None

Physical and inorganic Chemistry. Studies are reported on: volatile complexes of ZrCl/sub 4/ and HfCl/sub 4/ with POCl/sub 3/; reaction of UCl/sub 4/ with LiAlH/sub 4/; preparation and properties of metal uranates and polyuranates; heats of solution of UO/sub 2/(NO/sub 3/)/sub 2/ hydrates; absorption spectra of Np in HClO/sub 4/, and separation of Np and Pu chlorides by a flow method. Process Chemistry. Extraction of Th from Mailiackrodt U raffinate was studied. Nuclear Chemistry aad Radiochemistry. Invesigations were carried out on: organic tritium; exchange reactions of U ions in solution; exchange reactions of Fe in aqueous solutions: Tc recovery from old Hanford slugs; (a,2n) cross section of Pa/sup 231/; and spontaneous fission counting U/sup 236/ and Pu/sup 238. (T.R.H) l822 Nuclear Chemistry and Radiochemistry. Measurements of the half- lives of Ac/sup 227/ and RaD(Pb/sup 210/) were continued. The effective pile neutron capture cross sections for U/sup 236/ were determined by measuring the activity of the resultant U/sup 237/ with an end window geiger counter. A study of ion chambers for tritium analysis is presented. Procedures were developed for the determination of tritium and C/sup 14/ in onganic compounds. Physical and Inorganic Chemistry. An investigation of the electrochemistry of Np in …

None

None

It was the purpose of this study to determine whether it will be more desirable when activatiing Task I of the RMA. Line to revise the existing remotely operated equipment or to remove existing equipment and install a manually operated facility. It was also the purpose of this study to provide sketches and cost estimates for each alternative which could be used as a guide for preparation of a Project Proposal. At present, the process to be used in Task I has not been established. This study, therefore, necessarily covers only processes similar to those for which Task I was originally designed. Information received from the Process Unit indicates adoption of such a process is probable.

None

This chapter presents the highlights of the fabrication and heat treatment of uranium with emphasis on HAPO type core material. For pile use three properties of uranium are of prime interest; grain size, type and degree of preferred orientation, and the mechanical properties.

Modifications are described in the nuclear instrumentation system of the Shippingport Pressurized Water Reactor designed to monitor neutron flux level from source to 150% of reactor designed full power output, to compute the rate of change of the neutron flux level for indication and control, and to provide level and rate of change of level signals for reactor shutdown to prevent reactor damage. (C.H.)

The interpretation of the dimensional instability of U- Zr alloy containing small amounts of boron has raised the question of whether the observed low-temperature swelling can be related to the temperatureswelling characteristics of either the U-Zr alloy or Zr- B alloys by themselves. To obtain such information on the Zr--B system to compare with the more detailed study of thc alloy early results of which were reported in KAPL-1562, pieces of previously irradiated Zr- B alloys and dispersions were annealed in vacuum at temperatures between 350 and 750 C. (auth)

The theory of energy transfer between charged particles in a fully ionized gas is reviewed, and calculations are made of the rate at which energy is transferred from electrons at a temperature T to cooler ions. The interaction between ion and electron is assumed to be of the Debye form (Ze/r) exp (-r/ lambda ), where lambda is the Debye shielding length. It is suggested that future improvements of the theory of Coulomb interaclions in ionized gases are likely to be made in two ways: through employing an effective potential derived on the basis of quantum statistics for the electrons and through improvements in the two-body approximation to the many-body problem. (auth)

Transient effects of making step changes of the core dump tank concentration are studied for single-region operation of the Homogeneous Reactor Test. It is assumed that the feed and the letdown streams are only between the core high-pressure system and the core dump tanks, and that transfer of fuel to or from the blanket can only be made through the core high pressure system. Transfer rates between the HRT highpressure systems of 75 to 100 lb/min will give reasonable mixing times, about 4 hours, without peaking of fuel concentration which may cause premature critical conditions in the core. Lower transfer rates could be used for lower feed rates, but the mixing time will be longer. Transfer rates greater than 100 lb/min would not shorten the mixing time appreciably and, therefore, they need not be considered. (auth)

Three simultaneous polar-coordinate component equations in an aximuthally homogeneous magnetic field of a cyclotron are integrated by a fixed- point program on the IBM 650 computer to give the orbits of particles in the cyclotron. A regenerator action for extracting particles is computed as an inpulse once each turn as a subprogram when desired. The program is described and instructions for its use are included. (auth)

ABS>A series of seven flowsheet demonstrations of the Volatility Process was performed using nonirradiated material. In this series (a) the Pilot Pland was proven to be operable but not sufficiently reliable for remote operation; (b) the feasibility of a bed of NaF pellets as a trap for Cr aad Zr fluorides was demonstrated; and (c) the most desirable fluorine flow rate for fluorination of molten salt in the existing equipment was determined to be in the range 10 to 30 std. liters per min. (auth)

