Least squares analyses of calorimetric measurements made at Mound Laboratory on two tritide compounds over a period of 18 y were performed to determine the half-life of tritium. A half-life of 12.3232 +- 0.0043 mean solar years was obtained.

This report summarizes our current effort and ideas toward the development of a model for the planetary boundary layer using the finite element technique. As an initial step, the finite element methodology is applied to simpler version of the boundary layer equations given by the two-dimensional, constant-property, incompressible conservation equations (Navier-Stokes equations). Solution procedures for both the steady-state and transient equations are discussed. For the transient problem, a variable time-step, trapezoid-rule algorithm with dynamic time-truncation error control is presented. The resulting system of nonlinear algebraic equations is solved by a Newton iteration procedure with a frontal solution scheme used for the linear set of equations. The need to develop a suitable linear equation solver, with respect to minimization of computer storage and execution costs, particularly for large (three-dimensional) finite element problems, is also discussed.

We propose to study the utilization of high-temperature (approximately 2000-2500K) process heat from fusion reactors for large-scale chemical process applications. Of particular interest is the decomposition reaction, CO/sub 2/ ..-->.. CO + /sup 1///sub 2/O/sub 2/, which at 2500K should yield approximately 60 percent conversion to CO if O/sub 2/ is partially removed through an oxide membrane. Hydrogen can be derived from CO at lower temperatures by reacting CO with steam, and C can also be derived from CO by a disproportionation into C and CO/sub 2/ at approximately 1000K. These chemicals, CO, H/sub 2/, and C, form the basis for a multitude of non-electrical energy applications in the areas of transportation, industrial processes, and residential and commercial uses. In addition to the CO/sub 2/ decomposition process, we propose to explore a variety of ideas and evaluate them for scientific and economic merit. A follow-on research and development program will be proposed if the ideas prove promising.

Results are reported of a study for the Nuclear Regulatory Commission (NRC) to provide a general understanding of pressure transient (water hammer) propagation in pressurized water reactor (PWR) steam generator feedwater piping systems. A typical feedwater network is defined, and pressure transient initiation is discussed, as well as the plausible pulse shapes reported. The analysis is performed by using the computer codes PTA and WHAM. Forces are calculated at elbows and valves by using momentum principles. The effects of pipe yielding, pipe wall friction, and elbow and value losses are included. Pipe yielding and elbow/valve effects are found to be important, and pressure magnitudes and forces are substantially reduced when these effects are included in the analysis. Typical pressure and force time histories are also given.

A particularly simple problem exhibiting stochasticity is the motion of a charged particle in a uniform magnetic field and a single wave. Detailed studies of this wave-particle interaction show the following features. An electrostatic wave propagating obliquely to the magnetic field causes stochastic motion if the wave amplitude exceeds a certain threshold. The overlap of cyclotron resonances then destroys a constant of the motion, allowing strong particle acceleration. A wave of large enough amplitude would thus suffer severe damping and lead to rapid heating of a particle distribution. The stochastic motion resembles a diffusion process even though the wave spectrum contains only a single wave. The motion of ions in a nonuniform magnetic field and a single electrostatic wave is treated in our study of a possible saturation mechanism of the dissipative trapped-ion instability in a tokamak. A theory involving the overlap of bounce resonances predicts the main features found in the numerical integration of the equations of motion. Ions in a layer near the trapped-circulating boundary move stochastically. This motion leads to nonlinear stabilization mechanisms which are described qualitatively.

Illustrations for the review on materials design and selection are presented. They include the mechanical engineering, the electrochemistry task, and information coordination. No text is presented. (MHR)

Preliminary results of engineering, economic, and geographic analysis of the use of low-temperature geothermal heat for the commercial drying of grains, grasses, fruits, vegetables and livestock products in the United States are reported. Alfalfa (lucerne) dehydration was chosen for detailed process and cost study. Six different geothermal heat exchanger/dryer configurations were examined. A conveyor type that could utilize geothermal hot water for its entire heat requirement proved to be the most economical. A capital cost estimate for an all-geothermal alfalfa dehydration plant near the Heber Known Geothermal Resource Area in the Imperial Valley, California was prepared. The combined cost for heat exchangers and dryer is about $1.6 million. Output is about 11 metric tons per hour. Acreage, production and dollar value data for 22 dryable crops were compiled for the areas surrounding identified hydrothermal resources in 11 western states. The potential magnitude of fossil fuel use that could be replaced by geothermal heat for drying these crops will be estimated.

