EWR-ESE-144, Fifty MC-890 type final assemblies were subjected to irradiation at low temperature test in order to determine if irradiation would reduce the frequency of high voltage breakdowns. A control lot of a like number of units was subjected to low temperature test in the same manner except without irradiation.

Answers by ICPP personnel to questions asked by Eurochemic are given on a variety of subjects, including off-gas sampling systems, off-gas filtration, iodine evolution during fuel dissolution, and process cell contamination. Data are presented on the% of I/sup 131/ retained in waste solutions in the absence and presence of mercury. (D.L.C.)

An experimental investigation into the gas dynamics of a jet-driven vortex tube for application of a cavity nuclear reactor to rocket propulsion has shown that viscous retardation of the vortex motion is severe, because of a high level of turbulence near the periphery. Based on the experience gained in this study, it is estimated that the achievement of vortex strengths sufficient for practical application will require the use of small diameter tubes with appreciable expenditure of power for recirculation of the gas. The effect of the high degree of turbulence on the separation process near the periphery remains to be determined. The independent variables which were found to influence the vortex strength significantly for a given gas and temperature condition are the tube diameter, the mass flow rate per unit tube length, the injection velocity, and the wall pressure. Estimates of the degree of turbulence in vortex flow have been made from data on the variation in tangential velocity with radius. Virtual (total) viscosities near the periphery ranged from 30 to 700 times the molecular viscosity for tangential Reynolds numbers of from 4 x 10/sup 4/ to 2 x l0/sup 6/. Measurements of the position of the mole- fraction peak …

This monthly document details activities of the Hanford Operations Office during the month of March 1960. (FI)

This monthly document details activities of the Hanford Operations Office during the month of May 1960. (FI)

This report discusses the isothermal hydraulic demand characteristics were determined by laboratory experiment for full charges of self-supported I&E fuel elements in a zirconium process tube. Pressure drop, flow rate data, and the calculations of annulus-to-hole flow ratio are presented. For self-supported fuel elements, pressure drop does not vary with temperature as much as it dies for non-self-supported furl elements.

9 > ? ( ing schedule included MTR, ETR, and other aluminum-type fuels that were processed through the TBP headend at 75 to 100% of flowsheet rates and through the Hexone second and third cycle extraction system at up to l5O% of flowsheet values, achieving an over-all recovery of 99.60%. In carrying out basic studies on aqueous zirconium processing, results obtained during the potentiometric titration of zirconium-fluoride-nitric acid solutions with sodium hydroxide were explained by a mechanism in which the untitrated zirconium fluoride species is converted to a fluozirconate and further hydrolysis proceeds via a fluozirconate route. A modified Zirflex flowsheet for processing 2.5% U-Zr alloy fuels is proposed as a result of bench scale dissolution studies on unirradiated PWR plates that showed that dissolver solutions could be stabilized by adding aluminum nitrate and nitric acid. that higher ammonium fluoride concentrations increased the dissolution rate, that higher hydrogen peroxide concentrations lowered the dissolution rate and decreased solution stability, and that ammonia removal by boiling with or without air sparging had little effect on the reaction. Density curves for Zirflex solutions are reported. First tests of the pilot plant for continuous dissolution of zirconium-type elements have indicated that the dissolution rate …

The objective of this report is to summarize all in-reactor operating data associated with PT-288-A. This document will serve as a ready reference to the irradiation history of the fuel elements, and will record any anomalies encountered in the performance of this test.

The loop was charged October 30, 1959 with seven 12-inch Natural Uranium Zircaloy-2 clad 7-rod clusters. The test was primarily for the new hot-headed method of end closure used on these elements. The loop was pressure tested at 4000 psi after it was charged. Initially the loop was held at low-temperature to study the buildup of oxygen (presumably from radiolytic decomposition of water). After startup the neutron activity held at slightly above normal but the strainer gamma activity was exceptionally low. Frequent additions of LiOH bombs were necessary to maintain the pH at 10.0 (previously it was 4--5 pH but was raised to pH 10 for this test.) After the temperature was raised to operating conditions the pH held nicely at 10. On November 16, 1959, the heat exchanger exit temperature thermocouple blew out resulting in depressurization of the loop and a reactor scram. Repairs were made during the outage and the loop was returned to normal operation. Eleven scrams occurred during the test period caused by 105-KE or 1706-KER.

A procedure is reported for the sea disposal. by fixation in concrete. of ion-exchange resins containing sorbed fission products and filtered corrosion products. The results of sea disposal of both treated and untreated resins is presented. For the fixation of nuclear-reactor-system demineralizer resin in cement, a mixture of 2 parts of cement, 1 part of resin, and 1 part of water was found to be optimum. A concrete block prepared by this receipt showed only 0.44% of the gross gamma activity leached after 2540 hr of contact with simulated sea water. The data indicate that very little or no further leaching will occur. (auth)

None

Research efforts in neutron physics are reported in the areas of light- water-moderated reactors, new reactors for BSF and TSF, critical experiments, experimental nuclear physics, experimental reactor physics, reactor theory, shielding research, radiation detector studies, plasma physics theory, and theoretical nuclear physics. Separate abstracts were prepared for the seventy sections of the report. (W.D.M.)

