This NRC Plan, which defines NRC's functional role in cleanup operations at Three Mile Island Unit 2 and outlines NRC's regulatory responsibilities in fulfilling this role, is the first revision to the initial plan issued in July 1980 (NUREG-0698). Since 1980, a number of policy developments have occurred which will have an impact on the course of cleanup operations. This revision reflects these developments in the area of NRC's review and approval process with regard to cleanup operations as well as NRC's interface with the Department of Energy's involvement in the cleanup and waste disposal. This revision is also intended to update the cleanup schedule by presenting the cleanup progress that has taken place and NRC's role in ongoing and future cleanup activities.

The Fluidized-Bed Waste-Heat Recovery (FBWHR) System is designed to preheat this combustion air using the heat available in dirty flue gas streams. In this system, a recirculating medium is heated by the flue gas in a fluidized bed. The hot medium is then removed from the bed and placed in a second fluidized bed where it is fluidized by the combustion air. Through this process, the combustion air is heated. The cooled medium is then returned to the first bed. Initial development of this concept is for the aluminum smelting industry.

An aeroelastic stability analysis has been developed for predicting flutter instabilities on vertical axis wind turbines. The analytical model and mathematical formulation of the problem are described as well as the physical mechanism that creates flutter in Darrieus turbines. Theoretical results are compared with measured experimental data from flutter tests of the Sandia 2 Meter turbine. Based on this comparison, the analysis appears to be an adequate design evaluation tool.

Two models for describing the behavior of dense gases have been adapted for specific applications at the Savannah River Plant (SRP) and have been programmed on the IBM computer. One of the models has been used to predict the effect of a ruptured H/sub 2/S storage tank at the 400 Area. The other model has been used to simulate the effect of an unignited release of H/sub 2/S from the 400-Area flare tower.

This study determined how well crude and fuel oils burn on water. Objectives were: (1) to measure the burning rates for several oils; (2) to determine whether adding heat improves the oils' combustibility; (3) to identify the conditions necessary to ignite fuels known to be difficult to ignite on ocean waters (e.g., diesel and Bunker C fuel oils); and (4) to evaluate the accuracy of an oil-burning model proposed by Thompson, Dawson, and Goodier (1979). Observations were made about how weathering and the thickness of the oil layer affect the combustion of crude and fuel oils. Nine oils commonly transported on the world's major waterways were tested. Burns were first conducted in Oklahoma under warm-weather conditions (approx. 30/sup 0/C) and later in Ohio under cold-weather conditions (approx. 0/sup 0/C to 10/sup 0/C).

Calculations of the average neutronic properties of the ensemble of fission products producted by fast-neutron fission of /sup 235/U and /sup 239/Pu, where the properties are determined before the first beta decay of any of the fragments, are described. For each case we approximate the ensemble by a weighted average over 10 selected nuclides, whose properties we calculate using nuclear-model parameters deduced from the systematic properties of other isotopes of the same elements as the fission fragments. The calculations were performed primarily with the COMNUC and GNASH statistical-model codes. The results, available in ENDF/B format, include cross sections, angular distributions of neutrons, and spectra of neutrons and photons, for incident-neutron energies between 10/sup -5/ eV and 20 MeV. Over most of this energy range, we find that the capture cross section of /sup 239/Pu fission fragments is systematically a factor of two to five greater than for /sup 235/U fission fragments.