The tests conducted on the /sup 1///sub 5/-scale BWR Mark I pressure suppression test facility simulate the three-dimensional transient conditions that are encountered in a wetwell pressure suppression system during a hypothetical loss-of-coolant accident (LOCA). Specifically, the nitrogen (N/sub 2/)-driven air clearing phase tests discussed were performed to obtain the air/water-induced dynamic vertical load function and to determine the response of a 90/sup 0/ sector of a 360/sup 0/ torus structure.

Space charge neutralization of ion beams results from plasma generated by the beam. The two dimensional flow of plasma to walls surrounding a beam is analyzed to provide spatial distributions. Negative ion beams receive particular attention; the results are applied to electron control in beams subject to post-acceleration.

A Tektronix-31 (Tektronix Inc. Beaverton, Oregon) desk top calculator program, which is used as a backup to the PDP-8/I computer program, is described. The program yields interplanar (d) spacings and (2theta) angle values from measurements made on an x-ray diffraction film of a powdered sample of a crystalline material. Use of the calculator provides accurate computations in a relatively rapid time interval when the PDP-8/I is not functioning because of downtime for repairs, maintenance, etc.

Previous studies by Behrens have provided evidence of systematic behavior in neutron-induced fission cross sections in the incident neutron energy range 3 to 5 MeV. Recently measured fission cross-section ratios revealed this behavior. In this report, these measurements and those of others are used to illustrate the behavior of fission cross sections over the neutron energy range 0.1 MeV to 15 MeV. Similar trends are seen at 0.0253 eV, as revealed by thermal cross-section measurements. 12 figures.

Progress is reported in the following research areas: cesium fixation in aluminosilicates and supercalcine development; low sodium wastes and high sodium wastes. Phase relations in the appropriate (for supercalcine) portion of the Cs/sub 2/O-Al/sub 2/O/sub 3/-SiO/sub 2/ system are being investigated. Several compatibility lines (tie lines) have been established on the phase diagram. Methods of preparing pure single phases of CsAlSiO/sub 4/ and CsAlSi/sub 2/O/sub 6/ (pollucite) are being developed. Compatibility studies continue to be the basis of supercalcine crystalline phase formation modeling. (LK)

Efforts this past quarter were directed toward the determination of dissolution parameters in various reagents of PuO/sub 2/, PuO/sub 2/-UO/sub 2/ solid solution, and AmO/sub 2/-PuO/sub 2/. The reagents used were various concentrations of HNO/sub 3/-HF-H/sub 2/SO/sub 4/, HNO/sub 3/-HF, HNO/sub 3/-(NH/sub 4/)/sub 2/Ce(NO/sub 3/)/sub 6/, and HNO/sub 3/-H/sub 2/SO/sub 4/. In one series of tests, simulated contaminated HEPA filter media were used. This material was prepared by mixing shredded filter media with actinide oxides. In another series, actual HEPA glovebox filter media contaminated with PuO/sub 2/ were used. Fusion tests were also completed using simulated PuO/sub 2/ contaminated filter media. Both Na/sub 2/CO/sub 3/ and Na/sub 2/CO/sub 3/-KNO/sub 3/ were investigated as possible fusion agents.

Reduced instrument responses are presented for Thermal-Hydraulic Test Facility (THTF) test 100, which is part of the ORNL Pressurized-Water-Reactor (PWR) Blowdown Heat Transfer Separate-Effects Program. The objective of the program is to investigate the thermal-hydraulic phenomenon governing the energy transfer and transport processes that occur during a loss-of-coolant accident in a PWR system. Test 100 was conducted to investigate the response of heater rod bundle 1 and instrumented spool pieces with flow homogenizing screens to a double-ended rupture with equal break areas at the test section inlet and outlet. The primary purpose of this report is to make the reduced instrument responses during test 100 available. The responses are presented in graphical form in engineering units and have been analyzed only to the extent necessary to assure reasonableness and consistency.

None

Observations on the use of the SEMPEX computer code are given. The issues of proper sampling rate and total sampling interval are addressed. The effect that noise in the data has on the results and the ability of autocorrelation, truncation filtering, and the sliding-window technique to reduce these effects are also discussed. 35 figures, 24 tables.

Various leaching agents were tested to determine their capability for dissolving PuO/sub 2/, UO/sub 2/, and U/sub 3/O/sub 8/. The amount of radionuclides retained by the filter media was investigated. Adsorption isotherms for two leaching systems were obtained. A four-stage dissolution process was developed. 10 figures, 2 tables.

