Ptolemy is an IBM/360 program for the computation of nuclear elastic and direct-reaction cross sections. It carries out both optical-model fits to elastic-scattering data at one or more energies, and DWBA calculations for nucleon-transfer reactions. Ptolemy has been specifically designed for heavy-ion calculations. It is fast and does not require large amounts of core. The input is exceptionally flexible and easy to use. This report outlines the types of calculation that Ptolemy can carry out, summarizes the formulas used, and gives a detailed description of its input.

A procedure is described for the dynamic analysis of a fast-reactor hexagonal subassembly. The internals of the fuel subassembly are treated by an axisymmetric hydrodynamic code REXCO-HT which, among other properties, possesses a model of an MFCI pressure source. The housing of the fuel subassembly is handled by the SADCAT code, which is based on a triangular finite element in three-dimensional space. The code is used to illustrate the discrepancies involved if the hexcan is modeled by a cylinder of the same thickness. A study is also made of the reduction of cylinder thickness such that the same final cylindrical deformation can be predicted. A discussion in arriving at such an equivalence is offered.

Various mechanisms that can induce flow instabilities in two-phase flow systems are reviewed and their relative importance discussed. In view of their practical importance, the density-wave instabilities have been analyzed in detail based on the one-dimensional two-phase flow formulation. The dynamic response of the system to the inlet flow perturbations has been derived from the model; thus the characteristic equation that predicts the onset of instabilities has been obtained. The effects of various system parameters, such as the heat flux, sub-cooling, pressure, inlet velocity, inlet orificing, and exit orificing on the stability boundary have been analyzed. In addition to numerical solutions, some simple stability criteria under particular conditions have been obtained. Both results have been compared with various experimental data, and a satisfactory agreement has been demonstrated.

The interim report presented describes a continuation of the work reported in ANL-7890, Interaction of Sodium with Molten Uranium dioxide and Stainless Steel Using a Dropping Mode of Contact. In the current study, sodium was injected into a pool of molten uranium dioxide. The experiment consistently produced vapor explosions, both with the injection nozzle above and beneath the surface of the uranium dioxide. Although the efficiency of the conversion of thermal to mechanical energy was small (due in part to very conservative data analysis and an inefficient geometry), the results did demonstrate that there is no intrinsic reason why reactor materials cannot produce a vapor explosion.

About 1200 Mark II driver-fuel elements were xenon-tagged to facilitate qualification for irradiation of Mark II fuel manufactured at ANL-West. Tagging equipment was designed and developed. In this equipment, the plenum in a fuel-element jacket was evacuated then filled with xenon to a predetermined pressure. The equipment design allows tagging and element fabrication to proceed normal rates for production of fuel elements. A Kr-85 tracer in the xenon-tag gas verified by gamma counting the adequate tagging of each element.

Annual report of the environmental monitoring program at Argonne National Laboratory, discussing activities and findings of the group.

This course seeks to achieve two objectives: to provide initial safety training for people just beginning work with plutonium, and to serve as a review and reference source for those already engaged in such work. Numerous references have been included to provide information sources for those wishing to pursue certain topics more fully. The first part of the course content deals with the general safety approach used in dealing with hazardous materials. Following is a discussion of the four properties of plutonium that lead to potential hazards: radioactivity, toxicity, nuclear properties, and spontaneous ignition. Next, the various hazards arising from these properties are treated. The relative hazards of both internal and external radiation sources are discussed, as well as the specific hazards when plutonium is the source. Similarly, the general hazards involved in a criticality, fire, or explosion are treated. Comments are made concerning the specific hazards when plutonium is involved. A brief summary comparison between the hazards of the trans-plutonium nuclides relative to plutonium-239 follows. The final portion deals with control procedures with respect to contamination, internal and external exposure, nuclear safety, and fire protection. The philosophy and approach to emergency planning are also discussed.