This report presents results of a Hydrogeochemical and Stream Sediment Reconnaissance (HSSR) of the Bettles NTMS quadrangle, Alaska. In addition to this abbreviated data release, more complete data are available to the public in machine-readable form. These machine-readable data, as well as quarterly or semiannual program progress reports containing further information on the HSSR program in general, or on the Los Alamos National Laboratory (LANL) portion of the program in particular, are available from DOE's Technical Library at its Grand Junction Area Office. Presented in this data release are location data, field analyses, and laboratory analyses of several different sample media. For the sake of brevity, many field site observations have not been included in this volume; these data are, however, available on the magnetic tape. Appendices A and B describe the sample media and summarize the analytical results for each medium. The data have been subdivided by one of the Los Alamos National Laboratory sorting programs of Zinkl and others (1981a) into groups of stream-sediment and lake-sediment samples. For each group which contains a sufficient number of observations, statistical tables, tables of raw data, and 1:1,000,000 scale maps of pertinent elements have been included in this report. Also included …

This technical monthly report covers studies related to the use of /sup 238/PuO/sub 2/ in radioisotope power systems carried out for the Office of Coordination and Special Projects of the US Department of Energy by los Alamos National Laboratory. Most of the studies discussed here are ongoing. Results and conclusions described may change as the work continues. Published reference of the results cited in this report should not be made without the explicit permission of the person in charge of the work.

The removal of hydrogen sulfide and other sulfur gaseous compounds from the fuel gas of coal gasification plants using iron and zinc oxides has been accomplished with promising success. Associated with this desulfurization process is the problem of regeneration of the metal sulfides formed back to the oxide state for reuse. For the efficient design and optimum operation of process plants, it is imperative that the reaction mechanism for the gas-solid reactions be known as also the gas and solids dispersion and movement in the reactor. In recent years, four mechanistic models have been developed and proposed for this purpose. In section II, models intended for use in connection with the noncatalytic gas-solid reactions are briefly described. They are: shrinking core model, homogeneous model, grain model and pore model. All the four models have been employed to mechanistically describe the desulfurization process in a fixed bed of granular metal oxide. In the light of limited success of these models in their present form to represent the experimental data, a relative assessment of their appropriateness is given in the last section of this report along with some recommendations for future work.

This report describes research in environment, health, and safety conducted during fiscal year 1981. The five parts of the report are oriented to particular segments of the program. Parts 1 to 4 report on research performed for the DOE Office of Health and Environmental Research in the Office of Energy Research. Part 5 reports progress on all research performed for the Office of the Assistant Secretary for Environmental Protection, Safety and Emergency Preparedness. The parts are: Part 1: Biomedical Sciences under Program Manager, H. Drucker; Part 2: Ecological Sciences, under Program Manager, B.E. Vaughan; Part 3: Atmospheric Sciences under Program Manager, C.E. Elderkin; Part 4: Physical Sciences under Program Manager, J.M. Nielsen; and Part 5: Environmental and Occupational Protection, Assessment, and Engineering under Program Managers, D.L. Hessel, S. Marks, and W.A. Glass.

Sufficient discussion of the elements of the leasing and permitting programs is included to place the information developed in proper context. A table and process flow diagram developed previously which outline the steps in the non-competitive leasing process, is reprinted. Computer printout profiles are presented on 195 identifiable areas in the following states: Arizona, California, Colorado, Idaho, Montana, Nevada, New Mexico, Oregon, Utah, Washington, and Wyoming. Sufficient information on the boundaries of these areas is contained in the report to permit identification of their general location on any map of the appropriate state which shows township and range locations.

This report presents the results of ground water, stream water, and stream sediment reconnaissance in Illinois, Indiana, Kentucky, Tennessee, and Ohio. The following sample types were collected in each state: Illinois - 716 stream sediment, 1046 ground water, 337 stream water; Indiana - 126 stream sediment, 443 ground water, 111 stream water; Kentucky - 4901 stream sediment, 6408 ground water, 3966 stream water; Tennessee - 3309 stream sediment, 3574 ground water, 1584 stream water; Ohio - 1214 stream sediment, 2049 ground water, 1205 stream water. Neutron activation analyses are given for U, Br, Cl, F, Mn, Na, Al, V, and Dy in ground water and stream water, and for U, Th, Hf, Ce, Fe, Mn, Na, Sc, Ti, V, Al, Dy, Eu, La, Sm, Yb, and Lu in sediments. Supplementary analyses by other techniques are reported for U (extractable), Ag, As, Ba, Be, Ca, Co, Cr, Cu, K, Li, Mg, Mo, Nb, Ni, P, Pb, Se, Sn, Sr, W, Y, and Zn. These analyses were made on 248 sediment samples from Tennessee. Field measurements and observations are reported for each site. Oak Ridge National Laboratory analyzed sediment samples which were not analyzed by Savannah River Laboratory neutron activation.

