Report describing the design of a Fast Fuel Test Reactor (FFTR), analyses of of the reactor's operations, related costs, and possible future projects.

From Introduction: "This report describes tests conducted on EBWR to evaluate the vapor recovery system."

From Introduction: "Los Alamos and British lifetime measurements are consistent with the results reported here."

From Introduction: "This report will present and discuss the results of a preliminary investigation for a facility which could be utilized to test nuclear rocket fuel elements at operating conditions."

Report issued by the Argonne National Laboratory discussing engineering properties of diphenyl. As stated in the abstract, "data collected from the literature on the vapor pressure, enthalpy, liquid density, and vapor density of pure diphenyl are presented. A Mollier diagram, a temperature entropy diagram, and data on viscosity of diphenyl as a function of temperature are also presented" (p. 5). This report includes tables, and illustrations.

Report issued by the Argonne National Laboratory discussing the Experimental Breeder Reactor (EBR). Descriptions and methods of the EBR are presented. This report includes tables, and illustrations.

Analysis of a class of steady magnetohydrodynamic channel flow problems when natural, as well as forced, convection is important.

A condition of compression loading could possibly occur to a subassembly as a result of large length changes to irradiation-induced swelling and thermal expansion. The effects of axial compression loading on EBR-II experimental and driver-fuel subassemblies were evaluated. Compression tests that were performed on the slotted top fixture of a subassembly showed that a force of 2100 lb at 900 degrees F would close the slot enough so that the core-gripper blade would not fit into the slot. Such a slot closure would prevent the subassembly from being removed from the reactor with the core gripper.

Analytical and experimental methods are presented for evaluating the vibration characteristics of cylindrical shells such as the thermal liner of the Fast Flux Test Facility (FFTF) reactor vessel. The NASTRAN computer program is used to calculate the natural frequencies, mode shapes, and response to a harmonic loading of a thin, circular cylindrical shell situated inside a fluid-filled rigid circular cylinder. Solutions in a vacuum are verified with an exact solution method and the SAP IV computer code. Comparisons between analysis and experiment are made, and the accuracy and utility of the fluid-solid interaction package of NASTRAN is assessed.

This report provides a summary of theoretical and experimental studies of actinide spectra in condensed phases. Much of the work was accomplished at Argonne National Laboratory, but references to related investigations by others are included. Spectroscopic studies of the trivlent actinides are emphasized, as is the use of energy level parameters, evaluated from experimental data, to investigate systematic trends in electronic structure and other properties. Some reference is made to correlations with atomic spectra, as well as with spectra of the (II), (IV), and higher valence states.

The reliability of stainless steel type 304L canisters for the containment of solidified high-level radioactive wastes in the glass and calcine forms was studied. A reference system, drawn largely from information furnished by Battelle Northwest Laboratories and Atlantic Richfield Hanford Company is described. Operations include filling the canister with the appropriate waste form, interim storage at a reprocessing plant, shipment in water to a Retrievable Surface Storage Facility (RSSF), interim storage at the RSSF, and shipment to a final disposal facility.

Report on research in carcinogenesis, human radiobiology, low-level radiation, molecular biology, and toxicology.

Investigation of the volcanic tuff beds of Yucca Mountain Nevada, as a potential site for a high-level waste repository is a function of the Nevada Nuclear Waste Storage Investigations (NNWSI). A series of tests with SRL 165 type glass was performed to determine whether the NNWSI Unsaturated Test could be used to produce data that would be useful in assessing waste form performance under unsaturated conditions anticipated for the NNWSI repository site.

Measurements are described for determining average values of fission rates in uranium-235, uranium-238 and plutonium-239 and capture rates in uranium-238 for heterogeneous cells used to construct fast critical assemblies. The measurements are based on irradiations of foils of uranium-238, uranium-235 and plutonium-239 with counting of fission and capture products using gamma-ray spectroscopy. Both plate and pin cells are considered. Procedures are described for inferring cell-average reaction rate values from a single foil location based on a cell using a quantity called a cell factor. Cell factors are determined from special measurements in which several foils are irradiated within a cell. Comparisons are presented between cell factors determined by measurements and by Monte Carlo calculations which lend credibility to the measurement procedures.

Eccentricity of a specific slip-joint design separating two cantilevered, telescoping tubes did not create any self-excited lateral vibrations that had not been observed previously for a concentric slip joint. In fact, the eccentricity made instabilities less likely to occur, but only marginally. Most important, design rules previously established to avoid instabilities for the concentric slip joint remain valid for the eccentric slip joint.