This report is a compilation of the formal Final Safety Analysis Addenda (FSAA's) to the EBR-II Hazard Summary Report and Addendum that have been prepared in support of certain modifications to the reactor-shutdown-system portion of the EBR-II plant protection system. Each major section is an edited version of the original FSAA for a particular modification and provides a description of the pre - and post -modification system, the rationale for the modification, and required supporting safety analysis.

The motion and location of the molten-cladding during an unprotected loss-of-flow accident in liquid metal fast breeder reactors are important because of the effects on the reactivity and the subsequent fuel motion. The present study analyzes the cladding-relocation problem based on a single-channel film-flow model and a simple thermal transient model for fuel pins. The motion of molten cladding induced by sodium-vapor streaming undergoes initial rapid upward acceleration, slowing down, flow reversal, and eventual slumping down into liquid sodium at the lower end of the heated section. Freezing of the molten cladding at the unheated upper plenum region is possible; bottom freezing and blockage formation were also included in the analysis. A simple calculation has been made for the R-series seven-pin tests in the TREAT reactor. The agreement of the overall physical behavior of the cladding motion with the post-test observations is quite satisfactory.

An experimental apparatus was constructed to examine the heat-transfer characteristics of a sputtering front. In the present study, a heat source of sufficient intensity was located immediately below the sputtering front, which prevented its downward progress, thus permitting detailed measurements of steady-state surface temperatures throughout a sputtering front. A two-dimensional analytical model was developed to describe a stationary sputtering front where the wet-dry interface corresponds to a CHF phenomena and the dry zone is adiabatic. This model is nonlinear because of the temperature dependence of the heat-transfer coefficient in the wetted region and has yielded good agreement with data. A simplified one-dimensional approximation was developed which adequately describes these data. Finally, by means of a coordinate transformation and additional simplifying assumptions, this analysis was extended to analyze moving sputtering fronts, and reasonably good agreement with reported data was shown.

Six groups of jobs were run on the IBM 370/195 at the Applied Mathematics Division (AMD) of Argonne National Laboratory using the current production versions of OS/MVT 21.7 and ASP 3.1. The same jobs were then run on an AMDAHL 470V/6 at the AMDAHL manufacturing facilities in Sunnyvale, California, using the identical operating systems. Performances of the two machines are compared. Differences in the configurations were minimized. The memory size on each machine was the same, all software which had an impact on run times was the same, and the I/O configurations were as similar as possible. This allowed the comparison to be based on the relative performance of the two CPU's. As part of the studies preliminary to the acquisition of the IBM 195 in 1972, two of the groups of jobs had been run on a CDC 7600 by CDC personnel in Arden Hills, Minnesota, on an IBM 360/195 by IBM personnel in Poughkeepsie, New York, and on the AMD 360/50/75 production system in June, 1971.

Present concepts of disposal of low-level aqueous wastes (LLAW) that contain much of the fission-product tritium from light water reactors involve dispersal to the atmosphere or to surface streams at fuel reprocessing plants. These concepts have been challenged in recent years. Deep-well injection of low-level aqueous wastes, an alternative to biospheric dispersal, is the subject of this presentation. Many factors must be considered in assessing its feasibility, including technology, costs, environmental impact, legal and regulatory constraints, and siting. Examination of these factors indicates that the technology of deep-well injection, extensively developed for other industrial wastes, would require little innovation before application to low-level aqueous wastes. Costs would be low, of the order of magnitude of 10⁻⁴ mill/kWh. The environmental impact of normal deep-well disposal would be small, compared with dispersal to the atmosphere or to surface streams; abnormal operation would not be expected to produce catastrophic results. Geologically suitable sites are abundant in the U.S., but a well would best be co-located with the fuel-reprocessing plant where the LLAW is produced. Legal and regulatory constraints now being developed will be the most important determinants of the feasibility of applying the method.

Annual report of the environmental monitoring program at Argonne National Laboratory, discussing activities and findings of the group.

Report on research and development of the lead-acid battery for electric vehicle propulsion, focusing on continuing development on the forced electrolyte flow-through concept with some work on the composite, plastic/lead grid.