A Hamiltonian formulation of the guiding-center drift in arbitrary, steady state, magnetic and electric fields is given. The canonical variables of this formulation are simply related to the magnetic coordinates. The modifications required to treat ergodic magnetic fields using magnetic coordinates are explicitly given in the Hamiltonian formulation.

Accurate radiative transfer calculations are performed in the middle ultraviolet spectral region for aerosol-loaded atmospheres with the goal of determining the solar irradiance at the ground and quantifying the irradiance perturbations due to the presence of aerosols and various ozone depletions. The extent of the increase of UV-B radiation as a function of wave-length and solar zenith angle is calculated for five model atmospheres. In addition, the damaging ultraviolet dose rates and radiation amplification factors are evaluated at different latitudes and seasons for erythemal and DNA action spectra.

North Dakota Concrete Products Company uses a steam curing process that accelerates the concrete curing so that 28-day strength is obtained within 24 hours. The cost of energy required to accomplish this is significant, amounting to approximately $80,000 in 1980. The present boilers are oil fired. Recently, fuel oil prices have increased substantially. Further, supply shortages in the past have threatened plant production. The purpose of this study was to evaluate the economic feasibility of using deep formation warm water as an alternative energy source. A water-to-water heat pump system to replace the existing boiler system was investigated. TPI, Inc. economic and engineering findings for this particular potential geothermal application are disclosed. The operating cost savings of the geothermal system over the operating costs of the existing oilfired system would be insufficient to provide an acceptable rate of return on the investment at todays cost of money.

The use of methane-related fuels, derived from a variety of sources, in highway vehicles is assessed. Methane, as used here, includes natural gas (NG) as well as synthetic natural gas (SNG). Methanol is included because it can be produced from NG or the same resources as SNG, and because it is a liquid fuel at normal ambient conditions. Technological, operational, efficiency, petroleum displacement, supply, safety, and economic issues are analyzed. In principle, both NG and methanol allow more efficient engine operation than gasoline. In practice, engines are at present rarely optimized for NG and methanol. On the basis of energy expended from resource extraction to end use, only optimized LNG vehicles are more efficient than their gasoline counterparts. By 1985, up to 16% of total petroleum-based highway vehicle fuel could be displaced by large fleets with central NG fueling depots. Excluding diesel vehicles, which need technology advances to use NG, savings of 8% are projected. Methanol use by large fleets could displace up to 8% of petroleum-based highway vehicle fuel from spark-ignition vehicles and another 9% from diesel vehicles with technology advances. The US NG supply appears adequate to accommodate fleet use. Supply projections, future price differential versus gasoline, and …

The tanning process and associated energy requirements are summarized. It appears that a significant economic impact may be possible if a shallow hydrothermal resource of approximately 150 to 170/sup 0/F (66 to 77/sup 0/C) were found, and the fluids were cascaded to produce the temperatures necessary for the various tanning operations. The hydrothermal energy would have to be cost competitive with the rapidly escalating fossil energy costs. Although one would need to thoroughly analyze the technical, environmental, and economic issues of such an application, this initial review indicates a good match between the process and potential hydrothermal resources.

Although existing radioisotope thermoelectric generator designs have proved more than adequately safe, more information is continually sought about the heat sources to improve their safety. The work here includes studies of the effects on the heat sources of terrestrial and aquatic environments and also of the effect of the heat sources on various simulated environments. This progress report presents recent data from environmental chamber and aquatic experiments and gives the present status of the experiments.

