Progress is reported on the following: well conditions; perforating and cementing; temperature-depth plot; slotted liner, well head and auxiliary equipment; well testing and analysis program; well monitoring during standby; environmental assessment; time schedule; and budgets. (MHR)

By exposing samples to various irradiance levels from a calibrated thermal radiation source, the ignition responses of blackened alpha-cellulose and cotton cloth with and without fire-retardant additives were compared. Samples treated with retardant compounds which showed the most promise were then isothermally pyrolyzed in air for comparisons between the pyrolysis rates. Alpha-cellulose samples containing a mixture of boric acid, borax, and ammonium di-hydrogen phosphate could not be ignited by irradiances up to 4.0 cal cm/sup -2/ s-1 (16.7 W/cm/sup 2/). At higher irradiances the specimens ignited, but flaming lasted only until the flammable gases were depleted. Cotton cloth containing a polymeric retardant with the designation THPC + MM was found to be ignition-resistant to all irradiances below 7.0 cal cm/sup -2/ s/sup -1/ (29.3 W/cm/sup 2/). Comparison of the pyrolysis rates of the retardant-treated alpha-cellulose and the retardant-treated cotton showed that the retardant mechanism is qualitatively the same. Similar ignition-response measurements were also made with specimens exposed to ionizing radiation. It was observed that gamma radiation results in ignition retardance of cellulose, while irradiation by neutrons does not.

Various waste management systems were examined in order to determine what the environmental impacts might be and to rank the relative importance of those impacts. This examination determined that radiation dose to man was the most significant, and probably overriding, impact. This report describes methods of providing an objective function for dose to man. The search for an objective function began with a reading of Federal Regulations and the output of various standard setting councils and committees. Ample guidance was found on maximum allowable doses to individuals but no guidance on dose to large populations or criteria by which systems could be compared or optimized. Several other ways were postulated by which waste management systems could be evaluated besides maximum allowable dose to individuals. 0.1 man-rem per MW(e)-year was selected as the measure of system performance. This unit compares a rational estimate of population dose commitment with the concurrent benefit.

Estimates were made of the shielding thicknesses required at various points around the ISABELLE ring. Both hadron and muon requirements are considered. Radiation levels at the outside of the shield and at the BNL site boundary are kept at or below 1000 mrem per year and 5 mrem/year respectively. Muon requirements are based on the Wang formula for pion spectra, and the hadron requirements on the hadron cascade program CYLKAZ of Ranft. A muon shield thickness of 77 meters of sand is indicated outside the ring in one area, and hadron shields equivalent to from 2.7 to 5.6 meters in thickness of sand above the ring. The suggested safety allowance would increase these values to 86 meters and 4.0 to 7.2 meters respectively. There are many uncertainties in such estimates, but these last figures are considered to be rather conservative.

A practical model has been developed that is capable of describing the overall Ge(Li) detection efficiency as a function of several known or measurable parameters such as gamma-ray energy, source-to-detector distance, detector dimensions, source extension (area and volume), source composition, and external absorbers. The algorithms of this model permit the evaluation of a large variety of sample shapes, sizes, material compositions, and source strengths with a single initial detector calibration. Sources of small volume generally can be measured to within 1 to 2 percent regardless of energy or source-to-detector distance. Even large volume sources placed at close-in geometries give results within 10 percent of the correct values.

The principal aim of the National Waste Terminal Storage (NWTS) program is to develop pilot plants and, ultimately, repositories in several different rock formations in various parts of the country. Rocks such as salt, shale, limestone, granite, schists, and serpentinite may all qualify as host media for the disposition of radioactive wastes in the proper environments. In general, the only requirement for any rock formation or storage site is that it contain any emplaced wastes for so long as it takes for the radioactive materials to decay to innocuous levels. This requirement, though, is a formidable one as some of the wastes will remain active for periods of hundreds of thousands of years and the physical and chemical properties of rocks that govern circulating groundwater and hence containment, are difficult to determine and define. Nevertheless, there are many rock types and a host of areas throughout the country where conditions are promising for the development of waste repositories. Some of these are discussed below.

Objective of this program is to provide facilities (Federal repositories) in various deep geologic formations at several locations in USA for the safe disposal of commercial radioactive waste from power reactors. The four types of containerized waste are described. The steps for developing the repositories are outlined. (DLC)

About 40 underground nuclear explosions detonated at the Nevada Test Site (NTS) were chosen for analysis of their spectra and any relationships they might have to source parameters such as yield, depth of burial, etc. The sample covered a large yield range (less than 20 kt to greater than 1 Mt). Broadband (0.05 to 20 Hz) data recorded by the four-station seismic network operated by Lawrence Livermore Laboratory were analyzed in a search for unusual explosion signatures in their spectra. Long time windows (total wave train) as well as shorter windows (for instance, P/sub n/) were used as input to calculate the spectra. Much variation in the spectra of the long windows is typical although some gross features are similar, such as a dominant peak in the microseismic window. The variation is such that selection of corner frequencies is impractical and yield scaling could not be determined. Spectra for one NTS earthquake showed more energy in the short periods (less than 1 sec) as well as in the long periods (greater than 8 sec) compared to those for NTS explosions.

