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 condition for extracting a maximum negative ion current density is found when the product of the radius of the negative ion conversion electrode, the cross-section for negative and positive ion recombination, and the density of positive ions in the ion source equals one. The optimum output is obtained at the highest positive ion density and the smallest electrode radius.

The relevance of the statistical equilibrium limit to the description of substantially relaxed degrees of freedom is discussed. Fluctuations are considered specifically in the following processes: the correlation between entrance-channel angular momentum and exit-channel kinetic energy; the sharing of the dissipated kinetic energy between the two fragments; the magnitude and the alignment of the fragment angular momentum including the effect of shell structure. It is found that statistical fluctuations play a major role and that the statistical equilibrium limit seems to have been reached for a number of degrees of freedom.

Originally an orthorhombic structure was assigned to the non-stoichiometric hydride TiCr/sub 1/ /sub 8/H/sub 3/ /sub 6/. Recent neutron and x-ray diffraction data indicated, however, that an alternate interpretation was possible, i.e. the solid consists of two hydride phases, an ..cap alpha..' Laves phase having a composition of TiCr/sub 1/ /sub 8/H/sub 2/ /sub 8/ and an fcc phase with a much higher hydrogen content. This proved to be the case and it has been determined that the high concentration phase has a disordered fluorite structure with a/sub o/=4.27 A. Its hydrogen content, as estimated from diffraction peak intensities, corresponds to TiCr/sub 1/ /sub 8/H/sub 5/ /sub 3/. We have not been able to produce single phase fcc material but have prepared a mixed phase sample with an overall composition of TiCr/sub 1/ /sub 8/H/sub 4/ /sub 8/. The high-pressure reaction leading to the formation of the fluorite phase is very sluggish and irreversible. Pressure-composition-temperature (p-c-T) properties of this system have been determined and are discussed and a revised phase diagram is proposed.

TMX Upgrade (TMX-U), a tandem mirror experiment at LLNL, will use high power microwaves for electron cyclotron resonant heating (ECRH). As demonstrated on Elmo Bumpy Torus (EBT) and related experiments which use similar heating techniques, high energy electron populations are created. In these devices, which run CW, significant x-ray production occurs and adequate shielding must be provided for personnel protection. TMX-U is a pulsed experiment; however, significant x-ray production is expected from the 50 keV mean energy electron population. In this report the expected x-ray generation is calculated and the provisions for shielding are described. Based upon these calculations, as well as scaling estimates from other devices, the provided shielding is shown to be adequate for hot electron temperatures of interest for the experiment.

Research progress in briefly described, and details are presented in the attached preprints and reprints: (1) precision mass differences in light rubidium and krypton isotopes utilizing beta endpoint measurements; (2) precision mass measurements utilizing beta endpoints; (3) Monte Carlo calculations predicting the response of intrinsic GE detectors to electrons and positrons; and (4) reactor antineutrino spectra and nuclear spectroscopy of isotopes far from beta stability. (WHK)

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).

This plan outlines the procedures and operations used at LLNL's Site 300 for the management of the hazardous waste generated. This waste consists primarily of depleted uranium (a by-product of U-235 enrichment), beryllium, small quantities of analytical chemicals, industrial type waste such as solvents, cleaning acids, photographic chemicals, etc., and explosives. This plan details the operations generating this waste, the proper handling of this material and the procedures used to treat or dispose of the hazardous waste. A considerable amount of information found in this plan was extracted from the Site 300 Safety and Operational Manual written by Site 300 Facility personnel and the Hazards Control Department.

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.

A prediction of dynamic soil properties at the site of a nuclear power plant plays a very important role in the seismic analysis of the facility. Conventional modal analysis procedures can accommodate virtually any range of equivalent elastic soil stiffness which is used to characterize the site. However, high radiation damping associated with energy dissipation in the soil half-space is difficult to accommodate in an elastic modal solution to the dynamic problem. Several methods are available to combine the soil damping with the structural damping in a composite modal damping coefficient. However, even with this convenient representation, the resulting large fractions of critical damping can make modal solutions to the problems suspect. This paper is based on experience gained in this area during studies performed for the Nuclear Regulatory Commission involving seismic analyses of power plants.

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.

Separate abstracts were prepared for each of the 10 included sections. (MOW)

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 paper summarizes the development testing in progress at the FFTF to determine the effectiveness of high temperature microphones as acoustic monitors in the upper plenum of the FFTF. The specific goal of this testing is development of an automated loose parts monitor for the upper plenum. A description of the acoustic probe is included, as well as a discussion of the signal processing. A summary of the results to date is also given.

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.

A possible source of preheat for heavy ion driven inertial fusion targets is the production of fast precursors by nuclear interactions between the incident heavy ions and the outer parts of the target. A model has been developed which roughly describes these interactions for all beam-target combinations for all incident energies. This interaction model has been applied to a specific capsule design. The resultant preheat is an order of magnitude below the level which could impair target performance.

The purpose of the research was to determine the degree of change in commercial building design practice relating to energy conservation since the enactment of the Energy Conservation Standard for New Buildings Act of 1976. Data on current design practices consisted of information from 400 buildings advertised for bids or under construction in 1979 to 1980 on glass in windows and doors, exterior wall systems, roof system, heating plants, and lighting systems. In addition to these building design components, energy conservation measures used included: natural lighting; deadband thermostat; greenhouse-effect atrium collector, heat recovery from the top of the atrium, greenhouse passive heating panels; natural ventilation; insulating shutters, closable skylights, thermal shutters, Trombe wall, corridor trombe; attic ventilation; wind shielding, concrete wall; titlted windows; night flushing cycle; and cooling coils using cooling tower water. A brief explanation of these measures is given. (MCW)