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.

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.

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.

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.

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.

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.

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".

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."

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.

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.

Quarterly report discussing fuel cell research and development work at Argonne National Laboratory (ANL). This report describes activities directed toward understanding and improvement of molten-carbonate-electrolyte fuel cells operating at temperatures near 923 Kelvin.

Portions of the cesium-uranium-oxygen system have been investigated between 873 and 1273°K and a phase diagram has been constructed using our data and the data of other workers in the field. Thermodynamic and kinetic data have been used to examine the reactions that occur in fast-reactor fuel pins between fission-product cesium and the uranium oxide blanket. It was concluded that at the low oxygen potentials existing at the interface between the uranium-plutonium mixed-oxide and the uranium oxide blanket, Cs₂UO₄ is the only Cs-U-O compound expected to be formed in the uranium oxide blanket.

This report presents results from an investigation on the creep-fatigue and cyclic-deformation of Type 16-8-2 (16% Cr-8% Ni-2% Mo) stainless steel weld metal. Tests were conducted in air at 593 degrees C and a strain rate of 0.004 s⁻¹. Comparisons with data for Type 316 stainless steel base metal indicated that the weld metal has significantly longer fatigue lives for several tension hold-time tests. This is attributed to the fine duplex microstructure of the weld metal that inhibits the growth rate of cracks. Additional studies on the cyclic deformation behavior of the weld metal indicate that the material is strain-history dependent; therefore a unique stress-strain curve does not exist. Monotonic tension tests after cyclic straining result in a different stress-strain curve than obtained from companion fatigue tests at various completely reversed constant strain ranges. A comparison of the fracture morphology and creep-rupture specimens indicates that differences resulting from these tests can be attributed to different failure mechanisms.

The effects of cyclic strains at 4.2 K on the electrical resistivity of copper have been investigated as Phase I of a program to determine the overall effects on monolithic superconducting composites. This work is a direct application to the design of large superconducting magnets that are subject to several different modes of cyclic strain during assembly and normal operations.

This report discusses the effectiveness of the EBR-II fuel-element-rupture-detector (FERD) system which detects delayed-neutron-emitting fission products. It is demonstrated that FERD provides no reactor or public protection for loss-of-flow or transient-overpower fault events that affect the whole core; such protection is provided by other systems.

Quarterly report discussing fuel cell research and development work at Argonne National Laboratory (ANL). This report describes efforts directed toward understanding and improving the components of molten-carbonate-electrolyte fuel cells operated at temperatures near 925 K.

Report on electrochemical energy development, including development of advanced, high-temperature lithium/metal sulfide batteries for vehicle propulsion and stationary energy storage.

This report deals with the REXCO-code predictions of the SRI SM-2 test. Two calculations were performed with the REXCO-HEP code: one used the pressure history of the core detonation products as input and the other the pressure-volume relations of the detonation products as input. The other inputs of the computer analysis are the vessel and the core-barrel dimensions and boundary conditions, the constitutive equations of the vessel and the core barrel materials, and the equation of state for the coolant. The REXCO-predicted well deformations, pressure loadings, and dynamic strain histories at various gauge positions are compared with the experimental data. Results of the comparisons are discussed.