Large pools for storing spent fuel elements from nuclear reactors are being proposed to augment the present storage capacity of pools located at nuclear power plants and fuel reprocessing plants. These pools will be part of either independent spent fuel storage installations or large reprocessing plants. Because of the large size of the pools, seismic loads are of significant interest, and in particular the adequacy of current design methods for calculating seismic loads was of special concern. An evaluation of design methods representative of current practice was carried out, and the results are summarized. The evaluation was based on a comparison of total structural loads obtained by these methods with those obtained using the LUSH code. The LUSH code offered a combination of latest technologies in structural analysis involving soil-structure interaction.

Results of homogeneous catalytic hydrogenation of complex unsaturated substrates including coal and coal-derived materials are reported, with organic soluble molecular complexes as catalysts. Among the substrates used were Hvab coal, solvent-refined coal, and COED pyrolysate. The hydrogenations were carried out in an autoclave. The results are summarized in tables.

The objective of this investigation is to determine the upper limits on the thermal yield of a 1 kt source detonated at shallow depths. Three problems were computed for the depths of burial of 0.5, 1.5, and 3 m. The source is an iron bubble with 30 cm radius and 25 kg of mass. The computation was done on the CEL code. The results show that the relative thermal yield is no more than 6 percent, and that it vanishes at DOB of about 4 m. The computed blast strength is plotted against the range. The results are consistent with the measurements on ''Johnnie Boy'' and ''Jangle-U'', and in good agreement with the RAD9 calculations and the HULL calculations.

Experimental data in the literature on the physical, thermodynamic, and transport properties of aqueous LiOH are summarized. The behavior of some properties is predicted beyond the range of the data. 12 fig, 14 tables, 20 references.

This manual describes the use and structure of the June 30, 1976 version of the Four-D propagation code for high energy laser beams. It provides selected sample output from a typical run and from several debug runs. The Four-D code now includes the important noncoplanar scenario feature. Many problems that required excessive computer time can now be meaningfully simulated as steady-state noncoplanar problems with short run times.

In the study of ductile fracture it is useful to simulate fracture on the computer under plane stress conditions. In general, this is a three dimensional problem. Presented here is a method for adapting a two dimensional elastic-plastic computer program to calculate problems in plane stress as well as plane strain geometry. A simulation of a tension test of a flat aluminum plate pulled to failure is calculated with the modified two dimensional program. The results are compared with a fully three dimensional calculation. Finally a comparison is made with an experiment to demonstrate the effectiveness of the computational methods for studying fracture of work hardening materials.

The use of the Borrmann effect to produce nearly monoenergetic x rays is described. Both theoretical and experimental results are presented for the energy range from 15 to 55 keV. Peak shape, full-widths at half-maximum, and intensities are discussed. In addition, a brief description of a computer code for calculating the theoretical results is given.

During 1975 Pantex Plant conducted a monitoring program to determine the concentration of specific radioactive and non-radioactive species in the local environment. Although the plant activities involve the handling of significant quantities of uranium, plutonium and tritium, only small releases of uranium (depleted in the isotope /sup 235/U) and tritium occurred which could have affected the local environment. Monitoring data indicate that concentrations of these nuclides in the environment are below established criteria for air and water and therefore should not present a health hazard either to employees or to the public.

An add-on program is proposed to the existing Brayton Isotope Power System (BIPS) Contract E(04-3)-1123. The proposed program includes the design and fabrication of a superalloy BIPS ''workhorse'' loop and the technical assessment of an optimized superalloy flight system (FS).

The field-reversed-mirror (FRM) is a plasma-confinement scheme that uses the diamagnetic current of the deuterium-tritium (D-T) fuel plasma to convert the open-field pattern of a conventional mirror machine into a closed-field pattern that should have considerably improved plasma-confinement properties. If realized, this improvement in confinement will considerably improve the energy gain of the mirror reactor and will reduce the cost of producing energy. The FRM device is described and compared with earlier field-reversed configurations. The overall energy and particle-balance relations are given and used as bases for preliminary engineering design calculations of the major components of an FRM reactor. We find that the engineering design leads to simple structures (e.g., circular coils, cylindrical vacuum tanks) for which it is easy to make reasonably accurate cost estimates. A cost optimization has been performed; the optimum D-T reactor is found to have a fusion output of 23 MW/cell from a 5-cm radius, 15-cm long plasma in a field of roughly 10 T.

A series of laser fusion microimplosion experiments have been performed with the LLL two beam laser system JANUS. The JANUS laser is capable of focusing up to 400 gigawatts of 1.06 ..mu..m laser power (32J in 80 psec) on microscopic laser fusion targets, producing intensities in excess of 10/sup 17/ w/cm/sup 2/. In these experiments the targets were Deuterium--Tritium (DT) gas filled, thin walled (.5 to 1.0 ..mu..m) SiO/sub 2/ microshells with diameters of 40 to 100 ..mu..m. Targets with these dimensions, properties and laser powers operate in what has become known as the exploding pusher mode. A summary of the salient points of each design limit is illustrated.

A relatively simple model, using Baker parameters, is described and applied to flow-regime data generated by high speed photography of two-phase steam flow. The experiments were conducted at the Geothermal Test Facility (GTF) at Lawrence Livermore Laboratory. Although results depend somewhat on the personal judgment and interpretation of the observer, the model was found to give a reasonable prediction of the flow regime for the flow ranges available in 1- and 2-in.-diam pipes.