A discussion of the hazards and philosophy of plutonium handling is presented. Glove box construction and materials are also discussed along with handling techniques and work being done with plutonium in various parts of this country. (J.R.D.)

The objective of the production test detailed in this report is to evaluate the behavior of N-Reactor inner fuel tubes during irradiation in the KER Loops at conditions equivalent to those expected in the N-Reactor. Natural and .947% enriched Zircaloy-2 jacketed N-Reactor inner fuel tubes (NIN-1) and (NIE-1) will be irradiated in the KER Loops to exposures no greater than 3500 MWD/T. The elements have brazed end closures and Zircaloy-2 supports and are contained in Zr-2 flow distributing sleeves.

This memorandum discusses coupling of the reactor exhaust system to the filter building, under Project CG-791, which will require diversion of the 105 Building exhaust air to two temporary stacks. The temporary stacks will be installed over each of two exhaust fans. The use of these temporary (short) stacks during the tie-in period (estimated at 8 to 16 days) could greatly aggravate radiological problems because of reduced dilution and of the reactor building exhaust air. Special operating requirements are given.

Specifications were prepared for control rod fuel elements for the Core Il of PM-2A. These stainless steel-base fuel components of thin plate-type construction and containing a dispersion of UO/sub2/ were successfully used in powering the Army Package Power Reactor. The component, which consisted of sixteen composite fuel plates joined by brazing, was designed for radioactive service in pressurized water. Tests for qualification of fabrication procedures and specifications covening loading, materials, and processing are presented. Also included are drawings and the process flow diagram. (M.C.G.)

Specifications were prepared for the control rod absorber sections for Core Il of Army Reactor PM-2A. The neutron absorber section was composed of composite plates welded into the form of a rectangular parallelepiped. The composite plates were made of compacts of europium oxide in a stainless steel matrix clad with stainless steel by hot-roll bonding. Specifications covering materials and processes are included in the repont along with fabrication qualification tests. (M.C.G.)

Specifications were prepared for stationary fuel elements for PM-2A Core Il. Stainless steel-base fuel compcnents of thin plate-type construction and containing a dispersion of UO/sub 2/ were successfully used in the Army Reactor (SM-1). The component consisted of eighteen composite fuel plates joined by brazing, and was designed for radioactive service in pressurized water. Fabrication qualification tests and specifications covering loading, materials, and processing are presented. Also included are applicable drawings and the process flow diagram. (M.C.G.)

Stainless steel-base fuel components of thin plate-type construction and containing a dispersion of UO/sub 2/ were successfully employed in powering the Army Package Power Reactor. The component is designed for radioactive service in pressurized water and consists of sixteen composite fuel plates Joined into an integral unit or assembly by brazing. Specifications covering loading, materials, and processing are presented. A list of applicable drawings and the process flow diagram are included. (auth)

The composite plates of the absorber section consist of compacts of europium oxide-- stainless steel clad with stainless steel by hot roll-bonding. Specifications are given to cover materials, dimensional and finish requirements, tests for quallfication of absorber plate fabrication, the conformance of fabrication procedure, and the manufacturing procedures. Drawings are also included. (M.C.G.)

Stainless steel-base fuel components of thin plate-type construction and containing a dispersion of UO/sub 2/ were successfully employed in powering the Array Package Power Reactor (SM-1). The component is designed for radioactive service in pressurized water and consists of eighteen composite fuel plates joined into an integral unit or assembly by brazing. Specifications are presented which cover loading, mterials, and processing. A list of applicable drawings and a process flow diagram are included. (auth)

An investigation of the stabilizing influence of oxide additions to uranium oxide was continued. These additions are employed to eliminate the phase transformation to U/sub 3/O?sub 8/ which occurs when UO/sub 2/ is exposed to an oxidizing environment at elevated temperatures and to reduce the volatility or transpiration losses of uranium oxide which become appreciable in air at temperatures in excess of 1200 deg C. The results show that CaO may be successfully employed in partial substitution for La/sub 2/O/sub 3/ and Y/sub 2/O/ sub 3/. The resulting solid solutions exhibited high-temperature stability comparable to that of the "binary" solid solutions of UO/sub 2/ containing La/sub 2/O/sub 3/ or Y/sub 2/O/sub 3/. On the basis of thes e and other results some alternative approaches appear possible to reduce the amount and cross section of additive required for stabilization. (auth)

A series of isothermal heat treatments was performed on the highly ordered Al- Fe alloy, 13.6 Alfenol. Resistivity vs. time curves are presented for temperatures of 0 to 700 deg C. (For preceding period see TM-5730.) (C.J.G.)

The filtration and pressure drop-flow rate characteristics of MC 1478 filter paper was determined over wide ranges in pressure 1/20 to 1/5 atm.) ard temperature (--40, 0, and 70 deg F). The retention of SiO/sub 2/ spherical particles by the filter paper at a flow rate of 5000 ft/min at 1/20 atm. pressure and 70 deg F was found to be essentially 100%. The retention (generally 30 to 75%) for aluminum oxide particles (about 40 A) and pressure drop were determined over wide ranges in pressure, temperature, and flow rate, The application of kinetic theory to small particle diffusion in a gas is discussed. The theory of diffusion of particles from a streaming gas to the tube wall was evolved and applied to the estimation of particle size. (C.J.G.)