December 31, 1991
Creator:
unknown
Object Type:
Article
System:
The UNT Digital Library
Annual site environmental report for calendar year 1991
The Western Area Power Administration (Western) has established a formal environmental protection, auditing, monitoring, and planning program which has been in effect since 1978. The significant environmental projects and issues Western was involved with in 1991 are discussed in this annual site environmental report. It is written to demonstrate the nature and effectiveness of the environmental protection program. Western is responsible for the operation and maintenance of 16,664 miles of transmission lines, 265 substations, and various appurtenant power facilities in fifteen central and western states. Western also is responsible for planning, construction, and operation and maintenance of additional federal transmission facilities that may be authorized in the future. There is a combined total of 51 hydroelectric power generating plants in the service area. Additionally, Western markets the US entitlement from the Navajo coal-fired plant near Page, Arizona. The Department of Energy requires the preparation of an annual site environmental report. Because Western has numerous facilities located in these states, this report was written to address the environmental activities in all of the facilities as one site.
Date:
December 31, 1991
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Annual site environmental report for calendar year 1991
The Western Area Power Administration (Western) has established a formal environmental protection, auditing, monitoring, and planning program which has been in effect since 1978. The significant environmental projects and issues Western was involved with in 1991 are discussed in this annual site environmental report. It is written to demonstrate the nature and effectiveness of the environmental protection program. The Department of Energy Order 5400.1, Chapter 2.4, requires the preparation of an annual site environmental report. Because Western has numerous facilities located in 15 states, this report was written to address the environmental activities in all of the facilities as one ``site``. In 1991, Western provided power to 615 wholesale power customers consisting of cooperatives, municipalities, public utility districts, investor-owned utilities, federal and state agencies, irrigation districts, and project use customers. The wholesale power customers, in turn, provide service to millions of retail consumers in the States of California, Nevada, Montana, Arizona, Utah, New Mexico, Texas, North Dakota, South Dakota, Iowa, Colorado, Wyoming, Minnesota, Nebraska, and Kansas.
Date:
December 31, 1991
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Anomalous transport in toroidal plasmas. Annual report, [June 1, 1990--May 31, 1991]
We have developed a Monte Carlo method to estimate the transport of different groups of particles for plasmas in toroidal geometries. This method can determine the important transport mechanisms driving the anomalous transport by comparing the numerical results with the experimental data. The important groups of particles whose transport can be estimated by this method include runaway electrons, thermal electrons, both passing and trapped diagnostic beam ions etc. The three basic mechanisms driving the anomalous transport are: spatial variation of magnetic field strength, spatial variation of electrostatic potential within the flux surfaces, and the loss of flux surfaces. The equation of motion are obtained from the drift hamiltonian. The equations of motion are developed in the canonical and in the non-canonical, practical co-ordinates as well. The effects of collisions are represented by appropriate stochastic changes in the constants of motion at each time-step. Here we present the results of application of this method to three cases: superathermal alphas in the rippled field of tokamaks, motion in the magnetic turbulence of takapole II, and transport in the stochastic fields of ZT40. This work is supported by DOE OFE and ORAU HBCU program.
Date:
December 31, 1991
Creator:
Punjabi, A.
Object Type:
Report
System:
The UNT Digital Library
The antibody approach of labeling blood cells
Although the science of blood cell labeling using monoclonal antibodies directed against specific cellular antigens is still in its early stages, considerable progress has recently been accomplished in this area. The monoclonal antibody approach offers the promise of greater selectivity and enhanced convenience since specific cell types can be labeled in vivo, thus eliminating the need for complex and damaging cell separation procedures. This article focuses on these developments with primary emphasis on antibody labeling of platelets and leukocytes. The advantages and the shortcomings of the recently reported techniques are criticality assessed and evaluated.
Date:
December 31, 1991
Creator:
Srivastava, S. C.
Object Type:
Article
System:
The UNT Digital Library
Apparatus for generating a robotic plan for automatically assembling a mechanical component
This invention is comprised of an apparatus operable in combination with a robot positioned in a workcell having a preselected specification is operable to generate a program for operating the robot to assemble a mechanical component. The apparatus includes a planner for receiving as inputs a CAD model of the mechanical component to be assembled, a set of robot primitives and a set of mechanical component assembly rules for determining the conditions under which the set of robot primitives apply. The planner generates from these inputs a general, workcell specification-independent plan for assembling the mechanical component. The general plan generated by the planner is provided as an input to a compiler along with details relating to the workcell specification, and the compiler generates from these inputs a workcell specification-dependent program which operates the robot to assemble the mechanical component.
Date:
December 31, 1991
Creator:
Maciejewski, A. A. & Strip, D. R.
Object Type:
Patent
System:
The UNT Digital Library