The tests conducted on the 1/5-scale BWR Mark I pressure suppression test facility simulate the three-dimensional transient conditions that are encountered in a wetwell pressure suppression system during a hypothetical loss-of-coolant accident (LOCA). Specifically, the nitrogen (N2)-driven air clearing phase tests discussed here were performed to obtain the air/water-induced dynamic vertical load function and to determine the response of a 90/sup 0/ sector of a 360/sup 0/ torus structure.

Permeabilities of 10.2 cm in length, 2.5 cm in diameter Kayenta (porosity, 20.7, +- 1.66%) and St. Peter (porosity, 13.6, +- 0.13%) sandstones to Magmamax No. 1 brine containing suspended solids were determined from 70 to 90/sup 0/C at 10.3-MPa confining pressure. Measurements were performed without filters, with one 10-..mu..m filter, and with two 10-..mu..m filters inserted upstream of the core sample. In all cases, there was a dramatic decrease in permeability within the first hour of flow or few hundred pore volumes of flow through the core. Experiments conducted without filters or with one filter yield permeabilities that represent both the rock and the 2- to 3-mm amorphous silica-iron layer on the top face of the core. The experimental results show that if the Salton Sea Geothermal Field (SSGF) were composed of porous, sedimentary formations similar to Kayenta sandstone, long-term injection of unmodified Magmamax brine would not be feasible. In the case of acidified brine, most of the permeability decline may result from the mobilization of calcite.

The work plan, schedule, and staffing plan to study the potential market for fuel cell total energy systems are outlined. (WHK)

During FY76 Lawrence Livermore Laboratory (LLL) continued its development of niobium tin (Nb/sub 3/Sn) conductors and its design support for the mirror fusion test facility (MFTF) superconducting magnet. Three highlights came from within the Laboratory. LLL completed its cryogenic tensile-test apparatus for NB/sub 3/Sn strain measurements. Over at MFTF, engineers ordered 2100 m of prototype material for a 1-m test coil. People at the high-field test facility (HFTF) released some components for fabrication; delivery was scheduled for early FY77. Outside LLL several subcontractors advanced Nb/sub 3/Sn manufacturing technology. One advance, in particular, improved conductor current densities at 12 T.

The primary objective of the proposed research will be elucidation of the etiology and pathogenesis of bovine leukemia. We have consistently demonstrated C-type particles in mitogen stimulated lymphocyte cultures from leukemic cows and cows with a persistent lymphocytosis. These particles have been concentrated and partially purified by continuous flow, density gradient, ultracentrifugation. Newborn calves and late stage bovine fetuses have been inoculated with these concentrated cell free preparations. Our current study involves extensive monitoring of these inoculated animals to detect early pre-cancerous changes. The following parameters are being measured: the serological titer against a bovine leukemia associated antigen; the percentage of lymphocytes showing nuclear pockets; the percentage of mitogen stimulated lymphocytes with C-type particles adherent to their surface; the percentage of B-lymphocytes in the peripheral circulation; the complete blood count; and the quantity of bovine leukemia virus (BLV) production as determined by the syncytia induction assay. Additional proposals include: using the monitoring parameters to study animals with the juvenile and thymic forms of leukemia; the examination of adult lymphosarcoma cases to determine which tissues harbor BLV; and lymphocyte subpopulation work to further define which cell types are associated with BLV production and tumor formation.

The results of calculations are presented for the decay time required prior to LOFT ECCS shutdown bypass actuation following a reactor shutdown. These calculations are based on a LOCA occurring during hot shutdown which would void the core. Based on an operator response time of 20 minutes to manually establish ECC flow, the reactor decay time was calculated to prevent the fuel cladding temperature from exceeding 1100/sup 0/F. Results show that 211 hours are required following normal reactor shutdown from 55 MW reactor power before ECCS shutdown bypass actuation can be allowed if the reactor is not in cold shutdown condition. One hundred (100) seconds are required following a LOCE before ECCS shutdown bypass actuation can be allowed.

One of the problems confronted in the investigation of environmental health and in biological research more generally is the fact that organisms often respond to combinations of treatments in ways which are not predictable from the way they respond to each of these taken separately. One air pollutant may, for example, disable the respiratory tract's self cleaning mechanisms and thereby increase its sensitivity to the effects of other pollutants. It is important that laboratory experiments be able to simultaneously detect the effects of the various possible combinations of treatments in a way that utilizes the data as effectively as possible. This paper deals with the optimal use of data from such experiments when the response variable can be regarded (possibly after undergoing a suitable transformation) as having a normal distribution with mean determined by the combination of treatments it has undergone.