The burns to the skin of anesthetized rats were determined for the thermal radiation pulses of a carbon arc on a hot-wet uniform when spaced 5 mm from the skin. The radiant exposures to cause burns resulting in eschar were tion pulses corresponding to 250, 1000, 2900, and 10,000 kiloton detonations, respectively. The threshold lesions were caused by volatile products not associated with ignition. The associated temperatures were recorded. (auth)

In 1958, planned large scale use of the new I & E slug geometry at more severe operating conditions than had been generally experienced suggested a possible compromise in reactor life and safety if a reasonable degree of rupture control with the new type of element was not maintained. The formalized slug corrosion limit (Top-of-Annulus limit) was issued as a Process Standard at the time of the full-scale loading of I & E geometry fuel elements to provide this limit for reactor operation. The loading of I & E slugs at all reactors has been accomplished and initial power level increases have been made. To date, 67 I & E ruptures have been sustained including both `hole` and `annulus` failures. The type and behavior of ruptures to be expected with I & E geometry are now characterized. Recent studies have indicated that the I & E failure experience is consistent with the general mathematical rupture model formulated from analysis of solid slug experience. Increased confidence in the use of this model in combination with Optimization Studies permits greater emphasis to be placed on the rupture model as a guide for reactor operation. It is the purpose of this report to …

Areas covered in this report are as follows: nuclear safety in the Fuel Preparation Dept.; studies related to the present production reactors; studies related to future production reactors; studies related to separation plants; studies form the neutron cross section program; reactor development (gas cooled reactor program and test reactor operations); and biology and medicine.

The corrosion behavior of types 304L and 309SCb stainless steel was examined during the production and first half of the development periods of Thorex pilot plant operation between December 15, 1954 and November 10, 1955. The process vessels in which corrosion data were obtained included the batch dissolver tank the feed adjustment tank the AP catch tank and the BT vapor separator. There was no significant difference between the corrosion resistance of the two alloys in any of the environments. Vapor-phase corrosion attack in some vessels was more severe than solution-phase attack in the same vessels, Dependent upon the particular process environment, corrosion rates in the vapor phase ranged from 0.1 to 46 mpy; solution-phase corrosion rates ranged from 0.1 to 28 mpy. The most severe attack in both solution and vapor phases occurred in the feed adjustment tank There was serious corrosion in the BT vapor separator also. Corrosion was moderate (8 mpy or less) in the batch dissolver tank and was almost negligible (0.2 mpy or less) in the AP catch tank. The attack on rolled surfaces of both types of stainless steel was uniform, with the exception that shallow, intergranular penetration was experienced in the more corrosive …

The hot-water corrosion resistance and mechanical properties of niobium and a number of its alloys were evaluated relative to their usefulness in pressurized-water thermal reactors. Unalloyed niobium was found to be rapidly attacked by 600 and 680 deg F water and 750 F steam. A number of alloying additions were found which markedly improve the corrosion resistance of niobium. Of these, binary and ternary combinations of chromium, molybdenum, titanium, vanadium, and zirconium were among the most effective. Many of these alloys exhibited as low or lower weight gains than those obtained for Zircaloy-2 under similar test conditions. Most of the niobium-base alloys tested for strength exhibited excellent resistance to creep at temperatures up to 1200 deg F under stresses through 20,000 psi. (auth)

The external holdup of expensive materials and associated capital costs for the heat removal systems of fluid fuel breeders were determined. The aqueous homogeneous and molten salt breeders were found to contain substantially less uranium holdup external to the core than the liquid metal fueled breeder. The cost of heat removal and turbogenerator plant equipment for the three systems was compared. (auth)

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

The polarization of the neutrons produced by photodisintegration of deuterium by 2.75-Mev gamma rays was measured and the results compared to theoretical predictions. The photoneutrons were tsken at five gamma-ray-neutron angles between 45 and 135 deg in the laboratory and scattered from magnesium which has a broad resonance at these neutron energies. Tne polarization was determined from the asymmetry in the left-right scattering from magnesium. The neutrons are found to be negatively polarized as predicted. The magnitude of the polarization and the dependence on the gamma-ray-neutron angle were found to be in agreement with the theory within experimental error. (auth)

The results of test stand studies of a pneumatic atomizing nozzle to be used in the Demonstrational Waste Calcining Facility at the Idaho Chemical Processing Plant are presented. Atomization and performance characteristics are described. The liquid feed control system for the Demonstrational Waste Calciner is compared with results of bench scale tests, and recommendations are made for improving the system. (auth)

None

This document is divided into: byproduct horizontal control rod system (5 reactors); high-speed scanning-effluent temperature monitoring system (KE reactor); improved reactor gas system (100-KE & KW); safety circuit system modifications (5 reactors); alternate process hot die sizing, 313 Building 300 Area; button line equipment (234-5 Building); in-tank waste solidification (3rd unit); and misc. minor equipment projects.