Report on the environmental impact of Argonne National Laboratory.

The conditions are given for which the more flexible of two cantilevered, telescoping tubes conveying fluid can be self-excited by flow leaking from an un-constricted slip joint. Also, a physical explanation of the excitation mechanism is discussed, and a design rule to avoid the mechanism is presented. In addition, the results for the un-constricted slip joint are shown to be similar to those for slip joints having annulus constrictions at very short engagement lengths.

Annual report on the results of efforts to evaluate the effect of Argonne National Laboratory operations on the environment.

Annual report of the Argonne National Laboratory Radiological and Environmental Research Division regarding activities related to the Center for Human Radiobiology. This report contains a mixture of original countributions, abstracts of published papers, and summaries of papers presented at meetings.

Quarterly report of the Argonne National Laboratory Chemical Engineering Division regarding activities related to properties and handling of radioactive materials, operation of nuclear reactors, and other relevant research.

Quarterly report of the Argonne National Laboratory Chemical Engineering Division regarding activities related to properties and handling of radioactive materials, operation of nuclear reactors, and other relevant research.

A process is being developed by the Sodium Waste Technology Program at ANL-W to remove metallic sodium from scrap and waste. The final step in the process is the removal of residual metallic sodium by evaporation at temperatures up to 482 C (900 F) and at pressures of about 10⁻² torr (1.3 Pa). Efficient operation of this process requires that the operators have a method to indicate the completion of the evaporation. This end point would signify when the chamber and scrap and waste is free of metallic sodium. It was determined that a measure of the vacuum was not sufficiently sensitive, and a research effort was undertaken to select an on-line monitoring device. In this effort, three promising methods were reviewed. The use of quadrupole mass spectrometer was recommended and an on-line device was designed for use in a Sodium Process Demonstration (SPD) Plant.

This report describes the preparation of a series of manganese oxides and an analysis of their sorptive, structural, and surface characteristics as low-energetic desiccants for passive dehumidification and active desiccant cooling systems. A cusped Type III isotherm for the adsorption of water is reported for the first time. The data are interpreted as evidence of a first-order phase change from a two-dimensional gas to a liquid film in the first reversibly adsorbed layer. It appears that the water adsorption characteristics of MnO2 compared to standard desiccants which exhibit Type II isotherms are due at least in part to differences in the physical topography and electronic properties of the desiccant substrates: MnO2 is a p-type semiconductor with essentially-flat, monoenergetic surface structures, while standard desiccants like silica gel are electronic insulators with irregular, heteroenergetic surfaces.

The need to understand concrete behavior under high temperatures in the nuclear industry has become rather acute. For this purpose, a constitutive model of concrete especially developed for this severe environment is indispensable. This report reviews the presently available constitutive models of concrete at standard-temperature conditions and considers their advantages and drawbacks. A rather simple but effective approach is selected to treat concrete behavior at high temperatures. Special emphasis is devoted to the modeling of concrete up to and including failure. The derived constitutive model is checked with biaxial and triaxial benchmark experimental results. Very good agreement is obtained.

Measurements of the optical properties of metallic aluminum are reviewed and available data are analyzed to obtain the bulk values of the optical constants and the complex dielectric function from 0.04 eV to 10 keV. The intra- and interband contributions to the dielectric function are discussed briefly, and recently proposed values for the Drude parameters describing the intraband absorption are critically considered. Factors influencing experimental measurements are discussed with emphasis on sample properties such as surface oxide layers, bulk inclusion of gases, surface roughness, and degree of crystallinity. The results of recent optical measurements are tabulated, along with recommended values of the optical properties resulting from a self-consistent Kramers-Kronig analysis of reflectance, transmission, and electron-energy-loss studies. The tabular data include the complex dielectric function, the complex index of refraction, and the reflectance and phase shift for normal incidence on a smooth, oxide-free surface. Detailed tabulations are given for the infrared, visible, and ultraviolet regions of the spectrum.