The design of the Argonaut (Argonne Nuclear Assembly for University Training) was initiated by the Reactor Engineering Division of Argonne National Laboratory to satisfy needs for a low-power reactor facility within the Laboratory, and for training uses within the international School of Nuclear Science and Engineering (ISNSE). It was intended primarily for instruction and research in reactor physics. It was also considered as a possibility that it would fulfill the requirements of universities engaged in a program of nuclear science. The cost of the facility was to be kept to a minimum consistent with the high degree of inherent safety and a great amount of flexibility in the system. The basic design stemmed from the Knolls Atomic Power Laboratory Thermal Test Reactor* (TTR), now called Nuclear Test Reactor (NTR). Modification during the course of the work justified the new name "Argonaut".

An improved continuous ether extractor is described. The modifications include a means of safely disposing of the active raffinate and a means of positivity checking the raffinate for completeness of uranium extraction. The results obtained on synthetic samples and on dissolver solutions are given. This work was undertaken because of a need for the determination of uranium in dissolver solutions with an accuracy of 0.1 per cent. After a review of available methods it was decided that a gravimetric determination would meet the requirements of precision and accuracy.

The ZPR-I is a facility to study low power critical assemblies using enriched uranium as fuel, having a light water moderator and an essentially infinite water reflector on all sides. The fuel is held in elements 43" long with a 1" square cross section. Any of these elements may be placed in or removed from any position in the reactor tank. Thus, any desired core configuration may be easily obtained.

This technical report describes work done on the electrolytic refining of natural uranium in fused salt baths composed of various eutectics of alkali metal chlorides in which were dissolved UF, or UCl3.

This report deals with the (1.1) physical properties of graphite, (1.2) effects of pile irradiation on the properties of graphite, (1.3) effect of irradiation on "ceramic" materials, (1.4) exposure and dosage for radiation damage experiments, (1.5) apparatus for the measurement of the thermal conductivity of solids, (1.6) effects of radiation on ice -- the thermoluminescence of ice, (1.7) investigation of color centers and other optical properties of single crystals. (2.1) radiation chemistry of liquids, (3.1) radiochemical investigation of the spontaneous fission of Cm242, (3.2) radiochemical service, (3.3) on the one-body model of alpha, (4.1) spectrographic analysis, (4.2) chemical analysis, (5.1) the 60-inch cyclotron.

Report describing the research and development activities related to nuclear chemistry and radiochemistry and basic chemistry conducted by the Argonne National Laboratory Chemistry Division, Section C-1.

This report covers the research and development activities of the program at Argonne National Laboratory (ANL) on lithium/iron sulfide batteries during the period October 1979-March 1980.

The research during 1980 in the Division of Biological and Medical Research, Argonne National Laboratory, is summarized. Research related to nuclear energy includes the delineation, in the6 eagle, of the responses to continuous low level Co gamma radiation and the development of cellular indicators of preclinical phases of leukemia; comparison of lifetime effects in mice of low level neutron and Co gamma radiation.

SLIDES is a program which takes text and commands as input and prepares lettered slides and posters. When run on the time-sharing computer, the program can display its output on an interactive graphics terminal; in batch, it can direct its graphical output to a variety of plotters. The program uses DISSPLA graphical subroutines and standard ANL plotter subroutines. This report contains material written for the novice computer user, who should be able to produce useful slides or posters by following the examples. This report also serves as a complete reference for the SLIDES program.

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.