When calculations of flux are done in less than three dimensions, leakage-absorption cross sections are normally used to model leakages (flows) in the dimensions for which the flux is not calculated. Since the neutron flux is axially dependent, the leakages, and hence the leakage-absorption cross sections, are also axially dependent. Therefore, to obtain axial flux profiles (or reaction rates) for individual subassemblies, an XY-geometry calculation delineating each subassembly has to be done at several axial heights with space- and energy-dependent leakage-absorption cross sections that are appropriate for each height. This report discusses homogeneous and heterogeneous XY-geometry calculations at various axial locations and using several differing assumptions for the calculation of the leakage-absorption cross section. The positive (outward) leakage-absorption cross sections are modeled as actual leakage absorptions, but the negative (inward) leakage-absorption cross sections are modeled as either negative leakage absorptions (+-B² method) or positive downscatter cross sections (the ..sigma../sub s/(1 ..-->.. g) method).

Proceedings of a workshop of a unique group of physicists in the fields of high-energy, nuclear and atomic physics. The meeting was organized in a manner that stimulated discussion among the 58 participants and focused on developments in polarized target technology and the underlying atomic physics. An impressive array of future possibilities for polarized targets as well as current developments in polarized target technology were discussed at the workshop.

Quarterly report on activities of Argonne National Laboratory's Nuclear Technical Programs, including evaluation of the potential of radiolytic production of nitric acid or ammonia in a nuclear waste repository to cause degradation of bentonite-based backfill materials.

Research and development work on rechargeable lithium/molten salt batteries, sponsored by the US Department of Energy, has been under way at Argonne National Laboratory and several industrial laboratories for the past decade. In 1978, a program for the US Army (Belvoir R and D Center) was initiated with ANL and Eagle-Picher Industries to ascertain the status and to aid the development of the manufacturing technology of the Li-Al/FeS battery as a power source for forklift trucks. A long-lived cell, achieving greater than 1000 discharge cycles, was developed in the Army program and was used as a basis for a forklift truck battery design. The projected performance of the Li-Al/FeS battery showed a 200% increase in stored energy when compared with a lead-acid battery of equal volume.

Report on various studies in the physics division of Argonne National Laboratory, including medium-energy physics research, superconducting LINAC accelerator, and theoretical nuclear physics.

Report on activities of the Division of Biological and Medical Research in carcinogenesis, low level radiation, molecular biology, and toxicology.

Quarterly report discussing fuel cell research and development work at Argonne National Laboratory (ANL). This report describes activities directed toward seeking alternative cathode materials to NiO for molten carbonate fuel cells.

Tubes in shell-and-tube heat exchangers, including nuclear plant steam generators, derive their support from longitudinally positioned tube support plates (TSPs). Typically there is a clearance between the tube and TSP hole. Depending on design and fabrication tolerances, the tube may or may not contract all of the TSPs. Noncontact results in an inactive TSP which can lead to detrimental flow induced tube vibrations under certain conditions dependent on the resulting tube-TSP interaction dynamics and the fluid excitation forces. The purpose of this study is to investigate the tube-TSP interaction dynamics. Results of an experimental study of damping and natural frequency as functions of tube-TSP diametral clearance and TSP thickness are reported. Calculated values of damping ratio and frequency of a tube vibrating within an inactive TSP are also presented together with a comparison of calculated and experimental quantities.

A system has been designed to use CPC collectors to collect solar energy and to generate steam for industrial process heat purposes. The system is divided into two loops with the collectors in the collector loop to operate a pre-heater and the collectors in the boiler loop to heat water to elevated pressures and temperatures. A flash boiler is used to throttle the heated water to steam. Two types of CPC collectors are chosen. In the collector loop the CPC collectors are fitted with concentric tube receivers. In the boiler loop the collectors employ heat pipes to transmit heat. This design is able to alleviate the scaling and plumbing problems. A fragile receiver tube can also be employed without rupture difficulties. The thermal processes in the collectors were analyzed using a computer modeling. The results were also used to develop a thermodynamic analysis of the total system. Calculations show that the design is technically feasible. The CPC collector is shown to have an efficiency that is very weakly dependent on its operating temperatures, which makes the collector particularly attractive in high temperature applications.