Separate abstracts were prepared for the 38 reports for this Pacific Northwest Laboratory Annual Report for 1981 to the DOE Office of Energy Research. This part dealt with research conducted in the ecological sciences.

Considerable information useful in nuclear waste storage can be gained by studying the conditions of uranium ore deposit formation. Further information can be gained by comparing the chemistry of uranium to nuclear fission products and other radionuclides of concern to nuclear waste disposal. Redox state appears to be the most important variable in controlling uranium solubility, especially at near neutral pH, which is characteristic of most ground water. This is probably also true of neptunium, plutonium, and technetium. Further, redox conditions that immobilize uranium should immobilize these elements. The mechanisms that have produced uranium ore bodies in the Earth's crust are somewhat less clear. At the temperatures of hydrothermal uranium deposits, equilibrium models are probably adequate, aqueous uranium (VI) being reduced and precipitated by interaction with ferrous-iron-bearing oxides and silicates. In lower temperature roll-type uranium deposits, overall equilibrium may not have been achieved. The involvement of sulfate-reducing bacteria in ore-body formation has been postulated, but is uncertain. Reduced sulfur species do, however, appear to be involved in much of the low temperature uranium precipitation. Assessment of the possibility of uranium transport in natural ground water is complicated because the system is generally not in overall equilibrium. For this reason, Eh …

This report details the results of research on the matrix encapsulation of high level wastes at PML over the past few years. The demonstrations and tests described were designed to illustrate how the waste materials are effected when encapsulated in an inert matrix. Candidate materials evaluated for potential use as matrices for encapslation of pelletized ceramics or glass marbles were categorized into four groups: metals, glasses, ceramics, and graphite. Two processing techniques, casting and hot pressing, were investigated as the most promising methods of formation or densification of the matrices. The major results reported deal with the development aspects. However, chemical durability tests (leach tests) of the matrix materials themselves and matrix-waste form composites are also reported. Matrix waste forms can provide a low porosity, waste-free barrier resulting in increased leach protection, higher impact strength and improved thermal conductivity compared to unencapsulated glass or ceramic waste materials. Glass marbles encapsulated in a lead matrix offer the most significant improvement in waste form stability of all combinations evaluated. This form represents a readily demonstrable process that provides high thermal conductivity, mechanical shock resistance, radiation shielding and increased chemical durability through both a chemical passivation mechanism and as a physical barrier. Other …

Logistical functions that are normally associated with US underground coal mining are investigated and analyzed. These functions imply all activities and services that support the producing sections of the mine. The report provides a better understanding of how these functions impact coal production in terms of time, cost, and safety. Major underground logistics activities are analyzed and include: transportation and personnel, supplies and equipment; transportation of coal and rock; electrical distribution and communications systems; water handling; hydraulics; and ventilation systems. Recommended areas for future research are identified and prioritized.

The computational physics group is ivolved in several areas of fusion research. One main area is the application of multidimensional Fokker-Planck, transport and combined Fokker-Planck/transport codes to both toroidal and mirror devices. Another major area is the investigation of linear and nonlinear resistive magnetohydrodynamics in two and three dimensions, with applications to all types of fusion devices. The MHD work is often coupled with the task of numerically generating equilibria which model experimental devices. In addition to these computational physics studies, investigations of more efficient numerical algorithms are being carried out.

In this report the current state of waste package development for high level waste, transuranic waste, and spent fuel in the US and abroad has been assessed. Specifically, reviewed are recent and on-going research on various waste forms, container materials and backfills and tentatively identified those which are likely to perform most satisfactorily in the repository environment. Radiation effects on the waste package components have been reviewed and the magnitude of these effects has been identified. Areas requiring further research have been identified. The important variables affecting radionuclide release from the waste package have been described and an evaluation of regulatory criteria for high level waste and spent fuel is presented. Finally, for spent fuel, high level, and TRU waste, components which could be used to construct a waste package having potential to meet NRC performance requirements have been described and identified.